sphinx.addnodesdocument)}( rawsourcechildren](docutils.nodestarget)}(h.. _2-0:h]
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lineKparenthhhsourceE/Users/john/Documents/SCALE-test/docs/Criticality Safety Overview.rstubh section)}(hhh](h title)}(hCriticality Safetyh]h TextCriticality Safety}(hh,h h*hhh!NhNubah}(h]h]h]h]h]uhh(h h%hhh!h"hKubh paragraph)}(h!**Introduction by B. T. Rearden**h]h strong)}(hh>h]h/Introduction by B. T. Rearden}(hhh hBubah}(h]h]h]h]h]uhh@h hFor many criticality safety applications, the additional step of
performing a deterministic calculation to initialize the starting
fission source distribution is not necessary. However, for challenging
criticality safety analyses such as as-loaded spent nuclear fuel
transportation packages with a mixed loading of low- and high-burnup
fuel, even a low-fidelity deterministic solution for the fission source
produces more reliable results than the typical starting distributions
of uniform or cosine functions over the fissionable regions, as
demonstrated in a recent study }(hX>For many criticality safety applications, the additional step of
performing a deterministic calculation to initialize the starting
fission source distribution is not necessary. However, for challenging
criticality safety analyses such as as-loaded spent nuclear fuel
transportation packages with a mixed loading of low- and high-burnup
fuel, even a low-fidelity deterministic solution for the fission source
produces more reliable results than the typical starting distributions
of uniform or cosine functions over the fissionable regions, as
demonstrated in a recent study h jhhh!NhNubh_)}(hibrahim_hybrid_2013h]he)}(hjh]h/[ibrahim_hybrid_2013]}(hhh jubah}(h]h]h]h]h]uhhdh jubah}(h]id8ah]hwah]h]h] refdomainh|reftypeh~ reftargetjrefwarnsupport_smartquotesuhh^h!h"hKqh jhhubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!h"hKqh h%hhubh;)}(hC**Criticality Accident Alarm System Analysis with KENO and MAVRIC**h]hA)}(hjh]h/?Criticality Accident Alarm System Analysis with KENO and MAVRIC}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!h"hK{h h%hhubh;)}(hXCriticality accident alarm systems (CAAS) safety analyses modeling
presents challenges because the analysis consists of a criticality
problem and a deep-penetration shielding problem :cite:`peplow_criticality_2009`. Modern codes are
typically optimized to handle one of these types of problems, but not
both. The two problems also differ in size—the criticality problem
depends on materials relatively close to the fissionable materials,
whereas the shielding problem can cover a much larger range.h](h/Criticality accident alarm systems (CAAS) safety analyses modeling
presents challenges because the analysis consists of a criticality
problem and a deep-penetration shielding problem }(hCriticality accident alarm systems (CAAS) safety analyses modeling
presents challenges because the analysis consists of a criticality
problem and a deep-penetration shielding problem h jhhh!NhNubh_)}(hpeplow_criticality_2009h]he)}(hjh]h/[peplow_criticality_2009]}(hhh jubah}(h]h]h]h]h]uhhdh jubah}(h]id9ah]hwah]h]h] refdomainh|reftypeh~ reftargetjrefwarnsupport_smartquotesuhh^h!h"hK}h jhhubh/X. Modern codes are
typically optimized to handle one of these types of problems, but not
both. The two problems also differ in size—the criticality problem
depends on materials relatively close to the fissionable materials,
whereas the shielding problem can cover a much larger range.}(hX. Modern codes are
typically optimized to handle one of these types of problems, but not
both. The two problems also differ in size—the criticality problem
depends on materials relatively close to the fissionable materials,
whereas the shielding problem can cover a much larger range.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!h"hK}h h%hhubh;)}(hXCAAS analysis can be performed using the CSAS6 criticality sequence and
the MAVRIC shielding sequence. First, the fission distribution (in space
and energy) is determined via CSAS6. This information is collected on a
grid geometry that overlies the physical geometry model and is saved as
a Monaco mesh source file. The mesh source is then used as the source
term in MAVRIC. The absolute source strength is set by the user to the
total number of fissions (based on the total power released) during the
criticality excursion. MAVRIC can be optimized to calculate a specific
detector response at one location or to calculate multiple
responses/locations with roughly the same relative uncertainty.h]h/XCAAS analysis can be performed using the CSAS6 criticality sequence and
the MAVRIC shielding sequence. First, the fission distribution (in space
and energy) is determined via CSAS6. This information is collected on a
grid geometry that overlies the physical geometry model and is saved as
a Monaco mesh source file. The mesh source is then used as the source
term in MAVRIC. The absolute source strength is set by the user to the
total number of fissions (based on the total power released) during the
criticality excursion. MAVRIC can be optimized to calculate a specific
detector response at one location or to calculate multiple
responses/locations with roughly the same relative uncertainty.}(hjh j
hhh!NhNubah}(h]h]h]h]h]uhh:h!h"hKh h%hhubh;)}(hhh](h h|)}(hhh](h label)}(hhh]h/,us_nuclear_regulatory_commission_burnup_2012}(hhh j$ubah}(h]h]h]h]h]support_smartquotesuhj"h jubh;)}(hhh](h/US}(hUSh j2ubh/ }(h h h;)}(hhh](h/Seth}(hSethh j?ubh/ }(hj>h j?ubh/R. Johnson.}(hR. Johnson.h j?ubh/ }(h h j?ubh/8Fast mix table construction for material discretization.}(h8Fast mix table construction for material discretization.h j?ubh/ }(hjTh j?ubh/In }(hIn h j?ubh)}(hhh](h/Proceedings of the 2013 }(hProceedings of the 2013 h jcubh/
International}(h
Internationalh jcubh/ }(hjTh jcubh/
Conference}(h
Conferenceh jcubh/ on }(h on h jcubh/Mathematics}(hMathematicsh jcubh/ and }(h and h jcubh/
Computational}(h
Computationalh jcubh/ }(hjTh jcubh/Methods}(hMethodsh jcubh/ }(hjTh jcubh/Applied}(hAppliedh jcubh/ to }(h to h jcubh/Nuclear}(hNuclearh jcubh/ }(hjTh jcubh/Science}(hScienceh jcubh/ and }(h and h jcubh/Engineering}(hEngineeringh jcubh/-}(h-h jcubh/M}(hMh jcubh/ and }(hjh jcubh/C}(hCh jcubh/ 2013}(h 2013h jcubeh}(h]h]h]h]h]uhhh j?ubh/. 2013.}(h. 2013.h j?ubeh}(h]h]h]h]h]uhh:h j)}(hhh](j#)}(hhh]h/johnson_fast_2013}(hhh jubah}(h]h]h]h]h]j1uhj"h jubj?eh}(h]johnson-fast-2013ah]hwah]johnson_fast_2013ah]h]id59adocnameCriticality Safety Overviewuhh|h h;)}(hhh](j)}(hhh](j#)}(hhh]h/evans_denovo_2010}(hhh jubah}(h]h]h]h]h]j1uhj"h jubh;)}(hhh](h/Thomas}(hThomash jubj<h/M. Evans, Alissa}(hM. Evans, Alissah jubj<h/S. Stafford, Rachel}(hS. Stafford, Rachelh jubj<h/N. Slaybaugh, and Kevin}(hN. Slaybaugh, and Kevinh jubj<h/
T. Clarno.}(h
T. Clarno.h jubj\h/Denovo: }(hDenovo: h jubh/A}(hAh jubh/; new three-dimensional parallel discrete ordinates code in }(h; new three-dimensional parallel discrete ordinates code in h jubh/SCALE}(hSCALEh jubh/.}(hjh jubj\h)}(hhh]h/Nuclear technology}(hNuclear technologyh jGubah}(h]h]h]h]h]uhhh jubh/, 171(2):171–200, 2010.}(h, 171(2):171–200, 2010.h jubj\h/Publisher: Taylor & Francis.}(hPublisher: Taylor & Francis.h jubeh}(h]h]h]h]h]uhh:h jubeh}(h]id71ah]hwah]h]evans_denovo_2010ah]jjuhh|
referencedKh jubj)}(hhh](j#)}(hhh]h/goluoglu_monte_2011}(hhh jqubah}(h]h]h]h]h]j1uhj"h jnubh;)}(hhh](h/Sedat Goluoglu, Lester}(hSedat Goluoglu, Lesterh j~ubj<h/ M. Petrie}(h M. Petrieh j~ubj<h/Jr, Michael}(hJr, Michaelh j~ubj<h/E. Dunn, Daniel}(hE. Dunn, Danielh j~ubj<h/F. Hollenbach, and Bradley}(hF. Hollenbach, and Bradleyh j~ubj<h/T. Rearden.}(hT. Rearden.h j~ubj\h/Monte }(hMonte h j~ubh/Carlo}(hCarloh j~ubh/2 criticality methods and analysis capabilities in }(h2 criticality methods and analysis capabilities in h j~ubh/SCALE}(hSCALEh j~ubh/.}(hjh j~ubj\h)}(hhh]h/Nuclear Technology}(hNuclear Technologyh jubah}(h]h]h]h]h]uhhh j~ubh/, 174(2):214–235, 2011.}(h, 174(2):214–235, 2011.h j~ubj\h/Publisher: Taylor & Francis.}(hPublisher: Taylor & Francis.h j~ubeh}(h]h]h]h]h]uhh:h jnubeh}(h]id72ah]hwah]h]goluoglu_monte_2011ah]jjuhh|jmKh jubj)}(hhh](j#)}(hhh]h/ibrahim_improving_2009}(hhh jubah}(h]h]h]h]h]j1uhj"h jubh;)}(hhh](h/Ahmad}(hAhmadh jubj<h/M. Ibrahim, Douglas}(hM. Ibrahim, Douglash jubj<h/E. Peplow, Thomas}(hE. Peplow, Thomash jubj<h/M. Evans, John}(hM. Evans, Johnh jubj<h/C. Wagner, and Paul}(hC. Wagner, and Paulh jubj<h/
PH Wilson.}(h
PH Wilson.h jubh/ }(h h jubh/Improving the }(hImproving the h jubh/Mesh}(hMeshh jubh/ }(h h jubh/
Generation}(h
Generationh jubh/ }(h h jubh/Capabilities}(hCapabilitiesh jubh/ in the }(h in the h jubh/SCALE}(hSCALEh jubh/ }(h h jubh/Hybrid}(hHybridh jubh/ }(h h jubh/ Shielding}(h Shieldingh jubh/ }(h h jubh/Analysis}(hAnalysish jubh/ }(hjh jubh/Sequence}(hSequenceh jubh/.}(hjh jubj\h)}(hhh]h/Trans. Am. Nucl. Soc}(hTrans. Am. Nucl. Soch jfubah}(h]h]h]h]h]uhhh jubh/, 100:302, 2009.}(h, 100:302, 2009.h jubeh}(h]h]h]h]h]uhh:h jubeh}(h]ibrahim-improving-2009ah]hwah]ibrahim_improving_2009ah]h]id58ajjuhh|h jresolvedKubjeh}(h]1bibtex-bibliography-Criticality Safety Overview-5ah]h]h]h]uhh:h h$)}(hhh](h))}(hSample Problemsh]h/Sample Problems}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!DEVC.rsthMubh;)}(hXMSample problems have been made that correspond to the eight CSAS6 sample
problems. In each problem, the KENO parameters block was commented out,
a parameters block containing Denovo calculation parameters was added,
and a grid geometry block was added. These sample problems use a coarse
discretization and loose tolerances to obtain a short runtime. Users
will typically use much finer discretization (mesh, quadrature) and
higher fidelity parameter settings for real eigenvalue calculations. The
voxelized geometry and starting source distribution are shown below in
:numref:`fig2-4a-9`.h](h/X9Sample problems have been made that correspond to the eight CSAS6 sample
problems. In each problem, the KENO parameters block was commented out,
a parameters block containing Denovo calculation parameters was added,
and a grid geometry block was added. These sample problems use a coarse
discretization and loose tolerances to obtain a short runtime. Users
will typically use much finer discretization (mesh, quadrature) and
higher fidelity parameter settings for real eigenvalue calculations. The
voxelized geometry and starting source distribution are shown below in
}(hX9Sample problems have been made that correspond to the eight CSAS6 sample
problems. In each problem, the KENO parameters block was commented out,
a parameters block containing Denovo calculation parameters was added,
and a grid geometry block was added. These sample problems use a coarse
discretization and loose tolerances to obtain a short runtime. Users
will typically use much finer discretization (mesh, quadrature) and
higher fidelity parameter settings for real eigenvalue calculations. The
voxelized geometry and starting source distribution are shown below in
h jhhh!NhNubh_)}(h:numref:`fig2-4a-9`h]h literal)}(hjh]h/ fig2-4a-9}(hhh jubah}(h]h](xrefstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarn reftarget fig2-4a-9uhh^h!jhMh jubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jhhubh;)}(hXResults for the sample problems are displayed in :numref:`tab2-4a-10`. The
sample problems used QR 1/1, a P\ :sub:`0` scattering expansion, a k
tolerance of 0.001 and coarse meshes for speed. The higher fidelity runs
used finer spatial meshes, default parameters of QR 2/2, *P*\ :sub:`0`
scattering expansion, and the default *k* tolerance (10:sup:`-5`).
Results for the longer-time CSAS6 and higher fidelity Denovo
calculations are shown in :numref:`fig2-4a-10`.h](h/1Results for the sample problems are displayed in }(h1Results for the sample problems are displayed in h jhhh!NhNubh_)}(h:numref:`tab2-4a-10`h]j)}(hjh]h/
tab2-4a-10}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnj
tab2-4a-10uhh^h!jhMh jubh/(. The
sample problems used QR 1/1, a P }(h(. The
sample problems used QR 1/1, a P\ h jhhh!NhNubh subscript)}(h:sub:`0`h]h/0}(hhh j ubah}(h]h]h]h]h]uhjh jubh/ scattering expansion, a k
tolerance of 0.001 and coarse meshes for speed. The higher fidelity runs
used finer spatial meshes, default parameters of QR 2/2, }(h scattering expansion, a k
tolerance of 0.001 and coarse meshes for speed. The higher fidelity runs
used finer spatial meshes, default parameters of QR 2/2, h jhhh!NhNubh)}(h*P*h]h/P}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h:sub:`0`h]h/0}(hhh j/ubah}(h]h]h]h]h]uhjh jubh/'
scattering expansion, and the default }(h'
scattering expansion, and the default h jhhh!NhNubh)}(h*k*h]h/k}(hhh jBubah}(h]h]h]h]h]uhhh jubh/ tolerance (10:sup:}(h tolerance (10:sup:h jhhh!NhNubh title_reference)}(h`-5`h]h/-5}(hhh jWubah}(h]h]h]h]h]uhjUh jubh/Z).
Results for the longer-time CSAS6 and higher fidelity Denovo
calculations are shown in }(hZ).
Results for the longer-time CSAS6 and higher fidelity Denovo
calculations are shown in h jhhh!NhNubh_)}(h:numref:`fig2-4a-10`h]j)}(hjlh]h/
fig2-4a-10}(hhh jnubah}(h]h](jstd
std-numrefeh]h]h]uhjh jjubah}(h]h]h]h]h]refdocj refdomainjxreftypenumrefrefexplicitrefwarnj
fig2-4a-10uhh^h!jhMh jubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jhhubh)}(h.. _fig2-4a-9:h]h}(h]h]h]h]h]h fig2-4a-9uhh
hM,h jhhh!jubh figure)}(hhh](h image)}(h.. figure:: figs/DEVC/fig9.png
:align: center
:width: 600
Denovo geometry (left) and starting source distribution (right) for the sample problems.
h]h}(h]h]h]h]h]width600urifigs/DEVC/fig9.png
candidates}*jsuhjh jh!jhMubh caption)}(hXDenovo geometry (left) and starting source distribution (right) for the sample problems.h]h/XDenovo geometry (left) and starting source distribution (right) for the sample problems.}(hjh jubah}(h]h]h]h]h]uhjh!jhMh jubeh}(h](id116jeh]h] fig2-4a-9ah]h]aligncenteruhjhMh jhhh!jexpect_referenced_by_name}jjsexpect_referenced_by_id}jjsubh)}(h.. _fig2-4a-10:h]h}(h]h]h]h]h]h
fig2-4a-10uhh
hM,h jhhh!jubj)}(hhh](j)}(h.. figure:: figs/DEVC/fig10.png
:align: center
:width: 500
Fission source distributions computed by CSAS6 (left) and Denovo (right).
h]h}(h]h]h]h]h]width500urifigs/DEVC/fig10.pngj}jjsuhjh jh!jhMubj)}(hIFission source distributions computed by CSAS6 (left) and Denovo (right).h]h/IFission source distributions computed by CSAS6 (left) and Denovo (right).}(hjh jubah}(h]h]h]h]h]uhjh!jhMh jubeh}(h](id117jeh]h]
fig2-4a-10ah]h]jcenteruhjhMh jhhh!jj}jjsj}jjsubh table)}(hhh](h))}(hSample problem resultsh]h/Sample problem results}(hjh jubah}(h]h]h]h]h]uhh(h!jhMh j
ubh tgroup)}(hhh](h colspec)}(hhh]h}(h]h]h]h]h]colwidthKduhj#h j ubh tbody)}(hhh]h row)}(hhh]h entry)}(hhh]j)}(h.. image:: figs/DEVC/tab10.pngh]h}(h]h]h]h]h]urifigs/DEVC/tab10.pngj}jjIsuhjh j;h!jhKubah}(h]h]h]h]h]uhj9h j6ubah}(h]h]h]h]h]uhj4h j1ubah}(h]h]h]h]h]uhj/h j ubeh}(h]h]h]h]h]colsKuhjh j
ubeh}(h]
tab2-4a-10ah]h]
tab2-4a-10ah]h]jcenteruhjh jhhh!NhNubjh)}(h.. _2-5:h]h}(h]h]h]h]h]hid62uhh
hM,h jhhh! KMART.rstubeh}(h]id61ah]h]h]sample problemsah]uhh#h h$)}(hhh](h))}(hESourcerer: Deterministic Starting Source for Criticality Calculationsh]h/ESourcerer: Deterministic Starting Source for Criticality Calculations}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!
Sourcerer.rsthKubh;)}(hG*D. E. Peplow, A. M. Ibrahim, K. B. Bekar, C. Celik, and B. T. Rearden*h]h)}(hjh]h/ED. E. Peplow, A. M. Ibrahim, K. B. Bekar, C. Celik, and B. T. Rearden}(hhh jubah}(h]h]h]h]h]uhhh jubah}(h]h]h]h]h]uhh:h!jhKh jhhubh;)}(hXThe Sourcerer sequence in SCALE deterministically computes a fission
distribution and uses it as the starting source in a Monte Carlo
eigenvalue criticality calculation. Using a reasonably accurate starting
source, developed from the Denovo discrete-ordinates code through the
DEVC sequence, Sourcerer improves the KENO/CSAS Monte Carlo calculation
in two ways. First, the number of skipped generations required to
converge the fission source distribution in the KENO solution is
reduced. Second, for problems with loosely coupled fissionable areas,
the reliability of the final eigenvalue
(:math:`k_{\mathrm{\text{eff}}}`) is increased. Several convergence
diagnostic capabilities available in the KENO codes help the user better
measure when the fission source actually convergences.h](h/XOThe Sourcerer sequence in SCALE deterministically computes a fission
distribution and uses it as the starting source in a Monte Carlo
eigenvalue criticality calculation. Using a reasonably accurate starting
source, developed from the Denovo discrete-ordinates code through the
DEVC sequence, Sourcerer improves the KENO/CSAS Monte Carlo calculation
in two ways. First, the number of skipped generations required to
converge the fission source distribution in the KENO solution is
reduced. Second, for problems with loosely coupled fissionable areas,
the reliability of the final eigenvalue
(}(hXOThe Sourcerer sequence in SCALE deterministically computes a fission
distribution and uses it as the starting source in a Monte Carlo
eigenvalue criticality calculation. Using a reasonably accurate starting
source, developed from the Denovo discrete-ordinates code through the
DEVC sequence, Sourcerer improves the KENO/CSAS Monte Carlo calculation
in two ways. First, the number of skipped generations required to
converge the fission source distribution in the KENO solution is
reduced. Second, for problems with loosely coupled fissionable areas,
the reliability of the final eigenvalue
(h jhhh!NhNubh math)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh jubah}(h]h]h]h]h]uhjh jubh/) is increased. Several convergence
diagnostic capabilities available in the KENO codes help the user better
measure when the fission source actually convergences.}(h) is increased. Several convergence
diagnostic capabilities available in the KENO codes help the user better
measure when the fission source actually convergences.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubh
highlightlang)}(hhh]h}(h]h]h]h]h]langscaleforcelinenothresholduhjh jhhh!jhKubh$)}(hhh](h))}(hIntroductionh]h/Introduction}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhKubh;)}(hXMonte Carlo eigenvalue calculations have been used in evaluating
critical and sub-critical systems for decades. Calculations are
typically done iteratively – starting with a set of fission neutrons,
transporting them through the geometry until they leak or are absorbed,
and then tabulating the fission sites for the next iteration. Each
iteration corresponds to a generation in a chain reaction, and the
eigenvalue, :math:`k_{\mathrm{\text{eff}}}`, is the ratio of the number
of fissions in one generation to the number in the previous generation.
Once the fission source distribution (the eigenfunction) has converged,
many generations are simulated to obtain more estimates of
:math:`k_{\mathrm{\text{eff}}}` with lower statistical uncertainty.h](h/XMonte Carlo eigenvalue calculations have been used in evaluating
critical and sub-critical systems for decades. Calculations are
typically done iteratively – starting with a set of fission neutrons,
transporting them through the geometry until they leak or are absorbed,
and then tabulating the fission sites for the next iteration. Each
iteration corresponds to a generation in a chain reaction, and the
eigenvalue, }(hXMonte Carlo eigenvalue calculations have been used in evaluating
critical and sub-critical systems for decades. Calculations are
typically done iteratively – starting with a set of fission neutrons,
transporting them through the geometry until they leak or are absorbed,
and then tabulating the fission sites for the next iteration. Each
iteration corresponds to a generation in a chain reaction, and the
eigenvalue, h jhhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh jubah}(h]h]h]h]h]uhjh jubh/, is the ratio of the number
of fissions in one generation to the number in the previous generation.
Once the fission source distribution (the eigenfunction) has converged,
many generations are simulated to obtain more estimates of
}(h, is the ratio of the number
of fissions in one generation to the number in the previous generation.
Once the fission source distribution (the eigenfunction) has converged,
many generations are simulated to obtain more estimates of
h jhhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh j
ubah}(h]h]h]h]h]uhjh jubh/$ with lower statistical uncertainty.}(h$ with lower statistical uncertainty.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubh;)}(hXTwo common questions that concern practitioners are (1) how many
generations (skipped generations) are required before the fission source
distribution is sufficiently converged that generational estimates of
:math:`k_{\mathrm{\text{eff}}}` can be included in the final average of
the eigenvalue (the active generations) and (2) has the fission source
converged to the correct distribution, such that the final value of the
eigenvalue will be correct? For most calculations, the final value of
the :math:`k_{\mathrm{\text{eff}}}` eigenvalue is all that matters, so
the convergence of the generational value of
:math:`k_{\mathrm{\text{eff}}}` is used to determine the number of
skipped generations. Fluxes and reaction rates computed during the
active generations are more sensitive to the entire fission distribution
and should only be accumulated when the fission distribution is
sufficiently converged – which is not necessarily as soon as the
generational value of :math:`k_{\mathrm{\text{eff}}}` has converged. To
address this concern, tools such as Shannon entropy :cite:`shannon_mathematical_1948` can be used to
measure the convergence of the fission source distribution
eigenfunction :cite:`ueki_stationarity_2003,ueki_stationarity_2005`.h](h/Two common questions that concern practitioners are (1) how many
generations (skipped generations) are required before the fission source
distribution is sufficiently converged that generational estimates of
}(hTwo common questions that concern practitioners are (1) how many
generations (skipped generations) are required before the fission source
distribution is sufficiently converged that generational estimates of
h j#hhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh j,ubah}(h]h]h]h]h]uhjh j#ubh/X can be included in the final average of
the eigenvalue (the active generations) and (2) has the fission source
converged to the correct distribution, such that the final value of the
eigenvalue will be correct? For most calculations, the final value of
the }(hX can be included in the final average of
the eigenvalue (the active generations) and (2) has the fission source
converged to the correct distribution, such that the final value of the
eigenvalue will be correct? For most calculations, the final value of
the h j#hhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh j?ubah}(h]h]h]h]h]uhjh j#ubh/Q eigenvalue is all that matters, so
the convergence of the generational value of
}(hQ eigenvalue is all that matters, so
the convergence of the generational value of
h j#hhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh jRubah}(h]h]h]h]h]uhjh j#ubh/XI is used to determine the number of
skipped generations. Fluxes and reaction rates computed during the
active generations are more sensitive to the entire fission distribution
and should only be accumulated when the fission distribution is
sufficiently converged – which is not necessarily as soon as the
generational value of }(hXI is used to determine the number of
skipped generations. Fluxes and reaction rates computed during the
active generations are more sensitive to the entire fission distribution
and should only be accumulated when the fission distribution is
sufficiently converged – which is not necessarily as soon as the
generational value of h j#hhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh jeubah}(h]h]h]h]h]uhjh j#ubh/G has converged. To
address this concern, tools such as Shannon entropy }(hG has converged. To
address this concern, tools such as Shannon entropy h j#hhh!NhNubh_)}(hshannon_mathematical_1948h]he)}(hjzh]h/[shannon_mathematical_1948]}(hhh j|ubah}(h]h]h]h]h]uhhdh jxubah}(h]id45ah]hwah]h]h] refdomainh|reftypeh~ reftargetjzrefwarnsupport_smartquotesuhh^h!jhK&h j#hhubh/Y can be used to
measure the convergence of the fission source distribution
eigenfunction }(hY can be used to
measure the convergence of the fission source distribution
eigenfunction h j#hhh!NhNubh_)}(hueki_stationarity_2003h]he)}(hjh]h/[ueki_stationarity_2003]}(hhh jubah}(h]h]h]h]h]uhhdh jubah}(h]id46ah]hwah]h]h] refdomainh|reftypeh~ reftargetjrefwarnsupport_smartquotesuhh^h!jhK&h j#hhubh_)}(hueki_stationarity_2005h]he)}(hjh]h/[ueki_stationarity_2005]}(hhh jubah}(h]h]h]h]h]uhhdh jubah}(h]id47ah]hwah]h]h] refdomainh|reftypeh~ reftargetjrefwarnsupport_smartquotesuhh^h!jhK&h j#hhubh/.}(hjh j#hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhK&h jhhubh;)}(hXFor the second question, the reliability in the final
:math:`k_{\mathrm{\text{eff}}}` eigenvalue depends on whether the
fission source converges to the correct distribution. Because no tool
currently exists in SCALE to verify that the fission distribution is
correct, models are often run for many generations using many histories
per generation to ensure that the result does not change. Another
approach to verify eigenvalue accuracy is to run several clones of the
same problem, but each starting with different random numbers seed, and
ensure that they all predict the same value for
:math:`k_{\mathrm{\text{eff}}}`. Addressing this concern relies heavily
on the engineering judgment of the practitioner.h](h/6For the second question, the reliability in the final
}(h6For the second question, the reliability in the final
h jhhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh jubah}(h]h]h]h]h]uhjh jubh/X eigenvalue depends on whether the
fission source converges to the correct distribution. Because no tool
currently exists in SCALE to verify that the fission distribution is
correct, models are often run for many generations using many histories
per generation to ensure that the result does not change. Another
approach to verify eigenvalue accuracy is to run several clones of the
same problem, but each starting with different random numbers seed, and
ensure that they all predict the same value for
}(hX eigenvalue depends on whether the
fission source converges to the correct distribution. Because no tool
currently exists in SCALE to verify that the fission distribution is
correct, models are often run for many generations using many histories
per generation to ensure that the result does not change. Another
approach to verify eigenvalue accuracy is to run several clones of the
same problem, but each starting with different random numbers seed, and
ensure that they all predict the same value for
h jhhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh jubah}(h]h]h]h]h]uhjh jubh/Y. Addressing this concern relies heavily
on the engineering judgment of the practitioner.}(hY. Addressing this concern relies heavily
on the engineering judgment of the practitioner.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhK9h jhhubh;)}(hXInitial studies :cite:`ibrahim_acceleration_2011` have shown that the use of a
starting fission distribution that is similar to the true fission
distribution can both reduce the number of skipped generations required
for fission source convergence and significantly improve the reliability
of the final :math:`k_{\mathrm{\text{eff}}}` result. A recent study :cite:`ibrahim_hybrid_2013`
focusing on criticality calculations of a spent nuclear fuel cask showed
that the chance of a low eigenvalue result due to undersampling from an
unconverged source was dramatically reduced when using a deterministic
starting source. In that study, a cask holding 24 assemblies was
examined using a uniform starting source, a deterministic starting
source with loose convergence criteria, and a deterministic starting
source with tight convergence criteria. Multiple clones of KENO were run
(with different random number seeds) for different values of skipped
cycles. The number of clones that gave an incorrect result for
:math:`k_{\mathrm{\text{eff}}}` was then tabulated. The results from
that study, presented in Figure 2.4.1, show that using a deterministic
starting source significantly increases the
:math:`k_{\mathrm{\text{eff}}}` reliability.h](h/Initial studies }(hInitial studies h j hhh!NhNubh_)}(hibrahim_acceleration_2011h]he)}(hj h]h/[ibrahim_acceleration_2011]}(hhh j ubah}(h]h]h]h]h]uhhdh j ubah}(h]id48ah]hwah]h]h] refdomainh|reftypeh~ reftargetj refwarnsupport_smartquotesuhh^h!jhKEh j hhubh/ have shown that the use of a
starting fission distribution that is similar to the true fission
distribution can both reduce the number of skipped generations required
for fission source convergence and significantly improve the reliability
of the final }(h have shown that the use of a
starting fission distribution that is similar to the true fission
distribution can both reduce the number of skipped generations required
for fission source convergence and significantly improve the reliability
of the final h j hhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh j> ubah}(h]h]h]h]h]uhjh j ubh/ result. A recent study }(h result. A recent study h j hhh!NhNubh_)}(hibrahim_hybrid_2013h]he)}(hjS h]h/[ibrahim_hybrid_2013]}(hhh jU ubah}(h]h]h]h]h]uhhdh jQ ubah}(h]id49ah]hwah]h]h] refdomainh|reftypeh~ reftargetjS refwarnsupport_smartquotesuhh^h!jhKEh j hhubh/Xo
focusing on criticality calculations of a spent nuclear fuel cask showed
that the chance of a low eigenvalue result due to undersampling from an
unconverged source was dramatically reduced when using a deterministic
starting source. In that study, a cask holding 24 assemblies was
examined using a uniform starting source, a deterministic starting
source with loose convergence criteria, and a deterministic starting
source with tight convergence criteria. Multiple clones of KENO were run
(with different random number seeds) for different values of skipped
cycles. The number of clones that gave an incorrect result for
}(hXo
focusing on criticality calculations of a spent nuclear fuel cask showed
that the chance of a low eigenvalue result due to undersampling from an
unconverged source was dramatically reduced when using a deterministic
starting source. In that study, a cask holding 24 assemblies was
examined using a uniform starting source, a deterministic starting
source with loose convergence criteria, and a deterministic starting
source with tight convergence criteria. Multiple clones of KENO were run
(with different random number seeds) for different values of skipped
cycles. The number of clones that gave an incorrect result for
h j hhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh js ubah}(h]h]h]h]h]uhjh j ubh/ was then tabulated. The results from
that study, presented in Figure 2.4.1, show that using a deterministic
starting source significantly increases the
}(h was then tabulated. The results from
that study, presented in Figure 2.4.1, show that using a deterministic
starting source significantly increases the
h j hhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh j ubah}(h]h]h]h]h]uhjh j ubh/
reliability.}(h
reliability.h j hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKEh jhhubh;)}(hX'The Sourcerer sequence in SCALE uses the solution from the Denovo :cite:`evans_denovo_2010`
discrete-ordinates code (through the DEVC sequence) as that starting
fission source distribution in a CSAS/KENO Monte Carlo :cite:`goluoglu_monte_2011` calculation.
For challenging criticality safety analyses, such as as-loaded spent
nuclear fuel transportation packages with a mixed loading of low- and
high-burnup fuel, even a low-fidelity deterministic solution for the
fission source should be more accurate than the typical starting guesses
of uniform or cosine shape over the fissionable regions. The Sourcerer
sequence is fairly automated and uses an input very similar to standard
CSAS (KENO V.a or KENO-VI) inputs, along with a short description of the
mesh and other parameters for the Denovo calculation.h](h/BThe Sourcerer sequence in SCALE uses the solution from the Denovo }(hBThe Sourcerer sequence in SCALE uses the solution from the Denovo h j hhh!NhNubh_)}(hevans_denovo_2010h]he)}(hj h]h/[evans_denovo_2010]}(hhh j ubah}(h]h]h]h]h]uhhdh j ubah}(h]id50ah]hwah]h]h] refdomainh|reftypeh~ reftargetj refwarnsupport_smartquotesuhh^h!jhKXh j hhubh/}
discrete-ordinates code (through the DEVC sequence) as that starting
fission source distribution in a CSAS/KENO Monte Carlo }(h}
discrete-ordinates code (through the DEVC sequence) as that starting
fission source distribution in a CSAS/KENO Monte Carlo h j hhh!NhNubh_)}(hgoluoglu_monte_2011h]he)}(hj h]h/[goluoglu_monte_2011]}(hhh j ubah}(h]h]h]h]h]uhhdh j ubah}(h]id51ah]hwah]h]h] refdomainh|reftypeh~ reftargetj refwarnsupport_smartquotesuhh^h!jhKXh j hhubh/X4 calculation.
For challenging criticality safety analyses, such as as-loaded spent
nuclear fuel transportation packages with a mixed loading of low- and
high-burnup fuel, even a low-fidelity deterministic solution for the
fission source should be more accurate than the typical starting guesses
of uniform or cosine shape over the fissionable regions. The Sourcerer
sequence is fairly automated and uses an input very similar to standard
CSAS (KENO V.a or KENO-VI) inputs, along with a short description of the
mesh and other parameters for the Denovo calculation.}(hX4 calculation.
For challenging criticality safety analyses, such as as-loaded spent
nuclear fuel transportation packages with a mixed loading of low- and
high-burnup fuel, even a low-fidelity deterministic solution for the
fission source should be more accurate than the typical starting guesses
of uniform or cosine shape over the fissionable regions. The Sourcerer
sequence is fairly automated and uses an input very similar to standard
CSAS (KENO V.a or KENO-VI) inputs, along with a short description of the
mesh and other parameters for the Denovo calculation.h j hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKXh jhhubh)}(h
.. _fig2-4-1:h]h}(h]h]h]h]h]hfig2-4-1uhh
hM'h jhhh!jubj)}(hhh](j)}(h.. figure:: figs/Sourcerer/fig1.png
:align: center
:width: 500
Fraction of failure to agree with the reference *k*\ :sub:`eff` value for KENO calculations with different starting sources (Figure 4 from Ref. 5).
h]h}(h]h]h]h]h]width500urifigs/Sourcerer/fig1.pngj}jj
suhjh j h!jhKiubj)}(hFraction of failure to agree with the reference *k*\ :sub:`eff` value for KENO calculations with different starting sources (Figure 4 from Ref. 5).h](h/0Fraction of failure to agree with the reference }(h0Fraction of failure to agree with the reference h j
ubh)}(h*k*h]h/k}(hhh j
ubah}(h]h]h]h]h]uhhh j
ubh/ }(h\ h j
ubj)}(h
:sub:`eff`h]h/eff}(hhh j+
ubah}(h]h]h]h]h]uhjh j
ubh/T value for KENO calculations with different starting sources (Figure 4 from Ref. 5).}(hT value for KENO calculations with different starting sources (Figure 4 from Ref. 5).h j
ubeh}(h]h]h]h]h]uhjh!jhKih j ubeh}(h](id99j eh]h]fig2-4-1ah]h]jcenteruhjhKih jhhh!jj}jI
j sj}j j subeh}(h]id44ah]h]h]introductionah]uhh#h jhhh!jhKjmKubh$)}(hhh](h))}(hCapabilitiesh]h/Capabilities}(hj\
h jZ
hhh!NhNubah}(h]h]h]h]h]uhh(h jW
hhh!jhKlubh;)}(hXThe Sourcerer sequence calls a series of other sequences and utilities
in SCALE – most importantly DEVC (for Denovo) and one of the CSAS
sequences. Because DEVC can only use KENO-VI geometry, the utility
c5toc6 geometry converter is used for KENO V.a geometries. The utility
dso2msl is used to convert the Denovo spatial output (\*.dso file) into a
mesh source lite (\*.msl) file that can be read as a starting source in
KENO. All of the steps in Sourcerer are described in :numref:`tab2-4-1`.h](h/XThe Sourcerer sequence calls a series of other sequences and utilities
in SCALE – most importantly DEVC (for Denovo) and one of the CSAS
sequences. Because DEVC can only use KENO-VI geometry, the utility
c5toc6 geometry converter is used for KENO V.a geometries. The utility
dso2msl is used to convert the Denovo spatial output (*.dso file) into a
mesh source lite (*.msl) file that can be read as a starting source in
KENO. All of the steps in Sourcerer are described in }(hXThe Sourcerer sequence calls a series of other sequences and utilities
in SCALE – most importantly DEVC (for Denovo) and one of the CSAS
sequences. Because DEVC can only use KENO-VI geometry, the utility
c5toc6 geometry converter is used for KENO V.a geometries. The utility
dso2msl is used to convert the Denovo spatial output (\*.dso file) into a
mesh source lite (\*.msl) file that can be read as a starting source in
KENO. All of the steps in Sourcerer are described in h jh
hhh!NhNubh_)}(h:numref:`tab2-4-1`h]j)}(hjs
h]h/tab2-4-1}(hhh ju
ubah}(h]h](jstd
std-numrefeh]h]h]uhjh jq
ubah}(h]h]h]h]h]refdocj refdomainj
reftypenumrefrefexplicitrefwarnjtab2-4-1uhh^h!jhKnh jh
ubh/.}(hjh jh
hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKnh jW
hhubh;)}(hX|The sequence can be terminated at several points throughout the
calculation using the ``“parm=”`` control on the ``“=sourcerer”`` line that
starts the sequence. This capability can be used to stop the sequence
between steps to ensure that the problem is progressing correctly or
used to make a single source distribution that can be used with many
variants of the final CSAS problem. Also when running several versions
of a problem, if a file that is normally created by the Sourcerer
sequence is supplied, then that step will be skipped, thus saving time.
Note that files that use the name of the input file (*input*.inp) will
be copied back to the user’s working directory automatically when the
sequence finishes. Files that do not use the input file name can be
copied back to the user’s working area with an extra ``“=shell”`` directive
in the ``*input*.inp`` input file.h](h/VThe sequence can be terminated at several points throughout the
calculation using the }(hVThe sequence can be terminated at several points throughout the
calculation using the h j
hhh!NhNubj)}(h``“parm=”``h]h/“parm=”}(hhh j
ubah}(h]h]h]h]h]uhjh j
ubh/ control on the }(h control on the h j
hhh!NhNubj)}(h``“=sourcerer”``h]h/“=sourcerer”}(hhh j
ubah}(h]h]h]h]h]uhjh j
ubh/X line that
starts the sequence. This capability can be used to stop the sequence
between steps to ensure that the problem is progressing correctly or
used to make a single source distribution that can be used with many
variants of the final CSAS problem. Also when running several versions
of a problem, if a file that is normally created by the Sourcerer
sequence is supplied, then that step will be skipped, thus saving time.
Note that files that use the name of the input file (}(hX line that
starts the sequence. This capability can be used to stop the sequence
between steps to ensure that the problem is progressing correctly or
used to make a single source distribution that can be used with many
variants of the final CSAS problem. Also when running several versions
of a problem, if a file that is normally created by the Sourcerer
sequence is supplied, then that step will be skipped, thus saving time.
Note that files that use the name of the input file (h j
hhh!NhNubh)}(h*input*h]h/input}(hhh j
ubah}(h]h]h]h]h]uhhh j
ubh/.inp) will
be copied back to the user’s working directory automatically when the
sequence finishes. Files that do not use the input file name can be
copied back to the user’s working area with an extra }(h.inp) will
be copied back to the user’s working directory automatically when the
sequence finishes. Files that do not use the input file name can be
copied back to the user’s working area with an extra h j
hhh!NhNubj)}(h``“=shell”``h]h/“=shell”}(hhh j
ubah}(h]h]h]h]h]uhjh j
ubh/ directive
in the }(h directive
in the h j
hhh!NhNubj)}(h``*input*.inp``h]h/*input*.inp}(hhh j
ubah}(h]h]h]h]h]uhjh j
ubh/ input file.}(h input file.h j
hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKvh jW
hhubh;)}(hXThe Sourcerer sequence can be used with KENO V.a or KENO-VI geometries.
Either multi-group (MG) or continuous energy cross-section libraries can
be used for the final CSAS calculation. Denovo only uses multi-group
libraries, and self-shielding can be done like any MG sequence in SCALE.
For efficient calculations, the user should understand the basics of
Denovo eigenvalue calculations, how to use macromaterials, and how to
use the KENO convergence metrics.h]h/XThe Sourcerer sequence can be used with KENO V.a or KENO-VI geometries.
Either multi-group (MG) or continuous energy cross-section libraries can
be used for the final CSAS calculation. Denovo only uses multi-group
libraries, and self-shielding can be done like any MG sequence in SCALE.
For efficient calculations, the user should understand the basics of
Denovo eigenvalue calculations, how to use macromaterials, and how to
use the KENO convergence metrics.}(hjh j hhh!NhNubah}(h]h]h]h]h]uhh:h!jhKh jW
hhubh)}(h
.. _tab2-4-1:h]h}(h]h]h]h]h]htab2-4-1uhh
hM'h jW
hhh!jubj)}(hhh](h))}(h7Steps in Sourcerer for an input file named *input*.inp.h](h/+Steps in Sourcerer for an input file named }(h+Steps in Sourcerer for an input file named h j%ubh)}(h*input*h]h/input}(hhh j.ubah}(h]h]h]h]h]uhhh j%ubh/.inp.}(h.inp.h j%ubeh}(h]h]h]h]h]uhh(h!jhKh j"ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jGubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jGubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jGubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jGubh thead)}(hhh]j5)}(hhh](j:)}(hhh]h;)}(hSteph]h/Step}(hjh j}ubah}(h]h]h]h]h]uhh:h!jhKh jzubah}(h]h]h]h]h]uhj9h jwubj:)}(hhh]h;)}(hModule/Taskh]h/Module/Task}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jwubj:)}(hhh]h;)}(hCreates fileh]h/Creates file}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jwubj:)}(hhh]h;)}(h
To stop afterh]h/
To stop after}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jwubeh}(h]h]h]h]h]uhj4h jtubah}(h]h]h]h]h]uhjrh jGubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(h0h]h/0}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hCheck user
inputh]h/Check user
input}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h``parm=check``h]j)}(hj$h]h/
parm=check}(hhh j&ubah}(h]h]h]h]h]uhjh j"ubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jEubj:)}(hhh]h}(h]h]h]h]h]uhj9h jEubj:)}(hhh]h}(h]h]h]h]h]uhj9h jEubj:)}(hhh]h}(h]h]h]h]h]uhj9h jEubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h1h]h/1}(hjzh jxubah}(h]h]h]h]h]uhh:h!jhKh juubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(hX``c5toc6`` – For
KENO V.a
sequences, the
geometry is
translated into
KENO-VI
geometry.h](j)}(h
``c5toc6``h]h/c5toc6}(hhh jubah}(h]h]h]h]h]uhjh jubh/N – For
KENO V.a
sequences, the
geometry is
translated into
KENO-VI
geometry.}(hN – For
KENO V.a
sequences, the
geometry is
translated into
KENO-VI
geometry.h jubeh}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh](h;)}(h``input.geom0…``h]j)}(hjh]h/input.geom0…}(hhh jubah}(h]h]h]h]h]uhjh jubah}(h]h]h]h]h]uhh:h!jhKh jubh;)}(h
``00.inp``h]j)}(hjh]h/00.inp}(hhh jubah}(h]h]h]h]h]uhjh jubah}(h]h]h]h]h]uhh:h!jhKh jubeh}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h}(h]h]h]h]h]uhj9h jrubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h2ah]h/2a}(hj-
h j+
ubah}(h]h]h]h]h]uhh:h!jhKh j(
ubah}(h]h]h]h]h]uhj9h j%
ubj:)}(hhh]h;)}(h+Create Denovo
input and AMPX
cross sectionsh]h/+Create Denovo
input and AMPX
cross sections}(hjD
h jB
ubah}(h]h]h]h]h]uhh:h!jhKh j?
ubah}(h]h]h]h]h]uhj9h j%
ubj:)}(hhh](h;)}(h``xkba_b.inp``h]j)}(hj[
h]h/
xkba_b.inp}(hhh j]
ubah}(h]h]h]h]h]uhjh jY
ubah}(h]h]h]h]h]uhh:h!jhKh jV
ubh;)}(h``ft02f001``h]j)}(hjr
h]h/ft02f001}(hhh jt
ubah}(h]h]h]h]h]uhjh jp
ubah}(h]h]h]h]h]uhh:h!jhKh jV
ubh;)}(h
``input.mmt``h]j)}(hj
h]h/ input.mmt}(hhh j
ubah}(h]h]h]h]h]uhjh j
ubah}(h]h]h]h]h]uhh:h!jhKh jV
ubeh}(h]h]h]h]h]uhj9h j%
ubj:)}(hhh]h;)}(h``parm=deninp``h]j)}(hj
h]h/parm=deninp}(hhh j
ubah}(h]h]h]h]h]uhjh j
ubah}(h]h]h]h]h]uhh:h!jhKh j
ubah}(h]h]h]h]h]uhj9h j%
ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j
ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h2bh]h/2b}(hj
h j
ubah}(h]h]h]h]h]uhh:h!jhKh j
ubah}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h;)}(hU``devc`` – Deno\
vo eigenvalue
calculation to
compute a
fission source
distributionh](j)}(h``devc``h]h/devc}(hhh jubah}(h]h]h]h]h]uhjh jubh/M – Deno
vo eigenvalue
calculation to
compute a
fission source
distribution}(hM – Deno\
vo eigenvalue
calculation to
compute a
fission source
distributionh jubeh}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h;)}(h*input*.dsoh](h)}(h*input*h]h/input}(hhh j>ubah}(h]h]h]h]h]uhhh j:ubh/.dso}(h.dsoh j:ubeh}(h]h]h]h]h]uhh:h!jhKh j7ubah}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h;)}(h``parm=denovo``h]j)}(hjbh]h/parm=denovo}(hhh jdubah}(h]h]h]h]h]uhjh j`ubah}(h]h]h]h]h]uhh:h!jhKh j]ubah}(h]h]h]h]h]uhj9h j
ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h3h]h/3}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hY``dso2msl`` –
Convert the
fission source
distribution
file into a
mesh source
lite fileh](j)}(h``dso2msl``h]h/dso2msl}(hhh jubah}(h]h]h]h]h]uhjh jubh/N –
Convert the
fission source
distribution
file into a
mesh source
lite file}(hN –
Convert the
fission source
distribution
file into a
mesh source
lite fileh jubeh}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
``input.msl``h]j)}(hjh]h/ input.msl}(hhh jubah}(h]h]h]h]h]uhjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h4ah]h/4a}(hjTh jRubah}(h]h]h]h]h]uhh:h!jhKh jOubah}(h]h]h]h]h]uhj9h jLubj:)}(hhh]h;)}(hCreate the CSAS
inputh]h/Create the CSAS
input}(hjkh jiubah}(h]h]h]h]h]uhh:h!jhKh jfubah}(h]h]h]h]h]uhj9h jLubj:)}(hhh]h}(h]h]h]h]h]uhj9h jLubj:)}(hhh]h;)}(h``parm=csasinp``h]j)}(hjh]h/parm=csasinp}(hhh jubah}(h]h]h]h]h]uhjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jLubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h4bh]h/4b}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hb``csasX`` - Run
the specific CS\
AS sequence usi\
ng the mesh sou\
rce lite as the
starting sourceh](j)}(h ``csasX``h]h/csasX}(hhh jubah}(h]h]h]h]h]uhjh jubh/Y - Run
the specific CS
AS sequence usi
ng the mesh sou
rce lite as the
starting source}(hY - Run
the specific CS\
AS sequence usi\
ng the mesh sou\
rce lite as the
starting sourceh jubeh}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubeh}(h]h]h]h]h]uhj/h jGubeh}(h]h]h]h]h]colsKuhjh j"ubeh}(h](id100j!eh]h]tab2-4-1ah]h]jcenteruhjh jW
hhh!jhNj}jCjsj}j!jsubh$)}(hhh](h))}(hUsing DEVC/Denovoh]h/Using DEVC/Denovo}(hjNh jLhhh!NhNubah}(h]h]h]h]h]uhh(h jIhhh!jhKubh;)}(hX%Some discussion is required about the extent and level of detail needed
in the grid geometry that will be used in the Denovo calculation and the
mesh-based starting source. When using discrete-ordinates transport
(S:sub:`N`) methods alone for solving radiation transport problems, a
good rule of thumb is to use mesh cell sizes on the order of a mean-free
path of the particle. For complex problems, this could lead to an
extremely large number of mesh cells, especially when considering the
size of the mean-free path of the lowest energy neutrons.h](h/Some discussion is required about the extent and level of detail needed
in the grid geometry that will be used in the Denovo calculation and the
mesh-based starting source. When using discrete-ordinates transport
(S:sub:}(hSome discussion is required about the extent and level of detail needed
in the grid geometry that will be used in the Denovo calculation and the
mesh-based starting source. When using discrete-ordinates transport
(S:sub:h jZhhh!NhNubjV)}(h`N`h]h/N}(hhh jcubah}(h]h]h]h]h]uhjUh jZubh/XF) methods alone for solving radiation transport problems, a
good rule of thumb is to use mesh cell sizes on the order of a mean-free
path of the particle. For complex problems, this could lead to an
extremely large number of mesh cells, especially when considering the
size of the mean-free path of the lowest energy neutrons.}(hXF) methods alone for solving radiation transport problems, a
good rule of thumb is to use mesh cell sizes on the order of a mean-free
path of the particle. For complex problems, this could lead to an
extremely large number of mesh cells, especially when considering the
size of the mean-free path of the lowest energy neutrons.h jZhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jIhhubh;)}(hXtIn Sourcerer, the goal is to use the S\ :sub:`N` calculation for a quick
estimate. Accuracy is not paramount—just getting an approximation of the
overall shape of the true fission source distribution will benefit the
CSAS Monte Carlo calculation. With a more accurate starting source,
fewer skipped generations may be required. At some point there is a time
trade-off where calculating the starting source guess requires more time
than the saved skipped generations would have used. Large numbers of
mesh cells, as a result of using very small mesh sizes, for S\ :sub:`N`
calculations also use a great deal of computer memory.h](h/(In Sourcerer, the goal is to use the S }(h(In Sourcerer, the goal is to use the S\ h j|hhh!NhNubj)}(h:sub:`N`h]h/N}(hhh jubah}(h]h]h]h]h]uhjh j|ubh/X calculation for a quick
estimate. Accuracy is not paramount—just getting an approximation of the
overall shape of the true fission source distribution will benefit the
CSAS Monte Carlo calculation. With a more accurate starting source,
fewer skipped generations may be required. At some point there is a time
trade-off where calculating the starting source guess requires more time
than the saved skipped generations would have used. Large numbers of
mesh cells, as a result of using very small mesh sizes, for S }(hX calculation for a quick
estimate. Accuracy is not paramount—just getting an approximation of the
overall shape of the true fission source distribution will benefit the
CSAS Monte Carlo calculation. With a more accurate starting source,
fewer skipped generations may be required. At some point there is a time
trade-off where calculating the starting source guess requires more time
than the saved skipped generations would have used. Large numbers of
mesh cells, as a result of using very small mesh sizes, for S\ h j|hhh!NhNubj)}(h:sub:`N`h]h/N}(hhh jubah}(h]h]h]h]h]uhjh j|ubh/7
calculations also use a great deal of computer memory.}(h7
calculations also use a great deal of computer memory.h j|hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jIhhubh;)}(hXBecause the S\ :sub:`N` calculation is only used to establish the
initial distribution of source neutrons, the runtime and memory
requirements for Sourcerer can be reduced by using larger/coarser mesh
cell sizes than is typical for a stand-alone S\ :sub:`N` analysis. Some
general guidelines to consider when creating a mesh for the Denovo
eigenvalue calculation/mesh-based starting source are as follows.h](h/Because the S }(hBecause the S\ h jhhh!NhNubj)}(h:sub:`N`h]h/N}(hhh jubah}(h]h]h]h]h]uhjh jubh/ calculation is only used to establish the
initial distribution of source neutrons, the runtime and memory
requirements for Sourcerer can be reduced by using larger/coarser mesh
cell sizes than is typical for a stand-alone S }(h calculation is only used to establish the
initial distribution of source neutrons, the runtime and memory
requirements for Sourcerer can be reduced by using larger/coarser mesh
cell sizes than is typical for a stand-alone S\ h jhhh!NhNubj)}(h:sub:`N`h]h/N}(hhh jubah}(h]h]h]h]h]uhjh jubh/ analysis. Some
general guidelines to consider when creating a mesh for the Denovo
eigenvalue calculation/mesh-based starting source are as follows.}(h analysis. Some
general guidelines to consider when creating a mesh for the Denovo
eigenvalue calculation/mesh-based starting source are as follows.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jIhhubh bullet_list)}(hhh](h list_item)}(hAll fissionable areas of the geometry and areas where neutrons can
reasonably affect the eigenvalue should be included in the mesh.
h]h;)}(hAll fissionable areas of the geometry and areas where neutrons can
reasonably affect the eigenvalue should be included in the mesh.h]h/All fissionable areas of the geometry and areas where neutrons can
reasonably affect the eigenvalue should be included in the mesh.}(hjh jubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhjh jhhh!jhNubj)}(h5More detail should be used in the fissionable areas.
h]h;)}(h4More detail should be used in the fissionable areas.h]h/4More detail should be used in the fissionable areas.}(hjh j ubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhjh jhhh!jhNubj)}(hAMesh planes should be placed at significant material boundaries.
h]h;)}(h@Mesh planes should be placed at significant material boundaries.h]h/@Mesh planes should be placed at significant material boundaries.}(hj#h j!ubah}(h]h]h]h]h]uhh:h!jhKh jubah}(h]h]h]h]h]uhjh jhhh!jhNubj)}(hANeighboring cell mesh sizes should not be drastically different.
h]h;)}(h@Neighboring cell mesh sizes should not be drastically different.h]h/@Neighboring cell mesh sizes should not be drastically different.}(hj;h j9ubah}(h]h]h]h]h]uhh:h!jhKh j5ubah}(h]h]h]h]h]uhjh jhhh!jhNubeh}(h]h]h]h]h]bulletjuhjh!jhKh jIhhubeh}(h]using-devc-denovoah]h]using devc/denovoah]h]uhh#h jW
hhh!jhKubh$)}(hhh](h))}(hConvergence Metrics in KENOh]h/Convergence Metrics in KENO}(hjah j_hhh!NhNubah}(h]h]h]h]h]uhh(h j\hhh!jhKubh;)}(hXKENO provides several tools that can be used to examine the convergence
of :math:`k_{\mathrm{\text{eff}}}` and the fission source distribution.
These include tools based on Shannon Entropy\ :sup:`1,3` and tools based
on the mesh tally metrics described in :cite:`kiedrowski_statistical_2011`. Running Sourcerer
should accelerate Shannon Entropy convergence for KENO calculations, and
Sourcerer/KENO users should always check that the calculation Shannon
Entropy has converged before active generations begin.h](h/KKENO provides several tools that can be used to examine the convergence
of }(hKKENO provides several tools that can be used to examine the convergence
of h jmhhh!NhNubj)}(h:math:`k_{\mathrm{\text{eff}}}`h]h/k_{\mathrm{\text{eff}}}}(hhh jvubah}(h]h]h]h]h]uhjh jmubh/T and the fission source distribution.
These include tools based on Shannon Entropy }(hT and the fission source distribution.
These include tools based on Shannon Entropy\ h jmhhh!NhNubh superscript)}(h
:sup:`1,3`h]h/1,3}(hhh jubah}(h]h]h]h]h]uhjh jmubh/8 and tools based
on the mesh tally metrics described in }(h8 and tools based
on the mesh tally metrics described in h jmhhh!NhNubh_)}(hkiedrowski_statistical_2011h]he)}(hjh]h/[kiedrowski_statistical_2011]}(hhh jubah}(h]h]h]h]h]uhhdh jubah}(h]id52ah]hwah]h]h] refdomainh|reftypeh~ reftargetjrefwarnsupport_smartquotesuhh^h!jhKh jmhhubh/. Running Sourcerer
should accelerate Shannon Entropy convergence for KENO calculations, and
Sourcerer/KENO users should always check that the calculation Shannon
Entropy has converged before active generations begin.}(h. Running Sourcerer
should accelerate Shannon Entropy convergence for KENO calculations, and
Sourcerer/KENO users should always check that the calculation Shannon
Entropy has converged before active generations begin.h jmhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh j\hhubeh}(h]convergence-metrics-in-kenoah]h]convergence metrics in kenoah]h]uhh#h jW
hhh!jhKubeh}(h]capabilitiesah]h]capabilitiesah]h]uhh#h jhhh!jhKlubh$)}(hhh](h))}(hSequence Inputh]h/Sequence Input}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhKubh;)}(hXThe input file for a Sourcerer calculation is similar to a CSAS input,
as shown in :numref:`tab2-4-2`. There are two major differences between
Sourcerer and CSAS: the beginning/end syntax of the CSAS input and the
presence of the “read detSource” block for specifying the deterministic
starting source. The CSAS input appears as one block in the Sourcerer
sequence – instead of “=csasXX” use “read csasXX” and instead of “end
data” use “end csasXX”. If any parm= parameters are required for the
CSAS sequence, they can be listed as “read csasX parm=(…)”. Because
Sourcerer runs both the DEVC and CSAS sequences, which will most likely
use different cross-section data libraries (coarse group for S\ :sub:`N`
and fine group or continuous energy for Monte Carlo), the library for
DEVC is listed in the new “read detSource” block, along with other
parameters used by the Sourcerer sequence.h](h/SThe input file for a Sourcerer calculation is similar to a CSAS input,
as shown in }(hSThe input file for a Sourcerer calculation is similar to a CSAS input,
as shown in h jhhh!NhNubh_)}(h:numref:`tab2-4-2`h]j)}(hjh]h/tab2-4-2}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-4-2uhh^h!jhKh jubh/Xr. There are two major differences between
Sourcerer and CSAS: the beginning/end syntax of the CSAS input and the
presence of the “read detSource” block for specifying the deterministic
starting source. The CSAS input appears as one block in the Sourcerer
sequence – instead of “=csasXX” use “read csasXX” and instead of “end
data” use “end csasXX”. If any parm= parameters are required for the
CSAS sequence, they can be listed as “read csasX parm=(…)”. Because
Sourcerer runs both the DEVC and CSAS sequences, which will most likely
use different cross-section data libraries (coarse group for S }(hXr. There are two major differences between
Sourcerer and CSAS: the beginning/end syntax of the CSAS input and the
presence of the “read detSource” block for specifying the deterministic
starting source. The CSAS input appears as one block in the Sourcerer
sequence – instead of “=csasXX” use “read csasXX” and instead of “end
data” use “end csasXX”. If any parm= parameters are required for the
CSAS sequence, they can be listed as “read csasX parm=(…)”. Because
Sourcerer runs both the DEVC and CSAS sequences, which will most likely
use different cross-section data libraries (coarse group for S\ h jhhh!NhNubj)}(h:sub:`N`h]h/N}(hhh jubah}(h]h]h]h]h]uhjh jubh/
and fine group or continuous energy for Monte Carlo), the library for
DEVC is listed in the new “read detSource” block, along with other
parameters used by the Sourcerer sequence.}(h
and fine group or continuous energy for Monte Carlo), the library for
DEVC is listed in the new “read detSource” block, along with other
parameters used by the Sourcerer sequence.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubh;)}(hXWOne important note about the geometry in Sourcerer is that for KENO V.a
geometries, an outer boundary region should be added for an accurate
internal conversion to a KENO-VI geometry prior to ray tracing. Also
note that when using CSAS methods with the search capability, the Denovo
mesh must encompass any changes to the size of the geometry.h]h/XWOne important note about the geometry in Sourcerer is that for KENO V.a
geometries, an outer boundary region should be added for an accurate
internal conversion to a KENO-VI geometry prior to ray tracing. Also
note that when using CSAS methods with the search capability, the Denovo
mesh must encompass any changes to the size of the geometry.}(hj0h j.hhh!NhNubah}(h]h]h]h]h]uhh:h!jhMh jhhubh;)}(hXParameters used for building the deterministic starting source and
establishing the CSAS sequence are specified in the detSource block. The
library name for the Denovo calculation and the grid for the Denovo
calculations are required. Many optional parameters are available for
controlling the Denovo solver and applying boundary conditions (in the
``eigenValParams`` sub-block). The grid geometry is defined in a sub-block,
or the keyword ``“gridGeometryID=`` \ *n*\ ” can be used to point to a grid
geometry defined in its own input block. The use of macromaterials to
construct a more representative mesh model from the Monte Carlo geometry
is controlled with the ``“mmSubCell=”`` and ``“mmTolerance=”`` parameters in the
macromaterial sub-block.h](h/X]Parameters used for building the deterministic starting source and
establishing the CSAS sequence are specified in the detSource block. The
library name for the Denovo calculation and the grid for the Denovo
calculations are required. Many optional parameters are available for
controlling the Denovo solver and applying boundary conditions (in the
}(hX]Parameters used for building the deterministic starting source and
establishing the CSAS sequence are specified in the detSource block. The
library name for the Denovo calculation and the grid for the Denovo
calculations are required. Many optional parameters are available for
controlling the Denovo solver and applying boundary conditions (in the
h j<hhh!NhNubj)}(h``eigenValParams``h]h/eigenValParams}(hhh jEubah}(h]h]h]h]h]uhjh j<ubh/I sub-block). The grid geometry is defined in a sub-block,
or the keyword }(hI sub-block). The grid geometry is defined in a sub-block,
or the keyword h j<hhh!NhNubj)}(h``“gridGeometryID=``h]h/“gridGeometryID=}(hhh jXubah}(h]h]h]h]h]uhjh j<ubh/ }(h \ h j<hhh!NhNubh)}(h*n*h]h/n}(hhh jkubah}(h]h]h]h]h]uhhh j<ubh/ ” can be used to point to a grid
geometry defined in its own input block. The use of macromaterials to
construct a more representative mesh model from the Monte Carlo geometry
is controlled with the }(h\ ” can be used to point to a grid
geometry defined in its own input block. The use of macromaterials to
construct a more representative mesh model from the Monte Carlo geometry
is controlled with the h j<hhh!NhNubj)}(h``“mmSubCell=”``h]h/“mmSubCell=”}(hhh j~ubah}(h]h]h]h]h]uhjh j<ubh/ and }(h and h j<hhh!NhNubj)}(h``“mmTolerance=”``h]h/“mmTolerance=”}(hhh jubah}(h]h]h]h]h]uhjh j<ubh/+ parameters in the
macromaterial sub-block.}(h+ parameters in the
macromaterial sub-block.h j<hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jhhubh;)}(hXiThe overall layout of the detSource block is shown in :numref:`tab2-4-3`. The
more common keywords for the eigenValParams sub-block are shown in
:numref:`tab2-4-4` and :numref:`tab2-4-5`. A full list of the Denovo parameters
appears in Appendix A. Macromaterials are explained in detail in the
DEVC manual, and a list of keywords is given in :numref:`tab2-4-6`.h](h/6The overall layout of the detSource block is shown in }(h6The overall layout of the detSource block is shown in h jhhh!NhNubh_)}(h:numref:`tab2-4-3`h]j)}(hjh]h/tab2-4-3}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-4-3uhh^h!jhMh jubh/I. The
more common keywords for the eigenValParams sub-block are shown in
}(hI. The
more common keywords for the eigenValParams sub-block are shown in
h jhhh!NhNubh_)}(h:numref:`tab2-4-4`h]j)}(hjh]h/tab2-4-4}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-4-4uhh^h!jhMh jubh/ and }(h and h jhhh!NhNubh_)}(h:numref:`tab2-4-5`h]j)}(hjh]h/tab2-4-5}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-4-5uhh^h!jhMh jubh/. A full list of the Denovo parameters
appears in Appendix A. Macromaterials are explained in detail in the
DEVC manual, and a list of keywords is given in }(h. A full list of the Denovo parameters
appears in Appendix A. Macromaterials are explained in detail in the
DEVC manual, and a list of keywords is given in h jhhh!NhNubh_)}(h:numref:`tab2-4-6`h]j)}(hj$h]h/tab2-4-6}(hhh j&ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j"ubah}(h]h]h]h]h]refdocj refdomainj0reftypenumrefrefexplicitrefwarnjtab2-4-6uhh^h!jhMh jubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jhhubj)}(hhh](h))}(hInput file for a Sourcerer calculation (and differences with a CSAS input file, where black text is the same as CSAS and green text is new for Sourcerer sequence).h]h/Input file for a Sourcerer calculation (and differences with a CSAS input file, where black text is the same as CSAS and green text is new for Sourcerer sequence).}(hjQh jOubah}(h]h]h]h]h]uhh(h!jhM$h jLubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.Kduhj#h j]ubj0)}(hhh]j5)}(hhh]j:)}(hhh]j)}(h".. image:: figs/Sourcerer/tab2.pngh]h}(h]h]h]h]h]urifigs/Sourcerer/tab2.pngj}jj}suhjh joh!jhKubah}(h]h]h]h]h]uhj9h jlubah}(h]h]h]h]h]uhj4h jiubah}(h]h]h]h]h]uhj/h j]ubeh}(h]h]h]h]h]colsKuhjh jLubeh}(h]tab2-4-2ah]h]tab2-4-2ah]h]jcenteruhjh jhhh!NhNubj)}(hhh](h))}(hThe detSource block.h]h/The detSource block.}(hjh jubah}(h]h]h]h]h]uhh(h!jhM*h jubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.Kduhj#h jubj0)}(hhh]j5)}(hhh]j:)}(hhh]j)}(h".. image:: figs/Sourcerer/tab3.pngh]h}(h]h]h]h]h]urifigs/Sourcerer/tab3.pngj}jjsuhjh jh!jhKubah}(h]h]h]h]h]uhj9h jubah}(h]h]h]h]h]uhj4h jubah}(h]h]h]h]h]uhj/h jubeh}(h]h]h]h]h]colsKuhjh jubeh}(h]tab2-4-3ah]h]tab2-4-3ah]h]jcenteruhjh jhhh!NhNubj)}(hhh](h))}(h9Common Denovo parameters in the eigenValParams sub-block.h]h/9Common Denovo parameters in the eigenValParams sub-block.}(hjh jubah}(h]h]h]h]h]uhh(h!jhM0h jubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.Kduhj#h jubj0)}(hhh]j5)}(hhh]j:)}(hhh]j)}(h".. image:: figs/Sourcerer/tab4.pngh]h}(h]h]h]h]h]urifigs/Sourcerer/tab4.pngj}jj'suhjh jh!jhKubah}(h]h]h]h]h]uhj9h jubah}(h]h]h]h]h]uhj4h jubah}(h]h]h]h]h]uhj/h jubeh}(h]h]h]h]h]colsKuhjh jubeh}(h]tab2-4-4ah]h]tab2-4-4ah]h]jcenteruhjh jhhh!NhNubj)}(hhh](h))}(h4Boundary conditions in the eigenValParams sub-block.h]h/4Boundary conditions in the eigenValParams sub-block.}(hjPh jNubah}(h]h]h]h]h]uhh(h!jhM6h jKubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.Kduhj#h j\ubj0)}(hhh]j5)}(hhh]j:)}(hhh]j)}(h".. image:: figs/Sourcerer/tab5.pngh]h}(h]h]h]h]h]urifigs/Sourcerer/tab5.pngj}jj|suhjh jnh!jhKubah}(h]h]h]h]h]uhj9h jkubah}(h]h]h]h]h]uhj4h jhubah}(h]h]h]h]h]uhj/h j\ubeh}(h]h]h]h]h]colsKuhjh jKubeh}(h]tab2-4-5ah]h]tab2-4-5ah]h]jcenteruhjh jhhh!NhNubj)}(hhh](h))}(hMacromaterial sub-block input.h]h/Macromaterial sub-block input.}(hjh jubah}(h]h]h]h]h]uhh(h!jhM<h jubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.Kduhj#h jubj0)}(hhh]j5)}(hhh]j:)}(hhh]j)}(h".. image:: figs/Sourcerer/tab6.pngh]h}(h]h]h]h]h]urifigs/Sourcerer/tab6.pngj}jjsuhjh jh!jhKubah}(h]h]h]h]h]uhj9h jubah}(h]h]h]h]h]uhj4h jubah}(h]h]h]h]h]uhj/h jubeh}(h]h]h]h]h]colsKuhjh jubeh}(h]tab2-4-6ah]h]tab2-4-6ah]h]jcenteruhjh jhhh!NhNubeh}(h]sequence-inputah]h]h]sequence inputah]uhh#h jhhh!jhKjmKubh$)}(hhh](h))}(hSequence Outputh]h/Sequence Output}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhMCubh;)}(hX6In addition to the data contained in the main Sourcerer text output
file, many other files are created containing the intermediate data used
by the sequence. These files are listed in :numref:`tab2-4-7`. Some of the
files produced can be viewed using the Java Mesh File Viewer, which is
distributed with SCALE.h](h/In addition to the data contained in the main Sourcerer text output
file, many other files are created containing the intermediate data used
by the sequence. These files are listed in }(hIn addition to the data contained in the main Sourcerer text output
file, many other files are created containing the intermediate data used
by the sequence. These files are listed in h jhhh!NhNubh_)}(h:numref:`tab2-4-7`h]j)}(hjh]h/tab2-4-7}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainj%reftypenumrefrefexplicitrefwarnjtab2-4-7uhh^h!jhMEh jubh/l. Some of the
files produced can be viewed using the Java Mesh File Viewer, which is
distributed with SCALE.}(hl. Some of the
files produced can be viewed using the Java Mesh File Viewer, which is
distributed with SCALE.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMEh jhhubh;)}(hXCNote that files that use the name of the input file (*input*.inp) will
be copied back to the user’s working directory automatically when the
sequence finishes. Files that do not use the input file name can be
copied back to the user’s working area with an extra ``“=shell”`` directive
in the *input*.inp input file.h](h/5Note that files that use the name of the input file (}(h5Note that files that use the name of the input file (h jBhhh!NhNubh)}(h*input*h]h/input}(hhh jKubah}(h]h]h]h]h]uhhh jBubh/.inp) will
be copied back to the user’s working directory automatically when the
sequence finishes. Files that do not use the input file name can be
copied back to the user’s working area with an extra }(h.inp) will
be copied back to the user’s working directory automatically when the
sequence finishes. Files that do not use the input file name can be
copied back to the user’s working area with an extra h jBhhh!NhNubj)}(h``“=shell”``h]h/“=shell”}(hhh j^ubah}(h]h]h]h]h]uhjh jBubh/ directive
in the }(h directive
in the h jBhhh!NhNubh)}(h*input*h]h/input}(hhh jqubah}(h]h]h]h]h]uhhh jBubh/.inp input file.}(h.inp input file.h jBhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMKh jhhubh;)}(hXInstructions on how to use the Java Mesh File Viewer to view the various
output files listed in :numref:`tab2-4-7` as well as how to use the
macromaterial table file are located in the DEVC manual and the Mesh
File Viewer help file, which is accessible through the Help/Help menu.h](h/`Instructions on how to use the Java Mesh File Viewer to view the various
output files listed in }(h`Instructions on how to use the Java Mesh File Viewer to view the various
output files listed in h jhhh!NhNubh_)}(h:numref:`tab2-4-7`h]j)}(hjh]h/tab2-4-7}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-4-7uhh^h!jhMQh jubh/ as well as how to use the
macromaterial table file are located in the DEVC manual and the Mesh
File Viewer help file, which is accessible through the Help/Help menu.}(h as well as how to use the
macromaterial table file are located in the DEVC manual and the Mesh
File Viewer help file, which is accessible through the Help/Help menu.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMQh jhhubh)}(h
.. _tab2-4-7:h]h}(h]h]h]h]h]htab2-4-7uhh
hM(h jhhh!jubj)}(hhh](h))}(h?Files created by Sourcerer for an input file named *input*.inp.h](h/3Files created by Sourcerer for an input file named }(h3Files created by Sourcerer for an input file named h jubh)}(h*input*h]h/input}(hhh jubah}(h]h]h]h]h]uhhh jubh/.inp.}(h.inp.h jubeh}(h]h]h]h]h]uhh(h!jhMWh jubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jubjs)}(hhh]j5)}(hhh](j:)}(hhh]h;)}(h**Filename**h]hA)}(hj$h]h/Filename}(hhh j&ubah}(h]h]h]h]h]uhh@h j"ubah}(h]h]h]h]h]uhh:h!jhMZh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
**Viewer**h]hA)}(hjMh]h/Viewer}(hhh jOubah}(h]h]h]h]h]uhh@h jKubah}(h]h]h]h]h]uhh:h!jhMZh jHubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h**Description**h]hA)}(hjmh]h/Description}(hhh joubah}(h]h]h]h]h]uhh@h jkubah}(h]h]h]h]h]uhh:h!jhMZh jhubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubah}(h]h]h]h]h]uhjrh jubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hOutput Summaryh]h/Output Summary}(hjh jubah}(h]h]h]h]h]uhh:h!jhM\h jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h*input*.outh](h)}(h*input*h]h/input}(hhh jubah}(h]h]h]h]h]uhhh jubh/.out}(h.outh jubeh}(h]h]h]h]h]uhh:h!jhM^h jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h/main text
output file,
contains
results summaryh]h//main text
output file,
contains
results summary}(hjh jubah}(h]h]h]h]h]uhh:h!jhM^h j
ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h;)}(h*input*.msgh](h)}(h*input*h]h/input}(hhh j=ubah}(h]h]h]h]h]uhhh j9ubh/.msg}(h.msgh j9ubeh}(h]h]h]h]h]uhh:h!jhMch j6ubah}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h;)}(h
messages fileh]h/
messages file}(hjjh jhubah}(h]h]h]h]h]uhh:h!jhMch jeubah}(h]h]h]h]h]uhj9h j*ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hGeometry
Conversionh]h/Geometry
Conversion}(hjh jubah}(h]h]h]h]h]uhh:h!jhMgh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hi_c5toc6h]h/i_c5toc6}(hjh jubah}(h]h]h]h]h]uhh:h!jhMjh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hinput file for
c5toc6 moduleh]h/input file for
c5toc6 module}(hjh jubah}(h]h]h]h]h]uhh:h!jhMjh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j3ubj:)}(hhh]h;)}(h*input*.geom000
….inph](h)}(h*input*h]h/input}(hhh jFubah}(h]h]h]h]h]uhhh jBubh/.geom000
….inp}(h.geom000
….inph jBubeh}(h]h]h]h]h]uhh:h!jhMmh j?ubah}(h]h]h]h]h]uhj9h j3ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j3ubj:)}(hhh]h;)}(h5KENO-VI version
of a KENO V.a
geometry, if
applicableh]h/5KENO-VI version
of a KENO V.a
geometry, if
applicable}(hjsh jqubah}(h]h]h]h]h]uhh:h!jhMmh jnubah}(h]h]h]h]h]uhj9h j3ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hDenovoh]h/Denovo}(hjh jubah}(h]h]h]h]h]uhh:h!jhMth jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hi_devch]h/i_devc}(hjh jubah}(h]h]h]h]h]uhh:h!jhMvh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hinput file for
DEVC sequenceh]h/input file for
DEVC sequence}(hj$h j"ubah}(h]h]h]h]h]uhh:h!jhMvh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(h
xkba_b.inph]h/
xkba_b.inp}(hjMh jKubah}(h]h]h]h]h]uhh:h!jhMyh jHubah}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(hV\ :sup:`a`h](h/V }(hV\ h jbubj)}(h:sup:`a`h]h/a}(hhh jkubah}(h]h]h]h]h]uhjh jbubeh}(h]h]h]h]h]uhh:h!jhMyh j_ubah}(h]h]h]h]h]uhj9h j<ubj:)}(hhh](h;)}(h9input file for
Denovo – if
this file is
renamed to haveh]h/9input file for
Denovo – if
this file is
renamed to have}(hjh jubah}(h]h]h]h]h]uhh:h!jhMyh jubh;)}(h8a \*.dsi
extension
(Denovo simple
input), it is
viewableh]h/8a *.dsi
extension
(Denovo simple
input), it is
viewable}(h8a \*.dsi
extension
(Denovo simple
input), it is
viewableh jubah}(h]h]h]h]h]uhh:h!jhM~h jubh;)}(hin the Mesh
File Viewerh]h/in the Mesh
File Viewer}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubeh}(h]h]h]h]h]uhj9h j<ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hft02f001h]h/ft02f001}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h(AMPX formatted
cross sections
for Denovoh]h/(AMPX formatted
cross sections
for Denovo}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h*input*.dsoh](h)}(h*input*h]h/input}(hhh jubah}(h]h]h]h]h]uhhh jubh/.dso}(h.dsoh jubeh}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hVh]h/V}(hj?h j=ubah}(h]h]h]h]h]uhh:h!jhMh j:ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h"Denovo fission
source
distributionh]h/"Denovo fission
source
distribution}(hjVh jTubah}(h]h]h]h]h]uhh:h!jhMh jQubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jnubj:)}(hhh]h;)}(h*input*.mmth](h)}(h*input*h]h/input}(hhh jubah}(h]h]h]h]h]uhhh j}ubh/.mmt}(h.mmth j}ubeh}(h]h]h]h]h]uhh:h!jhMh jzubah}(h]h]h]h]h]uhj9h jnubj:)}(hhh]h;)}(hj?h]h/V}(hj?h jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jnubj:)}(hhh]h;)}(h3macromaterial
table, use with
\*.dso or
\*.dsi fileh]h/3macromaterial
table, use with
*.dso or
*.dsi file}(h3macromaterial
table, use with
\*.dso or
\*.dsi fileh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jnubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hMesh Source
Conversionh]h/Mesh Source
Conversion}(hj h jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(hi_utilh]h/i_util}(hjMh jKubah}(h]h]h]h]h]uhh:h!jhMh jHubah}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(hinput file for
dso2msl utilityh]h/input file for
dso2msl utility}(hjmh jkubah}(h]h]h]h]h]uhh:h!jhMh jhubah}(h]h]h]h]h]uhj9h j<ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h*input*.mslh](h)}(h*input*h]h/input}(hhh jubah}(h]h]h]h]h]uhhh jubh/.msl}(h.mslh jubeh}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hj?h]h/V}(hj?h jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h7mesh source
lite file, the
starting source
distributionh]h/7mesh source
lite file, the
starting source
distribution}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hCSASh]h/CSAS}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jRubj:)}(hhh]h;)}(hi_csasXXh]h/i_csasXX}(hjch jaubah}(h]h]h]h]h]uhh:h!jhMh j^ubah}(h]h]h]h]h]uhj9h jRubj:)}(hhh]h}(h]h]h]h]h]uhj9h jRubj:)}(hhh]h;)}(h(input file for
the final
CSASXX sequenceh]h/(input file for
the final
CSASXX sequence}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh j~ubah}(h]h]h]h]h]uhj9h jRubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h*input*.fission
Source.3dmaph](h)}(h*input*h]h/input}(hhh jubah}(h]h]h]h]h]uhhh jubh/.fission
Source.3dmap}(h.fission
Source.3dmaph jubeh}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hj?h]h/V}(hj?h jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h3mesh tally of
fission source
distribution
from KENOh]h/3mesh tally of
fission source
distribution
from KENO}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h*input*.kenoNuB
ar.txth](h)}(h*input*h]h/input}(hhh jubah}(h]h]h]h]h]uhhh jubh/.kenoNuB
ar.txt}(h.kenoNuB
ar.txth jubeh}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h$text file
containing
value of nu-barh]h/$text file
containing
value of nu-bar}(hj@h j>ubah}(h]h]h]h]h]uhh:h!jhMh j;ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h?:sup:`a`\ V – c\
an be displayed
with the Mesh F\
ile Viewer.h](j)}(h:sup:`a`h]h/a}(hhh jbubah}(h]h]h]h]h]uhjh j^ubh/7 V – c
an be displayed
with the Mesh F
ile Viewer.}(h7\ V – c\
an be displayed
with the Mesh F\
ile Viewer.h j^ubeh}(h]h]h]h]h]uhh:h!jhMh j[ubah}(h]h]h]h]h]uhj9h jXubj:)}(hhh]h}(h]h]h]h]h]uhj9h jXubj:)}(hhh]h}(h]h]h]h]h]uhj9h jXubj:)}(hhh]h}(h]h]h]h]h]uhj9h jXubeh}(h]h]h]h]h]uhj4h jubeh}(h]h]h]h]h]uhj/h jubeh}(h]h]h]h]h]colsKuhjh jubeh}(h](id101jeh]h]tab2-4-7ah]h]jdefaultuhjh jhhh!jhNj}jjsj}jjsubeh}(h]sequence-outputah]h]h]sequence outputah]uhh#h jhhh!jhMCjmKubh$)}(hhh](h))}(hSample problemsh]h/Sample problems}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhMubh;)}(hX4In addition to the sample problems described in this section (with input
files included with SCALE), the reader is referred to the paper by
Ibrahim et al. for a detailed study using a real used nuclear fuel
transport and storage canister containing assemblies with a range of
initial enrichments and burnups.h]h/X4In addition to the sample problems described in this section (with input
files included with SCALE), the reader is referred to the paper by
Ibrahim et al. for a detailed study using a real used nuclear fuel
transport and storage canister containing assemblies with a range of
initial enrichments and burnups.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jhMh jhhubh$)}(hhh](h))}(hJezebelh]h/Jezebel}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhMubh;)}(hXConsider the Jezebel critical assembly [PU-MET-FAST-001 in Volume I of the *International Handbook of
Evaluated Criticality Safety Benchmark Experiments*, NEA/NSC/DOC(95)03, Organisation for Economic
Co-operation and Development, Nuclear Energy Agency (OECD-NEA), September 2012]. This is a very simple
problem (a single sphere) to solve with CSAS and can be useful as a way to demonstrate the Sourcerer sequence.h](h/KConsider the Jezebel critical assembly [PU-MET-FAST-001 in Volume I of the }(hKConsider the Jezebel critical assembly [PU-MET-FAST-001 in Volume I of the h jhhh!NhNubh)}(hN*International Handbook of
Evaluated Criticality Safety Benchmark Experiments*h]h/LInternational Handbook of
Evaluated Criticality Safety Benchmark Experiments}(hhh jubah}(h]h]h]h]h]uhhh jubh/X, NEA/NSC/DOC(95)03, Organisation for Economic
Co-operation and Development, Nuclear Energy Agency (OECD-NEA), September 2012]. This is a very simple
problem (a single sphere) to solve with CSAS and can be useful as a way to demonstrate the Sourcerer sequence.}(hX, NEA/NSC/DOC(95)03, Organisation for Economic
Co-operation and Development, Nuclear Energy Agency (OECD-NEA), September 2012]. This is a very simple
problem (a single sphere) to solve with CSAS and can be useful as a way to demonstrate the Sourcerer sequence.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jhhubh$)}(hhh](h))}(h
Input fileh]h/
Input file}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhMubh;)}(h`The standard CSAS inputs for Jezebel are shown below using both KENO V.a and KENO-VI geometries.h]h/`The standard CSAS inputs for Jezebel are shown below using both KENO V.a and KENO-VI geometries.}(hj'h j%hhh!NhNubah}(h]h]h]h]h]uhh:h!jhMh jhhubj)}(hhh]j)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h j6ubj$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h j6ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hKENO V.a geometryh]h/KENO V.a geometry}(hjVh jTubah}(h]h]h]h]h]uhh:h!jhMh jQubah}(h]h]h]h]h]uhj9h jNubj:)}(hhh]h;)}(hKENO-VI geometryh]h/KENO-VI geometry}(hjmh jkubah}(h]h]h]h]h]uhh:h!jhMh jhubah}(h]h]h]h]h]uhj9h jNubeh}(h]h]h]h]h]uhj4h jKubj5)}(hhh](j:)}(hhh]h
literal_block)}(hXJ=csas5
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 1 1 6.38493 .
end geometry
end data
endh]h/XJ=csas5
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 1 1 6.38493 .
end geometry
end data
end}(hhh jubah}(h]h]h]h]h] xml:spacepreserveuhjh!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]j)}(hXs=csas6
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 51 6.38493
media 1 1 51 vol=1090.3277
boundary 51
end geometry
end data
endh]h/Xs=csas6
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 51 6.38493
media 1 1 51 vol=1090.3277
boundary 51
end geometry
end data
end}(hhh jubah}(h]h]h]h]h]jjuhjh!jhMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jKubeh}(h]h]h]h]h]uhj/h j6ubeh}(h]h]h]h]h]colsKuhjh j3ubah}(h]h]h]h]h]jcenteruhjh jhhh!NhNubh;)}(hThe above inputs can be easily changed into the following Sourcerer
inputs (with geometry additions in brackets and extra Sourcerer input in
braces).h]h/The above inputs can be easily changed into the following Sourcerer
inputs (with geometry additions in brackets and extra Sourcerer input in
braces).}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jhMh jhhubj)}(hhh]j)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h jubj$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h jubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hKENO V.a geometryh]h/KENO V.a geometry}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hKENO-VI geometryh]h/KENO-VI geometry}(hjh jubah}(h]h]h]h]h]uhh:h!jhMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]j)}(hXS{=sourcerer}
{read} csas5
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 1 1 6.38493
[cuboid 0 1 7.0 -7.0 7.0 -7.0 7.0 -7.0]
end geometry
{end csas5}
{read detSource}
{dLibrary="v7-27n19g"}
{gridGeometry 7}
{xLinear 14 -7.0 7.0}
{yLinear 14 -7.0 7.0}
{zLinear 14 -7.0 7.0}
{end gridGeometry}
{end detSource}
end data
endh]h/XS{=sourcerer}
{read} csas5
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 1 1 6.38493
[cuboid 0 1 7.0 -7.0 7.0 -7.0 7.0 -7.0]
end geometry
{end csas5}
{read detSource}
{dLibrary="v7-27n19g"}
{gridGeometry 7}
{xLinear 14 -7.0 7.0}
{yLinear 14 -7.0 7.0}
{zLinear 14 -7.0 7.0}
{end gridGeometry}
{end detSource}
end data
end}(hhh j:ubah}(h]h]h]h]h]jjuhjh!jhMh j7ubah}(h]h]h]h]h]uhj9h j4ubj:)}(hhh]j)}(hXT{=sourcerer}
{read} csas6
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 51 6.38493
media 1 1 51 vol=1090.3277
boundary 51
end geometry
{end csas6}
{read detSource}
{dLibrary="v7-27n19g"}
{gridGeometry 7}
{xLinear 14 -7.0 7.0}
{yLinear 14 -7.0 7.0}
{zLinear 14 -7.0 7.0}
{end gridGeometry}
{end detSource}
end data
endh]h/XT{=sourcerer}
{read} csas6
Jezebel
v7-252n
read composition
pu-239 1 0 0.037047 end
pu-240 1 0 0.0017512 end
pu-241 1 0 0.00011674 end
ga 1 0 0.0013752 end
end composition
read parameters
gen=110 npg=1000 nsk=10
end parameters
read geometry
global unit 2
sphere 51 6.38493
media 1 1 51 vol=1090.3277
boundary 51
end geometry
{end csas6}
{read detSource}
{dLibrary="v7-27n19g"}
{gridGeometry 7}
{xLinear 14 -7.0 7.0}
{yLinear 14 -7.0 7.0}
{zLinear 14 -7.0 7.0}
{end gridGeometry}
{end detSource}
end data
end}(hhh jQubah}(h]h]h]h]h]jjuhjh!jhM+h jNubah}(h]h]h]h]h]uhj9h j4ubeh}(h]h]h]h]h]uhj4h jubeh}(h]h]h]h]h]uhj/h jubeh}(h]h]h]h]h]colsKuhjh jubah}(h]h]h]h]h]jcenteruhjh jhhh!NhNubh;)}(hWith either of these variations of the Jezebel problem, the fission
source distribution can be tallied by KENO and saved to a mesh tally
(\*.3dmap) file by adding the following to the input:h]h/With either of these variations of the Jezebel problem, the fission
source distribution can be tallied by KENO and saved to a mesh tally
(*.3dmap) file by adding the following to the input:}(hWith either of these variations of the Jezebel problem, the fission
source distribution can be tallied by KENO and saved to a mesh tally
(\*.3dmap) file by adding the following to the input:h jhhh!NhNubah}(h]h]h]h]h]uhh:h!jhMJh jhhubj)}(hread parameters
…
cds=1
end parameters
read gridGeometry 1
title="Mesh for collecting fission source distribution"
xLinear 28 -7.0 7.0
yLinear 28 -7.0 7.0
zLinear 28 -7.0 7.0
end gridGeometryh]h/read parameters
…
cds=1
end parameters
read gridGeometry 1
title="Mesh for collecting fission source distribution"
xLinear 28 -7.0 7.0
yLinear 28 -7.0 7.0
zLinear 28 -7.0 7.0
end gridGeometry}(hhh jubah}(h]h]h]h]h]jjuhjh!jhMPh jhhubh;)}(hXfNote that the mesh grid used for the KENO mesh tally can be different
from the mesh grid used by Denovo to create a starting source in the
Sourcerer sequence. Also note that more total histories (more particles
per generation or more active generations) would be required to produce
a KENO fission source tally with low relative uncertainties in every
voxel.h]h/XfNote that the mesh grid used for the KENO mesh tally can be different
from the mesh grid used by Denovo to create a starting source in the
Sourcerer sequence. Also note that more total histories (more particles
per generation or more active generations) would be required to produce
a KENO fission source tally with low relative uncertainties in every
voxel.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jhM\h jhhubeh}(h]
input-fileah]h]
input fileah]h]uhh#h jhhh!jhMubh$)}(hhh](h))}(hOutput fileh]h/Output file}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhMdubh;)}(hThe results for the standard CSAS calculations and the Sourcerer results
are shown in :numref:`tab2-4-8` for calculations with the 252-energy-group and
continuous-energy cross sections.h](h/VThe results for the standard CSAS calculations and the Sourcerer results
are shown in }(hVThe results for the standard CSAS calculations and the Sourcerer results
are shown in h jhhh!NhNubh_)}(h:numref:`tab2-4-8`h]j)}(hjh]h/tab2-4-8}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-4-8uhh^h!jhMfh jubh/Q for calculations with the 252-energy-group and
continuous-energy cross sections.}(hQ for calculations with the 252-energy-group and
continuous-energy cross sections.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMfh jhhubh)}(h
.. _tab2-4-8:h]h}(h]h]h]h]h]htab2-4-8uhh
hM)h jhhh!jubj)}(hhh](h))}(h+Eigenvalue results for the Jezebel problem.h]h/+Eigenvalue results for the Jezebel problem.}(hj h j ubah}(h]h]h]h]h]uhh(h!jhMkh j ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j ubjs)}(hhh]j5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jA ubj:)}(hhh]h;)}(hSample Problemh]h/Sample Problem}(hjR h jP ubah}(h]h]h]h]h]uhh:h!jhMoh jM ubah}(h]h]h]h]h]uhj9h jA ubj:)}(hhh]h;)}(hCSASh]h/CSAS}(hji h jg ubah}(h]h]h]h]h]uhh:h!jhMoh jd ubah}(h]h]h]h]h]uhj9h jA ubj:)}(hhh]h;)}(h Sourcererh]h/ Sourcerer}(hj h j~ ubah}(h]h]h]h]h]uhh:h!jhMoh j{ ubah}(h]h]h]h]h]uhj9h jA ubeh}(h]h]h]h]h]uhj4h j> ubah}(h]h]h]h]h]uhjrh j ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h enumerated_list)}(hhh]j)}(hhh]h}(h]h]h]h]h]uhjh j ubah}(h]h]h]h]h]enumtypearabicprefixhsuffixjuhj h j ubah}(h]h]h]h]h]uhj9h j ubj:)}(hhh]h;)}(hKENO V.a geometry, v7-252h]h/KENO V.a geometry, v7-252}(hj h j ubah}(h]h]h]h]h]uhh:h!jhMqh j ubah}(h]h]h]h]h]uhj9h j ubj:)}(hhh]h;)}(h1.0045 ± 0.0017h]h/1.0045 ± 0.0017}(hj h j ubah}(h]h]h]h]h]uhh:h!jhMqh j ubah}(h]h]h]h]h]uhj9h j ubj:)}(hhh]h;)}(h1.0054 ±0.0018h]h/1.0054 ±0.0018}(hj h j ubah}(h]h]h]h]h]uhh:h!jhMqh j ubah}(h]h]h]h]h]uhj9h j ubeh}(h]h]h]h]h]uhj4h j ubj5)}(hhh](j:)}(hhh]j )}(hhh]j)}(hhh]h}(h]h]h]h]h]uhjh j!ubah}(h]h]h]h]h]j j j hj jstartKuhj h j!ubah}(h]h]h]h]h]uhj9h j!ubj:)}(hhh]h;)}(hKENO-VI geometry, v7-252h]h/KENO-VI geometry, v7-252}(hj4!h j2!ubah}(h]h]h]h]h]uhh:h!jhMsh j/!ubah}(h]h]h]h]h]uhj9h j!ubj:)}(hhh]h;)}(h0.9998 ± 0.0018h]h/0.9998 ± 0.0018}(hjK!h jI!ubah}(h]h]h]h]h]uhh:h!jhMsh jF!ubah}(h]h]h]h]h]uhj9h j!ubj:)}(hhh]h;)}(h1.0007 ±0.0020h]h/1.0007 ±0.0020}(hjb!h j`!ubah}(h]h]h]h]h]uhh:h!jhMsh j]!ubah}(h]h]h]h]h]uhj9h j!ubeh}(h]h]h]h]h]uhj4h j ubj5)}(hhh](j:)}(hhh]j )}(hhh]j)}(hhh]h}(h]h]h]h]h]uhjh j!ubah}(h]h]h]h]h]j j j hj jj(!Kuhj h j}!ubah}(h]h]h]h]h]uhj9h jz!ubj:)}(hhh]h;)}(hKENO V.a geometry, ce_v7h]h/KENO V.a geometry, ce_v7}(hj!h j!ubah}(h]h]h]h]h]uhh:h!jhMuh j!ubah}(h]h]h]h]h]uhj9h jz!ubj:)}(hhh]h;)}(h1.0058±0.0027h]h/1.0058±0.0027}(hj!h j!ubah}(h]h]h]h]h]uhh:h!jhMuh j!ubah}(h]h]h]h]h]uhj9h jz!ubj:)}(hhh]h;)}(h1.0026 ±0.0017h]h/1.0026 ±0.0017}(hj!h j!ubah}(h]h]h]h]h]uhh:h!jhMuh j!ubah}(h]h]h]h]h]uhj9h jz!ubeh}(h]h]h]h]h]uhj4h j ubj5)}(hhh](j:)}(hhh]j )}(hhh]j)}(hhh]h}(h]h]h]h]h]uhjh j!ubah}(h]h]h]h]h]j j j hj jj(!Kuhj h j!ubah}(h]h]h]h]h]uhj9h j!ubj:)}(hhh]h;)}(hKENO-VI geometry, ce_v7h]h/KENO-VI geometry, ce_v7}(hj"h j"ubah}(h]h]h]h]h]uhh:h!jhMwh j"ubah}(h]h]h]h]h]uhj9h j!ubj:)}(hhh]h;)}(h0.9990 ±0.0023h]h/0.9990 ±0.0023}(hj"h j"ubah}(h]h]h]h]h]uhh:h!jhMwh j"ubah}(h]h]h]h]h]uhj9h j!ubj:)}(hhh]h;)}(h1.0041 ±0.0016h]h/1.0041 ±0.0016}(hj4"h j2"ubah}(h]h]h]h]h]uhh:h!jhMwh j/"ubah}(h]h]h]h]h]uhj9h j!ubeh}(h]h]h]h]h]uhj4h j ubeh}(h]h]h]h]h]uhj/h j ubeh}(h]h]h]h]h]colsKuhjh j ubeh}(h](id102j eh]h]tab2-4-8ah]h]jcenteruhjh jhhh!jhNj}j^"jsj}j jsubh;)}(hThe Denovo fission source provides a reliable starting source that is
similar to the actual fission source distribution computed by KENO
(using ``npg``\ =250000), as shown in :numref:`fig2-4-2`.h](h/The Denovo fission source provides a reliable starting source that is
similar to the actual fission source distribution computed by KENO
(using }(hThe Denovo fission source provides a reliable starting source that is
similar to the actual fission source distribution computed by KENO
(using h jd"hhh!NhNubj)}(h``npg``h]h/npg}(hhh jm"ubah}(h]h]h]h]h]uhjh jd"ubh/ =250000), as shown in }(h\ =250000), as shown in h jd"hhh!NhNubh_)}(h:numref:`fig2-4-2`h]j)}(hj"h]h/fig2-4-2}(hhh j"ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j"ubah}(h]h]h]h]h]refdocj refdomainj"reftypenumrefrefexplicitrefwarnjfig2-4-2uhh^h!jhMzh jd"ubh/.}(hjh jd"hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMzh jhhubh)}(h
.. _fig2-4-2:h]h}(h]h]h]h]h]hfig2-4-2uhh
hM)h jhhh!jubj)}(hhh](j)}(h.. figure:: figs/Sourcerer/fig2.png
:align: center
:width: 700
Fission source distribution from Denovo (left) and KENO (right).
h]h}(h]h]h]h]h]width700urifigs/Sourcerer/fig2.pngj}jj"suhjh j"h!jhMubj)}(h@Fission source distribution from Denovo (left) and KENO (right).h]h/@Fission source distribution from Denovo (left) and KENO (right).}(hj"h j"ubah}(h]h]h]h]h]uhjh!jhMh j"ubeh}(h](id103j"eh]h]fig2-4-2ah]h]jcenteruhjhMh jhhh!jj}j"j"sj}j"j"subeh}(h]output-fileah]h]output fileah]h]uhh#h jhhh!jhMdubh$)}(hhh](h))}(hOther variationsh]h/Other variations}(hj"h j"hhh!NhNubah}(h]h]h]h]h]uhh(h j"hhh!jhMubh;)}(hXTo increase the Denovo calculation speed (but decrease the fidelity of
the fission source result), the discretization in angle (``quadrature=`` or
``polarsPerOct=/azimuthsPerOct=``) can be coarsened and/or the tolerance
parameters can be loosened. To reduce the amount of memory required by
Denovo, the number of Legendre moments in the scattering cross-section
expansion can be reduced (``legendre=``). Using macromaterials can help
increase the fidelity of the Denovo calculation with only a small
increase in model setup time. Macromaterials do not impact the Denovo
run time. Denovo diagnostic messages can be turned on and will print to
the messages file.h](h/To increase the Denovo calculation speed (but decrease the fidelity of
the fission source result), the discretization in angle (}(hTo increase the Denovo calculation speed (but decrease the fidelity of
the fission source result), the discretization in angle (h j"hhh!NhNubj)}(h``quadrature=``h]h/quadrature=}(hhh j#ubah}(h]h]h]h]h]uhjh j"ubh/ or
}(h or
h j"hhh!NhNubj)}(h!``polarsPerOct=/azimuthsPerOct=``h]h/polarsPerOct=/azimuthsPerOct=}(hhh j#ubah}(h]h]h]h]h]uhjh j"ubh/) can be coarsened and/or the tolerance
parameters can be loosened. To reduce the amount of memory required by
Denovo, the number of Legendre moments in the scattering cross-section
expansion can be reduced (}(h) can be coarsened and/or the tolerance
parameters can be loosened. To reduce the amount of memory required by
Denovo, the number of Legendre moments in the scattering cross-section
expansion can be reduced (h j"hhh!NhNubj)}(h
``legendre=``h]h/ legendre=}(hhh j(#ubah}(h]h]h]h]h]uhjh j"ubh/X). Using macromaterials can help
increase the fidelity of the Denovo calculation with only a small
increase in model setup time. Macromaterials do not impact the Denovo
run time. Denovo diagnostic messages can be turned on and will print to
the messages file.}(hX). Using macromaterials can help
increase the fidelity of the Denovo calculation with only a small
increase in model setup time. Macromaterials do not impact the Denovo
run time. Denovo diagnostic messages can be turned on and will print to
the messages file.h j"hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh j"hhubj)}(hhh]j)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h jD#ubj$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h jD#ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(h Macromaterials (higher fidelity)h]h/ Macromaterials (higher fidelity)}(hjd#h jb#ubah}(h]h]h]h]h]uhh:h!jhMh j_#ubah}(h]h]h]h]h]uhj9h j\#ubj:)}(hhh]h;)}(h!Looser tolerances (faster Denovo)h]h/!Looser tolerances (faster Denovo)}(hj{#h jy#ubah}(h]h]h]h]h]uhh:h!jhMh jv#ubah}(h]h]h]h]h]uhj9h j\#ubeh}(h]h]h]h]h]uhj4h jY#ubj5)}(hhh](j:)}(hhh]j)}(hnread detSource
…
macromaterial
mmSubCell=3
mmTolerance=0.001
end macromaterial
end detSourceh]h/nread detSource
…
macromaterial
mmSubCell=3
mmTolerance=0.001
end macromaterial
end detSource}(hhh j#ubah}(h]h]h]h]h]jjuhjh!jhMh j#ubah}(h]h]h]h]h]uhj9h j#ubj:)}(hhh]j)}(hread detSource
…
eigenValParams
…
tolerance=1.0e-2
kTolerance=1.0e-3
end eigenValParams
end detSourceh]h/read detSource
…
eigenValParams
…
tolerance=1.0e-2
kTolerance=1.0e-3
end eigenValParams
end detSource}(hhh j#ubah}(h]h]h]h]h]jjuhjh!jhMh j#ubah}(h]h]h]h]h]uhj9h j#ubeh}(h]h]h]h]h]uhj4h jY#ubeh}(h]h]h]h]h]uhj/h jD#ubeh}(h]h]h]h]h]colsKuhjh jA#ubah}(h]h]h]h]h]jcenteruhjh j"hhh!NhNubj)}(hhh]j)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h j#ubj$)}(hhh]h}(h]h]h]h]h]j.K2uhj#h j#ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hScreen messagesh]h/Screen messages}(hj$h j#ubah}(h]h]h]h]h]uhh:h!jhMh j#ubah}(h]h]h]h]h]uhj9h j#ubj:)}(hhh]h;)}(hHigher fidelity (slower Denovo)h]h/Higher fidelity (slower Denovo)}(hj$h j$ubah}(h]h]h]h]h]uhh:h!jhMh j$ubah}(h]h]h]h]h]uhj9h j#ubeh}(h]h]h]h]h]uhj4h j#ubj5)}(hhh](j:)}(hhh]j)}(hread detSource
…
eigenValParams
…
diagnostics=1
output=1
diagnosticLevel=1
end eigenValParams
end detSourceh]h/read detSource
…
eigenValParams
…
diagnostics=1
output=1
diagnosticLevel=1
end eigenValParams
end detSource}(hhh j6$ubah}(h]h]h]h]h]jjuhjh!jhMh j3$ubah}(h]h]h]h]h]uhj9h j0$ubj:)}(hhh]j)}(hread sequence
…
eigenValParams
…
quadType=2
polarsPerOct=4
azimuthsPerOct=4
legendre=3
end eigenValParams
end sequenceh]h/read sequence
…
eigenValParams
…
quadType=2
polarsPerOct=4
azimuthsPerOct=4
legendre=3
end eigenValParams
end sequence}(hhh jM$ubah}(h]h]h]h]h]jjuhjh!jhMh jJ$ubah}(h]h]h]h]h]uhj9h j0$ubeh}(h]h]h]h]h]uhj4h j#ubeh}(h]h]h]h]h]uhj/h j#ubeh}(h]h]h]h]h]colsKuhjh j#ubah}(h]h]h]h]h]jcenteruhjh j"hhh!NhNubh;)}(hhh](j)}(hhh](j#)}(hhh]h/evans_denovo_2010}(hhh j$ubah}(h]h]h]h]h]j1uhj"h j~$ubh;)}(hhh](h/Thomas}(hThomash j$ubj<h/M. Evans, Alissa}(hM. Evans, Alissah j$ubj<h/S. Stafford, Rachel}(hS. Stafford, Rachelh j$ubj<h/N. Slaybaugh, and Kevin}(hN. Slaybaugh, and Kevinh j$ubj<h/
T. Clarno.}(h
T. Clarno.h j$ubj\h/Denovo: }(hDenovo: h j$ubh/A}(hj8h j$ubh/; new three-dimensional parallel discrete ordinates code in }(h; new three-dimensional parallel discrete ordinates code in h j$ubh/SCALE}(hSCALEh j$ubh/.}(hjh j$ubj\h)}(hhh]h/Nuclear technology}(hNuclear technologyh j$ubah}(h]h]h]h]h]uhhh j$ubh/, 171(2):171–200, 2010.}(h, 171(2):171–200, 2010.h j$ubj\h/Publisher: Taylor & Francis.}(hPublisher: Taylor & Francis.h j$ubeh}(h]h]h]h]h]uhh:h j~$ubeh}(h]id67ah]hwah]h]evans_denovo_2010ah]jjuhh|jmKh j{$ubj)}(hhh](j#)}(hhh]h/goluoglu_monte_2011}(hhh j$ubah}(h]h]h]h]h]j1uhj"h j$ubh;)}(hhh](h/Sedat Goluoglu, Lester}(hSedat Goluoglu, Lesterh j$ubj<h/ M. Petrie}(h M. Petrieh j$ubj<h/Jr, Michael}(hJr, Michaelh j$ubj<h/E. Dunn, Daniel}(hE. Dunn, Danielh j$ubj<h/F. Hollenbach, and Bradley}(hF. Hollenbach, and Bradleyh j$ubj<h/T. Rearden.}(hT. Rearden.h j$ubj\h/Monte }(hMonte h j$ubh/Carlo}(hCarloh j$ubh/2 criticality methods and analysis capabilities in }(h2 criticality methods and analysis capabilities in h j$ubh/SCALE}(hSCALEh j$ubh/.}(hjh j$ubj\h)}(hhh]h/Nuclear Technology}(hNuclear Technologyh j0%ubah}(h]h]h]h]h]uhhh j$ubh/, 174(2):214–235, 2011.}(h, 174(2):214–235, 2011.h j$ubj\h/Publisher: Taylor & Francis.}(hPublisher: Taylor & Francis.h j$ubeh}(h]h]h]h]h]uhh:h j$ubeh}(h]id68ah]hwah]h]goluoglu_monte_2011ah]jjuhh|jmKh j{$ubj)}(hhh](j#)}(hhh]h/ibrahim_hybrid_2013}(hhh jY%ubah}(h]h]h]h]h]j1uhj"h jV%ubh;)}(hhh](h/Ahmad}(hAhmadh jf%ubj<h/M. Ibrahim, Douglas}(hM. Ibrahim, Douglash jf%ubj<h/E. Peplow, Kursat}(hE. Peplow, Kursath jf%ubj<h/B. Bekar, Cihangir Celik, John}(hB. Bekar, Cihangir Celik, Johnh jf%ubj<h/ M. Scaglione, Dan Ilas, and John}(h M. Scaglione, Dan Ilas, and Johnh jf%ubj<h/
C. Wagner.}(h
C. Wagner.h jf%ubj\h/Hybrid technique in }(hHybrid technique in h jf%ubh/SCALE}(hSCALEh jf%ubh/F for fission source convergence applied to used nuclear fuel analysis.}(hF for fission source convergence applied to used nuclear fuel analysis.h jf%ubj\h/In }(hIn h jf%ubh)}(hhh](h/preparation for the 2013 }(hpreparation for the 2013 h j%ubh/Topical}(hTopicalh j%ubh/ }(hjTh j%ubh/Meeting}(hMeetingh j%ubh/ on }(h on h j%ubh/Nuclear}(hNuclearh j%ubh/ }(hjTh j%ubh/Criticality}(hCriticalityh j%ubh/ }(hjTh j%ubh/Safety}(hSafetyh j%ubh/ (}(h (h j%ubh/NCSD}(hNCSDh j%ubh/ 2013), }(h 2013), h j%ubh/
Wilmington}(h
Wilmingtonh j%ubh/, }(h, h j%ubh/NC}(hNCh j%ubeh}(h]h]h]h]h]uhhh jf%ubh/. 2013.}(h. 2013.h jf%ubeh}(h]h]h]h]h]uhh:h jV%ubeh}(h]id69ah]hwah]h]ibrahim_hybrid_2013ah]jjuhh|jmKh j{$ubj)}(hhh](j#)}(hhh]h/ibrahim_acceleration_2011}(hhh j&ubah}(h]h]h]h]h]j1uhj"h j&ubh;)}(hhh](h/Ahmad}(hAhmadh j&ubj<h/M. Ibrahim, Douglas}(hM. Ibrahim, Douglash j&ubj<h/E. Peplow, John}(hE. Peplow, Johnh j&ubj<h/C. Wagner, Scott}(hC. Wagner, Scotth j&ubj<h/W. Mosher, and Thomas}(hW. Mosher, and Thomash j&ubj<h/ M. Evans.}(h M. Evans.h j&ubh/ }(h h j&ubh/Acceleration of }(hAcceleration of h j&ubh/Monte}(hMonteh j&ubh/ }(h h j&ubh/Carlo}(hCarloh j&ubh/ }(h h j&ubh/Criticality}(hCriticalityh j&ubh/ }(h h j&ubh/Calculations}(hCalculationsh j&ubh/ }(h h j&ubh/Using}(hUsingh j&ubh/ }(h h j&ubh/
Deterministic}(h
Deterministich j&ubh/-}(h-h j&ubh/Based}(hBasedh j&ubh/ }(h h j&ubh/Starting}(hStartingh j&ubh/ }(hj9&h j&ubh/Sources}(hSourcesh j&ubh/.}(hjh j&ubj\h)}(hhh]h/,Transactions of the American Nuclear Society}(h,Transactions of the American Nuclear Societyh j&ubah}(h]h]h]h]h]uhhh j&ubh/, 105:539–541, 2011.}(h, 105:539–541, 2011.h j&ubj\h/)Publisher: American Nuclear Society, Inc.}(h)Publisher: American Nuclear Society, Inc.h j&ubeh}(h]h]h]h]h]uhh:h j&ubeh}(h]id70ah]hwah]h]ibrahim_acceleration_2011ah]jjuhh|jmKh j{$ubj)}(hhh](j#)}(hhh]h/kiedrowski_statistical_2011}(hhh j&ubah}(h]h]h]h]h]j1uhj"h j&ubh;)}(hhh](h/Brian}(hBrianh j&ubj<h/C. Kiedrowski and Clell}(hC. Kiedrowski and Clellh j&ubj<h/J. Solomon.}(hJ. Solomon.h j&ubh/ }(h h j&ubh/#Statistical assessment of numerous }(h#Statistical assessment of numerous h j&ubh/Monte}(hMonteh j&ubh/ }(hj&h j&ubh/Carlo}(hCarloh j&ubh/ tallies.}(h tallies.h j&ubj\h/WTechnical Report, Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2011.}(hWTechnical Report, Los Alamos National Lab.(LANL), Los Alamos, NM (United States), 2011.h j&ubeh}(h]h]h]h]h]uhh:h j&ubeh}(h]kiedrowski-statistical-2011ah]hwah]kiedrowski_statistical_2011ah]h]jajjuhh|h j{$jKubj)}(hhh](j#)}(hhh]h/shannon_mathematical_1948}(hhh j'ubah}(h]h]h]h]h]j1uhj"h j'ubh;)}(hhh](h/Claude}(hClaudeh j'ubj<h/E. Shannon.}(hE. Shannon.h j'ubj\h/'A mathematical theory of communication.}(h'A mathematical theory of communication.h j'ubj\h)}(hhh]h/!The Bell system technical journal}(h!The Bell system technical journalh j1'ubah}(h]h]h]h]h]uhhh j'ubh/, 27(3):379–423, 1948.}(h, 27(3):379–423, 1948.h j'ubj\h/Publisher: Nokia Bell Labs.}(hPublisher: Nokia Bell Labs.h j'ubeh}(h]h]h]h]h]uhh:h j'ubeh}(h]shannon-mathematical-1948ah]hwah]shannon_mathematical_1948ah]h]jajjuhh|h j{$jKubj)}(hhh](j#)}(hhh]h/ueki_stationarity_2003}(hhh jZ'ubah}(h]h]h]h]h]j1uhj"h jW'ubh;)}(hhh](h/Taro Ueki and Forrest}(hTaro Ueki and Forresth jg'ubj<h/ B. Brown.}(h B. Brown.h jg'ubh/ }(h h jg'ubh/3Stationarity and source convergence diagnostics in }(h3Stationarity and source convergence diagnostics in h jg'ubh/Monte}(hMonteh jg'ubh/ }(hjx'h jg'ubh/Carlo}(hCarloh jg'ubh/ criticality calculation.}(h criticality calculation.h jg'ubj\h/In }(hIn h jg'ubh)}(hhh](h/Proceedings of }(hProceedings of h j'ubh/M}(hjh j'ubh/&}(h&h j'ubh/C}(hjh j'ubh/ 2003, }(h 2003, h j'ubh/ANS}(hANSh j'ubh/ }(hjTh j'ubh/Topical}(hTopicalh j'ubh/ }(hjTh j'ubh/Meeting}(hMeetingh j'ubeh}(h]h]h]h]h]uhhh jg'ubh/. 2003.}(h. 2003.h jg'ubeh}(h]h]h]h]h]uhh:h jW'ubeh}(h]ueki-stationarity-2003ah]hwah]ueki_stationarity_2003ah]h]jajjuhh|h j{$jKubj)}(hhh](j#)}(hhh]h/ueki_stationarity_2005}(hhh j'ubah}(h]h]h]h]h]j1uhj"h j'ubh;)}(hhh](h/Taro Ueki and Forrest}(hTaro Ueki and Forresth j'ubj<h/ B. Brown.}(h B. Brown.h j'ubh/ }(h h j'ubh/;Stationarity modeling and informatics-based diagnostics in }(h;Stationarity modeling and informatics-based diagnostics in h j'ubh/Monte}(hMonteh j'ubh/ }(hj(h j'ubh/Carlo}(hCarloh j'ubh/ criticality calculations.}(h criticality calculations.h j'ubj\h)}(hhh]h/Nuclear science and engineering}(hNuclear science and engineeringh j(ubah}(h]h]h]h]h]uhhh j'ubh/, 149(1):38–50, 2005.}(h, 149(1):38–50, 2005.h j'ubj\h/Publisher: Taylor & Francis.}(hPublisher: Taylor & Francis.h j'ubeh}(h]h]h]h]h]uhh:h j'ubeh}(h]ueki-stationarity-2005ah]hwah]ueki_stationarity_2005ah]h]jajjuhh|h j{$jKubeh}(h]1bibtex-bibliography-Criticality Safety Overview-4ah]h]h]h]uhh:h j"hhh!NhNubh)}(h .. _2-4A:h]h}(h]h]h]h]h]hauhh
hM=*h j"hhh!jubeh}(h]other-variationsah]h]other variationsah]h]uhh#h jhhh!jhMubeh}(h]jezebelah]h]jezebelah]h]uhh#h jhhh!jhMubeh}(h]id53ah]h]h]sample problemsah]uhh#h jhhh!jhMjmKubh$)}(hhh](h))}(h#DEVC: Denovo EigenValue Calculationh]h/#DEVC: Denovo EigenValue Calculation}(hjo(h jm(hhh!NhNubah}(h]h]h]h]h]uhh(h jj(hhh!jhKubh;)}(h&*Douglas E. Peplow and Cihangir Celik*h]h)}(hj}(h]h/$Douglas E. Peplow and Cihangir Celik}(hhh j(ubah}(h]h]h]h]h]uhhh j{(ubah}(h]h]h]h]h]uhh:h!jhKh jj(hhubeh}(h]("devc-denovo-eigenvalue-calculationjQ(eh]h](#devc: denovo eigenvalue calculation2-4aeh]h]uhh#h jhhh!jhKj}j(jG(sj}jQ(jG(subh$)}(hhh](h))}(hIntroductionh]h/Introduction}(hj(h j(hhh!NhNubah}(h]h]h]h]h]uhh(h j(hhh!jhK ubh;)}(hXThe DEVC (Denovo EigenValue Calculation) sequence is an interface to the
Denovo discrete-ordinates package :cite:`evans_denovo_2010` for calculating criticality
eigenvalue problems. This sequence reads an input file very similar to a
CSAS6 input file :cite:`goluoglu_monte_2011` that contains an extra block of input for
describing the Denovo mesh grid and calculational parameters. Many of
the subroutines are shared from the MAVRIC routines that interface with
Denovo for fixed-source calculations.h](h/kThe DEVC (Denovo EigenValue Calculation) sequence is an interface to the
Denovo discrete-ordinates package }(hkThe DEVC (Denovo EigenValue Calculation) sequence is an interface to the
Denovo discrete-ordinates package h j(hhh!NhNubh_)}(hevans_denovo_2010h]he)}(hj(h]h/[evans_denovo_2010]}(hhh j(ubah}(h]h]h]h]h]uhhdh j(ubah}(h]id55ah]hwah]h]h] refdomainh|reftypeh~ reftargetj(refwarnsupport_smartquotesuhh^h!jhKh j(hhubh/w for calculating criticality
eigenvalue problems. This sequence reads an input file very similar to a
CSAS6 input file }(hw for calculating criticality
eigenvalue problems. This sequence reads an input file very similar to a
CSAS6 input file h j(hhh!NhNubh_)}(hgoluoglu_monte_2011h]he)}(hj(h]h/[goluoglu_monte_2011]}(hhh j(ubah}(h]h]h]h]h]uhhdh j(ubah}(h]id56ah]hwah]h]h] refdomainh|reftypeh~ reftargetj(refwarnsupport_smartquotesuhh^h!jhKh j(hhubh/ that contains an extra block of input for
describing the Denovo mesh grid and calculational parameters. Many of
the subroutines are shared from the MAVRIC routines that interface with
Denovo for fixed-source calculations.}(h that contains an extra block of input for
describing the Denovo mesh grid and calculational parameters. Many of
the subroutines are shared from the MAVRIC routines that interface with
Denovo for fixed-source calculations.h j(hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh j(hhubh;)}(hXlThis manual assumes that the user is familiar with the
discrete-ordinates method for radiation transport and the Denovo
package. DEVC provides an easy way for users to modify existing CSAS6
inputs and use them to run Denovo. The DEVC sequence also provides a way
to create mesh geometry for Denovo from the combinatorial solid geometry
description used by KENO-VI.h]h/XlThis manual assumes that the user is familiar with the
discrete-ordinates method for radiation transport and the Denovo
package. DEVC provides an easy way for users to modify existing CSAS6
inputs and use them to run Denovo. The DEVC sequence also provides a way
to create mesh geometry for Denovo from the combinatorial solid geometry
description used by KENO-VI.}(hj)h j)hhh!NhNubah}(h]h]h]h]h]uhh:h!jhKh j(hhubh;)}(hAThe steps in the DEVC sequence are listed in :numref:`tab2-4a-1`.h](h/-The steps in the DEVC sequence are listed in }(h-The steps in the DEVC sequence are listed in h j)hhh!NhNubh_)}(h:numref:`tab2-4a-1`h]j)}(hj)h]h/ tab2-4a-1}(hhh j)ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j)ubah}(h]h]h]h]h]refdocj refdomainj&)reftypenumrefrefexplicitrefwarnj tab2-4a-1uhh^h!jhKh j)ubh/.}(hjh j)hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh j(hhubh)}(h.. _tab2-4a-1:h]h}(h]h]h]h]h]h tab2-4a-1uhh
hMX*h j(hhh!jubj)}(hhh](h))}(h1Steps in DEVC for an input file named *input*.inph](h/&Steps in DEVC for an input file named }(h&Steps in DEVC for an input file named h jP)ubh)}(h*input*h]h/input}(hhh jY)ubah}(h]h]h]h]h]uhhh jP)ubh/.inp}(h.inph jP)ubeh}(h]h]h]h]h]uhh(h!jhKh jM)ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jr)ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jr)ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jr)ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jr)ubjs)}(hhh]j5)}(hhh](j:)}(hhh]h;)}(hSteph]h/Step}(hj)h j)ubah}(h]h]h]h]h]uhh:h!jhK!h j)ubah}(h]h]h]h]h]uhj9h j)ubj:)}(hhh]h;)}(hModule/Taskh]h/Module/Task}(hj)h j)ubah}(h]h]h]h]h]uhh:h!jhK!h j)ubah}(h]h]h]h]h]uhj9h j)ubj:)}(hhh]h;)}(hCreates fileh]h/Creates file}(hj)h j)ubah}(h]h]h]h]h]uhh:h!jhK!h j)ubah}(h]h]h]h]h]uhj9h j)ubj:)}(hhh]h;)}(h
To stop afterh]h/
To stop after}(hj)h j)ubah}(h]h]h]h]h]uhh:h!jhK!h j)ubah}(h]h]h]h]h]uhj9h j)ubeh}(h]h]h]h]h]uhj4h j)ubah}(h]h]h]h]h]uhjrh jr)ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hjh]h/0}(hjh j*ubah}(h]h]h]h]h]uhh:h!jhK#h j*ubah}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h;)}(hCheck user
inputh]h/Check user
input}(hj,*h j**ubah}(h]h]h]h]h]uhh:h!jhK#h j'*ubah}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubeh}(h]h]h]h]h]uhj4h j*ubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jV*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h jV*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h jV*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h jV*ubeh}(h]h]h]h]h]uhj4h j*ubj5)}(hhh](j:)}(hhh]h;)}(hjzh]h/1}(hjzh j*ubah}(h]h]h]h]h]uhh:h!jhK(h j*ubah}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h;)}(h/Self-shielding
(celldata/cellm
ix)
calculationsh]h//Self-shielding
(celldata/cellm
ix)
calculations}(hj*h j*ubah}(h]h]h]h]h]uhh:h!jhK(h j*ubah}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubeh}(h]h]h]h]h]uhj4h j*ubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubeh}(h]h]h]h]h]uhj4h j*ubj5)}(hhh](j:)}(hhh]h;)}(h2h]h/2}(hj+h j*ubah}(h]h]h]h]h]uhh:h!jhK/h j*ubah}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h;)}(hProduces
optional \*.png
plotsh]h/Produces
optional *.png
plots}(hProduces
optional \*.png
plotsh j+ubah}(h]h]h]h]h]uhh:h!jhK/h j+ubah}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j*ubeh}(h]h]h]h]h]uhj4h j*ubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jB+ubj:)}(hhh]h;)}(hFProduces
optional
\*.3mdap files
(to visualize
grid in
MeshFileViewer)h]h/FProduces
optional
*.3mdap files
(to visualize
grid in
MeshFileViewer)}(hFProduces
optional
\*.3mdap files
(to visualize
grid in
MeshFileViewer)h jQ+ubah}(h]h]h]h]h]uhh:h!jhK3h jN+ubah}(h]h]h]h]h]uhj9h jB+ubj:)}(hhh]h}(h]h]h]h]h]uhj9h jB+ubj:)}(hhh]h;)}(h``parm=check``h]j)}(hjt+h]h/
parm=check}(hhh jv+ubah}(h]h]h]h]h]uhjh jr+ubah}(h]h]h]h]h]uhh:h!jhK3h jo+ubah}(h]h]h]h]h]uhj9h jB+ubeh}(h]h]h]h]h]uhj4h j*ubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j+ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j+ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j+ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j+ubeh}(h]h]h]h]h]uhj4h j*ubj5)}(hhh](j:)}(hhh]h;)}(hjh]h/3}(hjh j+ubah}(h]h]h]h]h]uhh:h!jhKThe keyword “``make3dmap``” for a particular grid geometry definition will
create a file called “\ *outputName*.grid\ *id*.3dmap”, which can be
visualized using the Java Mesh File Viewer. These files will contain
crude geometry information (unit, region, material) that corresponds to
the center of each voxel.h](h/The keyword “}(hThe keyword “h jX1hhh!NhNubj)}(h
``make3dmap``h]h/ make3dmap}(hhh ja1ubah}(h]h]h]h]h]uhjh jX1ubh/M” for a particular grid geometry definition will
create a file called “ }(hM” for a particular grid geometry definition will
create a file called “\ h jX1hhh!NhNubh)}(h*outputName*h]h/
outputName}(hhh jt1ubah}(h]h]h]h]h]uhhh jX1ubh/.grid }(h.grid\ h jX1hhh!NhNubh)}(h*id*h]h/id}(hhh j1ubah}(h]h]h]h]h]uhhh jX1ubh/.3dmap”, which can be
visualized using the Java Mesh File Viewer. These files will contain
crude geometry information (unit, region, material) that corresponds to
the center of each voxel.}(h.3dmap”, which can be
visualized using the Java Mesh File Viewer. These files will contain
crude geometry information (unit, region, material) that corresponds to
the center of each voxel.h jX1hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh j/hhubh;)}(hGKeywords for the grid geometry block are listed in :numref:`tab2-4a-5`.h](h/3Keywords for the grid geometry block are listed in }(h3Keywords for the grid geometry block are listed in h j1hhh!NhNubh_)}(h:numref:`tab2-4a-5`h]j)}(hj1h]h/ tab2-4a-5}(hhh j1ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j1ubah}(h]h]h]h]h]refdocj refdomainj1reftypenumrefrefexplicitrefwarnj tab2-4a-5uhh^h!jhKh j1ubh/.}(hjh j1hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh j/hhubj)}(hhh](h))}(hGrid geometry input keywordsh]h/Grid geometry input keywords}(hj1h j1ubah}(h]h]h]h]h]uhh(h!jhKh j1ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.Kduhj#h j1ubj0)}(hhh]j5)}(hhh]j:)}(hhh]j)}(h.. image:: figs/DEVC/tab5.pngh]h}(h]h]h]h]h]urifigs/DEVC/tab5.pngj}jj2suhjh j1h!jhKubah}(h]h]h]h]h]uhj9h j1ubah}(h]h]h]h]h]uhj4h j1ubah}(h]h]h]h]h]uhj/h j1ubeh}(h]h]h]h]h]colsKuhjh j1ubeh}(h] tab2-4a-5ah]h] tab2-4a-5ah]h]jcenteruhjh j/hhh!NhNubeh}(h]grid-geometry-blockah]h]grid geometry blockah]h]uhh#h j-hhh!jhKubh$)}(hhh](h))}(hMacromaterial blockh]h/Macromaterial block}(hj52h j32hhh!NhNubah}(h]h]h]h]h]uhh(h j02hhh!jhKubh;)}(hXDIn order to get more accurate solutions from a coarse-mesh
discrete-ordinates calculation, Denovo can represent the material in
each voxel of the mesh as a volume-weighted mixture of the real
materials in the problem. When constructing the Denovo input, DEVC can
estimate the volume fraction taken by each real material in each voxel
by a sampling method. The user can specify parameters for how to sample
the geometry. Note that finer sampling makes more accurate estimates of
the material fraction but requires more setup time to create the Denovo
input. Users should understand how the macromaterials are sampled and
consider that when constructing a mesh grid. This is especially
important for geometries that contain arrays. Careful consideration
should be given when overlaying a mesh on a geometry that contains
arrays of arrays.h]h/XDIn order to get more accurate solutions from a coarse-mesh
discrete-ordinates calculation, Denovo can represent the material in
each voxel of the mesh as a volume-weighted mixture of the real
materials in the problem. When constructing the Denovo input, DEVC can
estimate the volume fraction taken by each real material in each voxel
by a sampling method. The user can specify parameters for how to sample
the geometry. Note that finer sampling makes more accurate estimates of
the material fraction but requires more setup time to create the Denovo
input. Users should understand how the macromaterials are sampled and
consider that when constructing a mesh grid. This is especially
important for geometries that contain arrays. Careful consideration
should be given when overlaying a mesh on a geometry that contains
arrays of arrays.}(hjC2h jA2hhh!NhNubah}(h]h]h]h]h]uhh:h!jhKh j02hhubh;)}(hXBecause the list of macromaterials could become large, the user can also
specify a tolerance for how close two different macromaterials can be to
be considered the same, thereby reducing the total number of
macromaterials. The macromaterial tolerance, ``“mmTolerance=”``, is used for
creating a different macromaterial from the ones already created by
looking at the infinity norm between two macromaterials.h](h/Because the list of macromaterials could become large, the user can also
specify a tolerance for how close two different macromaterials can be to
be considered the same, thereby reducing the total number of
macromaterials. The macromaterial tolerance, }(hBecause the list of macromaterials could become large, the user can also
specify a tolerance for how close two different macromaterials can be to
be considered the same, thereby reducing the total number of
macromaterials. The macromaterial tolerance, h jO2hhh!NhNubj)}(h``“mmTolerance=”``h]h/“mmTolerance=”}(hhh jX2ubah}(h]h]h]h]h]uhjh jO2ubh/, is used for
creating a different macromaterial from the ones already created by
looking at the infinity norm between two macromaterials.}(h, is used for
creating a different macromaterial from the ones already created by
looking at the infinity norm between two macromaterials.h jO2hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh j02hhubh;)}(h`The number of macromaterials does not appreciably impact Denovo run time
or memory requirements.h]h/`The number of macromaterials does not appreciably impact Denovo run time
or memory requirements.}(hjs2h jq2hhh!NhNubah}(h]h]h]h]h]uhh:h!jhKh j02hhubh;)}(hX
Keywords for the macromaterial block are listed :numref:`tab2-4a-6`. Two
different sampling methods are available – ray tracing :cite:`ibrahim_improving_2009` with the
keyword ``mmRayTest`` and point testing :cite:`johnson_fast_2013` with the keyword ``mmPointTest``.h](h/0Keywords for the macromaterial block are listed }(h0Keywords for the macromaterial block are listed h j2hhh!NhNubh_)}(h:numref:`tab2-4a-6`h]j)}(hj2h]h/ tab2-4a-6}(hhh j2ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j2ubah}(h]h]h]h]h]refdocj refdomainj2reftypenumrefrefexplicitrefwarnj tab2-4a-6uhh^h!jhKh j2ubh/?. Two
different sampling methods are available – ray tracing }(h?. Two
different sampling methods are available – ray tracing h j2hhh!NhNubh_)}(hibrahim_improving_2009h]he)}(hj2h]h/[ibrahim_improving_2009]}(hhh j2ubah}(h]h]h]h]h]uhhdh j2ubah}(h]jah]hwah]h]h] refdomainh|reftypeh~ reftargetj2refwarnsupport_smartquotesuhh^h!jhKh j2hhubh/ with the
keyword }(h with the
keyword h j2hhh!NhNubj)}(h
``mmRayTest``h]h/ mmRayTest}(hhh j2ubah}(h]h]h]h]h]uhjh j2ubh/ and point testing }(h and point testing h j2hhh!NhNubh_)}(hjohnson_fast_2013h]he)}(hj2h]h/[johnson_fast_2013]}(hhh j2ubah}(h]h]h]h]h]uhhdh j2ubah}(h]jah]hwah]h]h] refdomainh|reftypeh~ reftargetj2refwarnsupport_smartquotesuhh^h!jhKh j2hhubh/ with the keyword }(h with the keyword h j2hhh!NhNubj)}(h``mmPointTest``h]h/mmPointTest}(hhh j3ubah}(h]h]h]h]h]uhjh j2ubh/.}(hjh j2hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh j02hhubj)}(hhh](h))}(hMacromaterial block inputh]h/Macromaterial block input}(hj3h j3ubah}(h]h]h]h]h]uhh(h!jhKh j3ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]j.Kduhj#h j+3ubj0)}(hhh]j5)}(hhh]j:)}(hhh]j)}(h.. image:: figs/DEVC/tab6.pngh]h}(h]h]h]h]h]urifigs/DEVC/tab6.pngj}jjK3suhjh j=3h!jhKubah}(h]h]h]h]h]uhj9h j:3ubah}(h]h]h]h]h]uhj4h j73ubah}(h]h]h]h]h]uhj/h j+3ubeh}(h]h]h]h]h]colsKuhjh j3ubeh}(h] tab2-4a-6ah]h] tab2-4a-6ah]h]jcenteruhjh j02hhh!NhNubh$)}(hhh](h))}(hRay tracingh]h/Ray tracing}(hjt3h jr3hhh!NhNubah}(h]h]h]h]h]uhh(h jo3hhh!jhKubh;)}(hXThis method estimates the volume of different materials in the Denovo
mesh grid elements by throwing rays through the KENO-VI geometry and
computing the average track lengths through the each material. Rays are
traced in all three dimensions to better estimate the volume fractions
of materials within each voxel. The ``mmSubCell`` parameter controls how
many rays to trace in each voxel in each dimension. For example, if
``mmSubCell=``\ :math:`\text{\ n}`, then when tracing rays in the
*z* dimension, each column of voxels uses a set of :math:`n \times n`
rays starting uniformly spaced in the *x* and *y* dimensions. With rays
being cast from all three orthogonal directions, then a total of
:math:`3n^{2}` rays are used to sample each voxel. One can think of
subcells as an equally spaced sub-mesh with a single ray positioned at
each center. The number of subcells in each direction, and hence the
number of rays, can be explicitly given with ``mmSubCells ny nz nx nz nx
ny end`` keyword for rays parallel to the :math:`x` axis, :math:`y` axis,
and :math:`z` axis. :numref:`fig2-4a-1` shows different subcell
configurations (in two dimensions) for a given voxel.h](h/X>This method estimates the volume of different materials in the Denovo
mesh grid elements by throwing rays through the KENO-VI geometry and
computing the average track lengths through the each material. Rays are
traced in all three dimensions to better estimate the volume fractions
of materials within each voxel. The }(hX>This method estimates the volume of different materials in the Denovo
mesh grid elements by throwing rays through the KENO-VI geometry and
computing the average track lengths through the each material. Rays are
traced in all three dimensions to better estimate the volume fractions
of materials within each voxel. The h j3hhh!NhNubj)}(h
``mmSubCell``h]h/ mmSubCell}(hhh j3ubah}(h]h]h]h]h]uhjh j3ubh/\ parameter controls how
many rays to trace in each voxel in each dimension. For example, if
}(h\ parameter controls how
many rays to trace in each voxel in each dimension. For example, if
h j3hhh!NhNubj)}(h``mmSubCell=``h]h/
mmSubCell=}(hhh j3ubah}(h]h]h]h]h]uhjh j3ubh/ }(h\ h j3hhh!NhNubj)}(h:math:`\text{\ n}`h]h/
\text{\ n}}(hhh j3ubah}(h]h]h]h]h]uhjh j3ubh/ , then when tracing rays in the
}(h , then when tracing rays in the
h j3hhh!NhNubh)}(h*z*h]h/z}(hhh j3ubah}(h]h]h]h]h]uhhh j3ubh/1 dimension, each column of voxels uses a set of }(h1 dimension, each column of voxels uses a set of h j3hhh!NhNubj)}(h:math:`n \times n`h]h/
n \times n}(hhh j3ubah}(h]h]h]h]h]uhjh j3ubh/'
rays starting uniformly spaced in the }(h'
rays starting uniformly spaced in the h j3hhh!NhNubh)}(h*x*h]h/x}(hhh j3ubah}(h]h]h]h]h]uhhh j3ubh/ and }(h and h j3hhh!NhNubh)}(h*y*h]h/y}(hhh j3ubah}(h]h]h]h]h]uhhh j3ubh/X dimensions. With rays
being cast from all three orthogonal directions, then a total of
}(hX dimensions. With rays
being cast from all three orthogonal directions, then a total of
h j3hhh!NhNubj)}(h:math:`3n^{2}`h]h/3n^{2}}(hhh j4ubah}(h]h]h]h]h]uhjh j3ubh/ rays are used to sample each voxel. One can think of
subcells as an equally spaced sub-mesh with a single ray positioned at
each center. The number of subcells in each direction, and hence the
number of rays, can be explicitly given with }(h rays are used to sample each voxel. One can think of
subcells as an equally spaced sub-mesh with a single ray positioned at
each center. The number of subcells in each direction, and hence the
number of rays, can be explicitly given with h j3hhh!NhNubj)}(h$``mmSubCells ny nz nx nz nx
ny end``h]h/ mmSubCells ny nz nx nz nx
ny end}(hhh j!4ubah}(h]h]h]h]h]uhjh j3ubh/" keyword for rays parallel to the }(h" keyword for rays parallel to the h j3hhh!NhNubj)}(h :math:`x`h]h/x}(hhh j44ubah}(h]h]h]h]h]uhjh j3ubh/ axis, }(h axis, h j3hhh!NhNubj)}(h :math:`y`h]h/y}(hhh jG4ubah}(h]h]h]h]h]uhjh j3ubh/ axis,
and }(h axis,
and h j3hhh!NhNubj)}(h :math:`z`h]h/z}(hhh jZ4ubah}(h]h]h]h]h]uhjh j3ubh/ axis. }(h axis. h j3hhh!NhNubh_)}(h:numref:`fig2-4a-1`h]j)}(hjo4h]h/ fig2-4a-1}(hhh jq4ubah}(h]h](jstd
std-numrefeh]h]h]uhjh jm4ubah}(h]h]h]h]h]refdocj refdomainj{4reftypenumrefrefexplicitrefwarnj fig2-4a-1uhh^h!jhKh j3ubh/N shows different subcell
configurations (in two dimensions) for a given voxel.}(hN shows different subcell
configurations (in two dimensions) for a given voxel.h j3hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jo3hhubh)}(h.. _fig2-4a-1:h]h}(h]h]h]h]h]h fig2-4a-1uhh
hM(+h jo3hhh!jubj)}(hhh](j)}(h.. figure:: figs/DEVC/fig1.png
:align: center
:width: 500
Ray positions within a voxel with different mmSubCells parameters.
h]h}(h]h]h]h]h]width500urifigs/DEVC/fig1.pngj}jj4suhjh j4h!jhKubj)}(hBRay positions within a voxel with different mmSubCells parameters.h]h/BRay positions within a voxel with different mmSubCells parameters.}(hj4h j4ubah}(h]h]h]h]h]uhjh!jhKh j4ubeh}(h](id105j4eh]h] fig2-4a-1ah]h]jcenteruhjhKh jo3hhh!jj}j4j4sj}j4j4subh;)}(hXRay tracing is a more robust method compared to the simple point testing
method used in previous versions of SCALE/MAVRIC; however, it requires
more memory than point testing. Ray tracing gives more accurate
estimates of volume fractions because track lengths across a voxel give
more information than a series of test points. Ray tracing is also much
faster than point testing because the particle tracking routines are
optimized for quickly determining lists of materials and distance along
a given ray.h]h/XRay tracing is a more robust method compared to the simple point testing
method used in previous versions of SCALE/MAVRIC; however, it requires
more memory than point testing. Ray tracing gives more accurate
estimates of volume fractions because track lengths across a voxel give
more information than a series of test points. Ray tracing is also much
faster than point testing because the particle tracking routines are
optimized for quickly determining lists of materials and distance along
a given ray.}(hj4h j4hhh!NhNubah}(h]h]h]h]h]uhh:h!jhKh jo3hhubh;)}(hXRay tracing operates on the grid geometry supplied by the user and
shoots rays in all three directions starting from the lower bounds of
the mesh grid. An example of arbitrary assembly geometry is shown in
:numref:`fig2-4a-2`. A ray consists of a number of steps that corresponds to
crossing a different material along the path of the ray. Ratios of each
step’s length to the voxel length in the ray’s direction determine the
material volume fraction of that step in that voxel, and summation of
the same material volume fractions gives the material volume fraction of
that material in that voxel. Ray tracing through a single voxel that
contains a fuel pin is illustrated in :numref:`fig2-4a-3`.h](h/Ray tracing operates on the grid geometry supplied by the user and
shoots rays in all three directions starting from the lower bounds of
the mesh grid. An example of arbitrary assembly geometry is shown in
}(hRay tracing operates on the grid geometry supplied by the user and
shoots rays in all three directions starting from the lower bounds of
the mesh grid. An example of arbitrary assembly geometry is shown in
h j4hhh!NhNubh_)}(h:numref:`fig2-4a-2`h]j)}(hj4h]h/ fig2-4a-2}(hhh j4ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j4ubah}(h]h]h]h]h]refdocj refdomainj4reftypenumrefrefexplicitrefwarnj fig2-4a-2uhh^h!jhKh j4ubh/X. A ray consists of a number of steps that corresponds to
crossing a different material along the path of the ray. Ratios of each
step’s length to the voxel length in the ray’s direction determine the
material volume fraction of that step in that voxel, and summation of
the same material volume fractions gives the material volume fraction of
that material in that voxel. Ray tracing through a single voxel that
contains a fuel pin is illustrated in }(hX. A ray consists of a number of steps that corresponds to
crossing a different material along the path of the ray. Ratios of each
step’s length to the voxel length in the ray’s direction determine the
material volume fraction of that step in that voxel, and summation of
the same material volume fractions gives the material volume fraction of
that material in that voxel. Ray tracing through a single voxel that
contains a fuel pin is illustrated in h j4hhh!NhNubh_)}(h:numref:`fig2-4a-3`h]j)}(hj5h]h/ fig2-4a-3}(hhh j5ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j
5ubah}(h]h]h]h]h]refdocj refdomainj5reftypenumrefrefexplicitrefwarnj fig2-4a-3uhh^h!jhKh j4ubh/.}(hjh j4hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jo3hhubh)}(h.. _fig2-4a-2:h]h}(h]h]h]h]h]h fig2-4a-2uhh
hME+h jo3hhh!jubj)}(hhh](j)}(h.. figure:: figs/DEVC/fig2.png
:align: center
:width: 600
Geometry model (left) and the Denovo representation (right) of an assembly using macromaterials determined by ray tracing.
h]h}(h]h]h]h]h]width600urifigs/DEVC/fig2.pngj}jjO5suhjh j?5h!jhMubj)}(hzGeometry model (left) and the Denovo representation (right) of an assembly using macromaterials determined by ray tracing.h]h/zGeometry model (left) and the Denovo representation (right) of an assembly using macromaterials determined by ray tracing.}(hjS5h jQ5ubah}(h]h]h]h]h]uhjh!jhMh j?5ubeh}(h](id106j>5eh]h] fig2-4a-2ah]h]jcenteruhjhMh jo3hhh!jj}jd5j45sj}j>5j45subh;)}(hXThe final constructed macromaterials for this model are also shown in
:numref:`fig2-4a-2`. Voxels that contain only a single material are assigned
that original material number in the constructed macromaterials. For the
voxels that contain a fuel pin with three different materials, the
result is a new macromaterial consisting of the volume weighted
fractions of each original material.h](h/FThe final constructed macromaterials for this model are also shown in
}(hFThe final constructed macromaterials for this model are also shown in
h jj5hhh!NhNubh_)}(h:numref:`fig2-4a-2`h]j)}(hju5h]h/ fig2-4a-2}(hhh jw5ubah}(h]h](jstd
std-numrefeh]h]h]uhjh js5ubah}(h]h]h]h]h]refdocj refdomainj5reftypenumrefrefexplicitrefwarnj fig2-4a-2uhh^h!jhMh jj5ubh/X*. Voxels that contain only a single material are assigned
that original material number in the constructed macromaterials. For the
voxels that contain a fuel pin with three different materials, the
result is a new macromaterial consisting of the volume weighted
fractions of each original material.}(hX*. Voxels that contain only a single material are assigned
that original material number in the constructed macromaterials. For the
voxels that contain a fuel pin with three different materials, the
result is a new macromaterial consisting of the volume weighted
fractions of each original material.h jj5hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jo3hhubh;)}(hXAfter the rays are shot in all three directions, the material volume
fractions are updated and macromaterials are created by using these
material volume fractions. Material volume fraction calculations for a
single voxel, as shown in :numref:`fig2-4a-3`, are given byh](h/After the rays are shot in all three directions, the material volume
fractions are updated and macromaterials are created by using these
material volume fractions. Material volume fraction calculations for a
single voxel, as shown in }(hAfter the rays are shot in all three directions, the material volume
fractions are updated and macromaterials are created by using these
material volume fractions. Material volume fraction calculations for a
single voxel, as shown in h j5hhh!NhNubh_)}(h:numref:`fig2-4a-3`h]j)}(hj5h]h/ fig2-4a-3}(hhh j5ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j5ubah}(h]h]h]h]h]refdocj refdomainj5reftypenumrefrefexplicitrefwarnj fig2-4a-3uhh^h!jhMh j5ubh/, are given by}(h, are given byh j5hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jo3hhubh
math_block)}(hX1F_{m} = \ \sum_{d = x,y,z}^{}{\sum_{r = 1}^{N_{r}}{\sum_{s = 1}^{N_{s}}\left\{ \begin{matrix}
\frac{L_{d,r,s}}{L_{d}},\ \ \ & m_{s} = = m \\
0,\ \ \ & \mathrm{\text{otherwise}} \\
\end{matrix} \right.\ }} \ \ \ \ \ \ \mathrm{\text{ and }} \ \ \ \ \ \ \ V_{m} = \frac{F_{m}}{\sum_{n = 1}^{N_{m}}F_{n}}\ ,h]h/X1F_{m} = \ \sum_{d = x,y,z}^{}{\sum_{r = 1}^{N_{r}}{\sum_{s = 1}^{N_{s}}\left\{ \begin{matrix}
\frac{L_{d,r,s}}{L_{d}},\ \ \ & m_{s} = = m \\
0,\ \ \ & \mathrm{\text{otherwise}} \\
\end{matrix} \right.\ }} \ \ \ \ \ \ \mathrm{\text{ and }} \ \ \ \ \ \ \ V_{m} = \frac{F_{m}}{\sum_{n = 1}^{N_{m}}F_{n}}\ ,}(hhh j5ubah}(h]h]h]h]h]docnamejnumberNlabelNnowrapjjuhj5h!jhMh jo3hhubh;)}(hDwhere *F*\ :sub:`m` = sampled fraction of material *m* in the voxel,h](h/where }(hwhere h j5hhh!NhNubh)}(h*F*h]h/F}(hhh j5ubah}(h]h]h]h]h]uhhh j5ubh/ }(h\ h j5hhh!NhNubj)}(h:sub:`m`h]h/m}(hhh j6ubah}(h]h]h]h]h]uhjh j5ubh/ = sampled fraction of material }(h = sampled fraction of material h j5hhh!NhNubh)}(h*m*h]h/m}(hhh j6ubah}(h]h]h]h]h]uhhh j5ubh/ in the voxel,}(h in the voxel,h j5hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM&h jo3hhubh;)}(h,*d* = direction of the rays (*x*, *y*, *z*),h](h)}(h*d*h]h/d}(hhh j26ubah}(h]h]h]h]h]uhhh j.6ubh/ = direction of the rays (}(h = direction of the rays (h j.6hhh!NhNubh)}(h*x*h]h/x}(hhh jE6ubah}(h]h]h]h]h]uhhh j.6ubh/, }(h, h j.6hhh!NhNubh)}(h*y*h]h/y}(hhh jX6ubah}(h]h]h]h]h]uhhh j.6ubh/, }(hjW6h j.6ubh)}(h*z*h]h/z}(hhh jj6ubah}(h]h]h]h]h]uhhh j.6ubh/),}(h),h j.6hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM(h jo3hhubh;)}(h*r* = ray number,h](h)}(h*r*h]h/r}(hhh j6ubah}(h]h]h]h]h]uhhh j6ubh/ = ray number,}(h = ray number,h j6hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM*h jo3hhubh;)}(hG*N*\ :sub:`r` = total number of rays in the voxel for direction of *d,*h](h)}(h*N*h]h/N}(hhh j6ubah}(h]h]h]h]h]uhhh j6ubh/ }(h\ h j6hhh!NhNubj)}(h:sub:`r`h]h/r}(hhh j6ubah}(h]h]h]h]h]uhjh j6ubh/6 = total number of rays in the voxel for direction of }(h6 = total number of rays in the voxel for direction of h j6hhh!NhNubh)}(h*d,*h]h/d,}(hhh j6ubah}(h]h]h]h]h]uhhh j6ubeh}(h]h]h]h]h]uhh:h!jhM,h jo3hhubh;)}(h*s* = step number,h](h)}(h*s*h]h/s}(hhh j6ubah}(h]h]h]h]h]uhhh j6ubh/ = step number,}(h = step number,h j6hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM.h jo3hhubh;)}(hT*N*\ :sub:`s` = total number of steps for ray *r* in the voxel for direction of
*d,*h](h)}(h*N*h]h/N}(hhh j6ubah}(h]h]h]h]h]uhhh j6ubh/ }(h\ h j6hhh!NhNubj)}(h:sub:`s`h]h/s}(hhh j7ubah}(h]h]h]h]h]uhjh j6ubh/! = total number of steps for ray }(h! = total number of steps for ray h j6hhh!NhNubh)}(h*r*h]h/r}(hhh j%7ubah}(h]h]h]h]h]uhhh j6ubh/ in the voxel for direction of
}(h in the voxel for direction of
h j6hhh!NhNubh)}(h*d,*h]h/d,}(hhh j87ubah}(h]h]h]h]h]uhhh j6ubeh}(h]h]h]h]h]uhh:h!jhM0h jo3hhubh;)}(hZ*L*\ :sub:`d,r,s` = length of the steps *s* for ray *r* in the voxel for
direction of *d,*h](h)}(h*L*h]h/L}(hhh jP7ubah}(h]h]h]h]h]uhhh jL7ubh/ }(h\ h jL7hhh!NhNubj)}(h:sub:`d,r,s`h]h/d,r,s}(hhh jc7ubah}(h]h]h]h]h]uhjh jL7ubh/ = length of the steps }(h = length of the steps h jL7hhh!NhNubh)}(h*s*h]h/s}(hhh jv7ubah}(h]h]h]h]h]uhhh jL7ubh/ for ray }(h for ray h jL7hhh!NhNubh)}(h*r*h]h/r}(hhh j7ubah}(h]h]h]h]h]uhhh jL7ubh/ in the voxel for
direction of }(h in the voxel for
direction of h jL7hhh!NhNubh)}(h*d,*h]h/d,}(hhh j7ubah}(h]h]h]h]h]uhhh jL7ubeh}(h]h]h]h]h]uhh:h!jhM3h jo3hhubh;)}(h<*L*\ :sub:`d,` = length of the voxel along direction of *d,*h](h)}(h*L*h]h/L}(hhh j7ubah}(h]h]h]h]h]uhhh j7ubh/ }(h\ h j7hhh!NhNubj)}(h :sub:`d,`h]h/d,}(hhh j7ubah}(h]h]h]h]h]uhjh j7ubh/* = length of the voxel along direction of }(h* = length of the voxel along direction of h j7hhh!NhNubh)}(h*d,*h]h/d,}(hhh j7ubah}(h]h]h]h]h]uhhh j7ubeh}(h]h]h]h]h]uhh:h!jhM6h jo3hhubh;)}(h%*m*\ :sub:`s` = material of step *s,*h](h)}(h*m*h]h/m}(hhh j7ubah}(h]h]h]h]h]uhhh j7ubh/ }(h\ h j7hhh!NhNubj)}(h:sub:`s`h]h/s}(hhh j8ubah}(h]h]h]h]h]uhjh j7ubh/ = material of step }(h = material of step h j7hhh!NhNubh)}(h*s,*h]h/s,}(hhh j8ubah}(h]h]h]h]h]uhhh j7ubeh}(h]h]h]h]h]uhh:h!jhM8h jo3hhubh;)}(h*m* = material number,h](h)}(h*m*h]h/m}(hhh j08ubah}(h]h]h]h]h]uhhh j,8ubh/ = material number,}(h = material number,h j,8hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM:h jo3hhubh;)}(h;*N*\ :sub:`m` = total number of materials in the voxel, andh](h)}(h*N*h]h/N}(hhh jM8ubah}(h]h]h]h]h]uhhh jI8ubh/ }(h\ h jI8hhh!NhNubj)}(h:sub:`m`h]h/m}(hhh j`8ubah}(h]h]h]h]h]uhjh jI8ubh/. = total number of materials in the voxel, and}(h. = total number of materials in the voxel, andh jI8hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM<h jo3hhubh;)}(h=*V*\ :sub:`m` = volume fraction of material *m* in the voxel.h](h)}(h*V*h]h/V}(hhh j}8ubah}(h]h]h]h]h]uhhh jy8ubh/ }(h\ h jy8hhh!NhNubj)}(h:sub:`m`h]h/m}(hhh j8ubah}(h]h]h]h]h]uhjh jy8ubh/ = volume fraction of material }(h = volume fraction of material h jy8hhh!NhNubh)}(h*m*h]h/m}(hhh j8ubah}(h]h]h]h]h]uhhh jy8ubh/ in the voxel.}(h in the voxel.h jy8hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM>h jo3hhubh)}(h.. _fig2-4a-3:h]h}(h]h]h]h]h]h fig2-4a-3uhh
hM|+h jo3hhh!jubj)}(hhh](j)}(hr.. figure:: figs/DEVC/fig3.png
:align: center
:width: 400
Ray tracing (in two dimensions) through a voxel.
h]h}(h]h]h]h]h]width400urifigs/DEVC/fig3.pngj}jj8suhjh j8h!jhMEubj)}(h0Ray tracing (in two dimensions) through a voxel.h]h/0Ray tracing (in two dimensions) through a voxel.}(hj8h j8ubah}(h]h]h]h]h]uhjh!jhMEh j8ubeh}(h](id107j8eh]h] fig2-4a-3ah]h]jcenteruhjhMEh jo3hhh!jj}j8j8sj}j8j8subeh}(h]ray-tracingah]h]ray tracingah]h]uhh#h j02hhh!jhKubh$)}(hhh](h))}(h
Point testingh]h/
Point testing}(hj8h j8hhh!NhNubah}(h]h]h]h]h]uhh(h j8hhh!jhMHubh;)}(hXThe recursive bisection method uses a series of point tests to determine
the macromaterial fractions. For a given voxel, the material at the
center is compared to the material at the eight corners. If they are all
the same, the entire volume is considered to be made of that material.
If different, the volume is divided into two in each dimension. Each
subvolume is tested, and the method is then applied to the subvolumes
that are not of a single material. When the ratio of the volume of the
tested region to the original voxel becomes less than a user-specified
tolerance (in the range of 10\ :sup:`-1` to 10\ :sup:`-4`), then further
subdivision and testing are stopped. This is illustrated in
:numref:`fig2-4a-4`.h](h/XUThe recursive bisection method uses a series of point tests to determine
the macromaterial fractions. For a given voxel, the material at the
center is compared to the material at the eight corners. If they are all
the same, the entire volume is considered to be made of that material.
If different, the volume is divided into two in each dimension. Each
subvolume is tested, and the method is then applied to the subvolumes
that are not of a single material. When the ratio of the volume of the
tested region to the original voxel becomes less than a user-specified
tolerance (in the range of 10 }(hXUThe recursive bisection method uses a series of point tests to determine
the macromaterial fractions. For a given voxel, the material at the
center is compared to the material at the eight corners. If they are all
the same, the entire volume is considered to be made of that material.
If different, the volume is divided into two in each dimension. Each
subvolume is tested, and the method is then applied to the subvolumes
that are not of a single material. When the ratio of the volume of the
tested region to the original voxel becomes less than a user-specified
tolerance (in the range of 10\ h j9hhh!NhNubj)}(h :sup:`-1`h]h/-1}(hhh j9ubah}(h]h]h]h]h]uhjh j9ubh/ to 10 }(h to 10\ h j9hhh!NhNubj)}(h :sup:`-4`h]h/-4}(hhh j'9ubah}(h]h]h]h]h]uhjh j9ubh/L), then further
subdivision and testing are stopped. This is illustrated in
}(hL), then further
subdivision and testing are stopped. This is illustrated in
h j9hhh!NhNubh_)}(h:numref:`fig2-4a-4`h]j)}(hj<9h]h/ fig2-4a-4}(hhh j>9ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j:9ubah}(h]h]h]h]h]refdocj refdomainjH9reftypenumrefrefexplicitrefwarnj fig2-4a-4uhh^h!jhMJh j9ubh/.}(hjh j9hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMJh j8hhubh)}(h.. _fig2-4a-4:h]h}(h]h]h]h]h]h fig2-4a-4uhh
hM+h j8hhh!jubj)}(hhh](j)}(h.. figure:: figs/DEVC/fig4.png
:align: center
:width: 600
Progression of the recursive bisection method (from upper left to lower right).
h]h}(h]h]h]h]h]width600urifigs/DEVC/fig4.pngj}jj9suhjh jo9h!jhM[ubj)}(hOProgression of the recursive bisection method (from upper left to lower right).h]h/OProgression of the recursive bisection method (from upper left to lower right).}(hj9h j9ubah}(h]h]h]h]h]uhjh!jhM[h jo9ubeh}(h](id108jn9eh]h] fig2-4a-4ah]h]jcenteruhjhM[h j8hhh!jj}j9jd9sj}jn9jd9subh;)}(hX'In point testing, the keyword “``mmTolerance=``\ *f*\ ” is interpreted to be
where *f* is the smallest fraction of the voxel volume to consider. This
same tolerance *f* is also used to limit the number of macromaterials.
Before a new macromaterial is created, if one already exists where the
fraction of each actual material matches to within the given tolerance,
then the existing material will be used. If using only a single point at
the center of each voxel, use ``“mmTolerance=1”``. The ``mmSubCell`` keyword is
not used in point testing.h](h/!In point testing, the keyword “}(h!In point testing, the keyword “h j9hhh!NhNubj)}(h``mmTolerance=``h]h/mmTolerance=}(hhh j9ubah}(h]h]h]h]h]uhjh j9ubh/ }(h\ h j9hhh!NhNubh)}(h*f*h]h/f}(hhh j9ubah}(h]h]h]h]h]uhhh j9ubh/! ” is interpreted to be
where }(h!\ ” is interpreted to be
where h j9hhh!NhNubh)}(h*f*h]h/f}(hhh j9ubah}(h]h]h]h]h]uhhh j9ubh/O is the smallest fraction of the voxel volume to consider. This
same tolerance }(hO is the smallest fraction of the voxel volume to consider. This
same tolerance h j9hhh!NhNubh)}(h*f*h]h/f}(hhh j9ubah}(h]h]h]h]h]uhhh j9ubh/X+ is also used to limit the number of macromaterials.
Before a new macromaterial is created, if one already exists where the
fraction of each actual material matches to within the given tolerance,
then the existing material will be used. If using only a single point at
the center of each voxel, use }(hX+ is also used to limit the number of macromaterials.
Before a new macromaterial is created, if one already exists where the
fraction of each actual material matches to within the given tolerance,
then the existing material will be used. If using only a single point at
the center of each voxel, use h j9hhh!NhNubj)}(h``“mmTolerance=1”``h]h/“mmTolerance=1”}(hhh j9ubah}(h]h]h]h]h]uhjh j9ubh/. The }(h. The h j9hhh!NhNubj)}(h
``mmSubCell``h]h/ mmSubCell}(hhh j:ubah}(h]h]h]h]h]uhjh j9ubh/& keyword is
not used in point testing.}(h& keyword is
not used in point testing.h j9hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhM]h j8hhubeh}(h]
point-testingah]h]
point testingah]h]uhh#h j02hhh!jhMHubh$)}(hhh](h))}(hExampleh]h/Example}(hj(:h j&:hhh!NhNubah}(h]h]h]h]h]uhh(h j#:hhh!jhMgubh;)}(hX:numref:`fig2-4a-5` shows an example of a cask geometry with two types of
spent fuel (yellows), steel (blue), resin (green), and other metals
(gray). When the Denovo geometry is set up by testing only the center of
each mesh cell, the curved surfaces are not well represented (upper
right). By applying the ray-tracing method and defining a new material
made of partial fractions of the original materials, an improved Denovo
model can be made. In the lower left of the figure, the Denovo model was
constructed using one ray (in each dimension) per voxel and a tolerance
of 0.1. This gives 20 new materials that are a mixture of the original
13 actual materials and void. With ``mmSubCells=3`` and an ``mmTolerance=0.01``,
139 macromaterials are created.h](h_)}(h:numref:`fig2-4a-5`h]j)}(hj::h]h/ fig2-4a-5}(hhh j<:ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j8:ubah}(h]h]h]h]h]refdocj refdomainjF:reftypenumrefrefexplicitrefwarnj fig2-4a-5uhh^h!jhMih j4:ubh/X shows an example of a cask geometry with two types of
spent fuel (yellows), steel (blue), resin (green), and other metals
(gray). When the Denovo geometry is set up by testing only the center of
each mesh cell, the curved surfaces are not well represented (upper
right). By applying the ray-tracing method and defining a new material
made of partial fractions of the original materials, an improved Denovo
model can be made. In the lower left of the figure, the Denovo model was
constructed using one ray (in each dimension) per voxel and a tolerance
of 0.1. This gives 20 new materials that are a mixture of the original
13 actual materials and void. With }(hX shows an example of a cask geometry with two types of
spent fuel (yellows), steel (blue), resin (green), and other metals
(gray). When the Denovo geometry is set up by testing only the center of
each mesh cell, the curved surfaces are not well represented (upper
right). By applying the ray-tracing method and defining a new material
made of partial fractions of the original materials, an improved Denovo
model can be made. In the lower left of the figure, the Denovo model was
constructed using one ray (in each dimension) per voxel and a tolerance
of 0.1. This gives 20 new materials that are a mixture of the original
13 actual materials and void. With h j4:hhh!NhNubj)}(h``mmSubCells=3``h]h/mmSubCells=3}(hhh j]:ubah}(h]h]h]h]h]uhjh j4:ubh/ and an }(h and an h j4:hhh!NhNubj)}(h``mmTolerance=0.01``h]h/mmTolerance=0.01}(hhh jp:ubah}(h]h]h]h]h]uhjh j4:ubh/",
139 macromaterials are created.}(h",
139 macromaterials are created.h j4:hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMih j#:hhubh;)}(hXA macromaterial table listing the fractions of each macromaterial is
saved to a file called “\ *outputName*.mmt”, where *outputName* is the
name the user chose for his or her output file. This file can be used by
the Mesh File Viewer to display the macromaterials as mixtures of the
actual materials, as seen in lower row of :numref:`fig2-4a-5`. See the Mesh
File Viewer help pages for more information on how to use colormap files
and macromaterial tables.h](h/aA macromaterial table listing the fractions of each macromaterial is
saved to a file called “ }(haA macromaterial table listing the fractions of each macromaterial is
saved to a file called “\ h j:hhh!NhNubh)}(h*outputName*h]h/
outputName}(hhh j:ubah}(h]h]h]h]h]uhhh j:ubh/.mmt”, where }(h.mmt”, where h j:hhh!NhNubh)}(h*outputName*h]h/
outputName}(hhh j:ubah}(h]h]h]h]h]uhhh j:ubh/ is the
name the user chose for his or her output file. This file can be used by
the Mesh File Viewer to display the macromaterials as mixtures of the
actual materials, as seen in lower row of }(h is the
name the user chose for his or her output file. This file can be used by
the Mesh File Viewer to display the macromaterials as mixtures of the
actual materials, as seen in lower row of h j:hhh!NhNubh_)}(h:numref:`fig2-4a-5`h]j)}(hj:h]h/ fig2-4a-5}(hhh j:ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j:ubah}(h]h]h]h]h]refdocj refdomainj:reftypenumrefrefexplicitrefwarnj fig2-4a-5uhh^h!jhMuh j:ubh/q. See the Mesh
File Viewer help pages for more information on how to use colormap files
and macromaterial tables.}(hq. See the Mesh
File Viewer help pages for more information on how to use colormap files
and macromaterial tables.h j:hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMuh j#:hhubh)}(h.. _fig2-4a-5:h]h}(h]h]h]h]h]h fig2-4a-5uhh
hM+h j#:hhh!jubj)}(hhh](j)}(hXO.. figure:: figs/DEVC/fig5.png
:align: center
:width: 600
Cask geometry model (upper left) and the Denovo representation using (upper right) cell center testing. Representations using macromaterials determined by ray tracing are shown for (lower left) mmSubCell=1/mmTolerance=0.1 and (lower right) mmSubCell=3/mmTolerance=0.01.
h]h}(h]h]h]h]h]width600urifigs/DEVC/fig5.pngj}jj:suhjh j:h!jhMubj)}(hX
Cask geometry model (upper left) and the Denovo representation using (upper right) cell center testing. Representations using macromaterials determined by ray tracing are shown for (lower left) mmSubCell=1/mmTolerance=0.1 and (lower right) mmSubCell=3/mmTolerance=0.01.h]h/X
Cask geometry model (upper left) and the Denovo representation using (upper right) cell center testing. Representations using macromaterials determined by ray tracing are shown for (lower left) mmSubCell=1/mmTolerance=0.1 and (lower right) mmSubCell=3/mmTolerance=0.01.}(hj;h j;ubah}(h]h]h]h]h]uhjh!jhMh j:ubeh}(h](id109j:eh]h] fig2-4a-5ah]h]jcenteruhjhMh j#:hhh!jj}j;j:sj}j:j:subeh}(h]exampleah]h]exampleah]h]uhh#h j02hhh!jhMgubeh}(h]macromaterial-blockah]h]macromaterial blockah]h]uhh#h j-hhh!jhKubh$)}(hhh](h))}(hStarting sources blockh]h/Starting sources block}(hj.;h j,;hhh!NhNubah}(h]h]h]h]h]uhh(h j);hhh!jhMubh;)}(hXYThe default KENO-VI starting source is “flat over the volume specified
by the unrotated, untranslated geometry record specified in the first
position of the global unit boundary record in fissile material only”.
For DEVC, the default starting source strength is uniform in the fissile
voxels contained within the bounding box of the global unit (uniform
density). If macromaterials are used, the amounts in each voxel are
volume averaged between fissile and non-fissile materials. :numref:`tab2-4a-7`
and :numref:`tab2-4a-8` describe the starting sources available in the DEVC
interface to Denovo.h](h/XThe default KENO-VI starting source is “flat over the volume specified
by the unrotated, untranslated geometry record specified in the first
position of the global unit boundary record in fissile material only”.
For DEVC, the default starting source strength is uniform in the fissile
voxels contained within the bounding box of the global unit (uniform
density). If macromaterials are used, the amounts in each voxel are
volume averaged between fissile and non-fissile materials. }(hXThe default KENO-VI starting source is “flat over the volume specified
by the unrotated, untranslated geometry record specified in the first
position of the global unit boundary record in fissile material only”.
For DEVC, the default starting source strength is uniform in the fissile
voxels contained within the bounding box of the global unit (uniform
density). If macromaterials are used, the amounts in each voxel are
volume averaged between fissile and non-fissile materials. h j:;hhh!NhNubh_)}(h:numref:`tab2-4a-7`h]j)}(hjE;h]h/ tab2-4a-7}(hhh jG;ubah}(h]h](jstd
std-numrefeh]h]h]uhjh jC;ubah}(h]h]h]h]h]refdocj refdomainjQ;reftypenumrefrefexplicitrefwarnj tab2-4a-7uhh^h!jhMh j:;ubh/
and }(h
and h j:;hhh!NhNubh_)}(h:numref:`tab2-4a-8`h]j)}(hjj;h]h/ tab2-4a-8}(hhh jl;ubah}(h]h](jstd
std-numrefeh]h]h]uhjh jh;ubah}(h]h]h]h]h]refdocj refdomainjv;reftypenumrefrefexplicitrefwarnj tab2-4a-8uhh^h!jhMh j:;ubh/I describe the starting sources available in the DEVC
interface to Denovo.}(hI describe the starting sources available in the DEVC
interface to Denovo.h j:;hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh j);hhubh)}(h.. _tab2-4a-7:h]h}(h]h]h]h]h]h tab2-4a-7uhh
hM+h j);hhh!jubj)}(hhh](h))}(hDStarting source types (within the fissile areas of the listed shape)h]h/DStarting source types (within the fissile areas of the listed shape)}(hj;h j;ubah}(h]h]h]h]h]uhh(h!jhMh j;ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j;ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j;ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j;ubjs)}(hhh]j5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j;ubj:)}(hhh]h;)}(hKENO-VI start typeh]h/KENO-VI start type}(hj;h j;ubah}(h]h]h]h]h]uhh:h!jhMh j;ubah}(h]h]h]h]h]uhj9h j;ubj:)}(hhh]h;)}(hDEVCh]h/DEVC}(hj;h j;ubah}(h]h]h]h]h]uhh:h!jhMh j;ubah}(h]h]h]h]h]uhj9h j;ubeh}(h]h]h]h]h]uhj4h j;ubah}(h]h]h]h]h]uhjrh j;ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hnst=0h]h/nst=0}(hj$<h j"<ubah}(h]h]h]h]h]uhh:h!jhMh j<ubah}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(h'the first surface of
boundary (default)h]h/'the first surface of
boundary (default)}(hj;<h j9<ubah}(h]h]h]h]h]uhh:h!jhMh j6<ubah}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(hThe bounding box of
global unith]h/The bounding box of
global unit}(hjR<h jP<ubah}(h]h]h]h]h]uhh:h!jhMh jM<ubah}(h]h]h]h]h]uhj9h j<ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=0h]h/nst=0}(hjr<h jp<ubah}(h]h]h]h]h]uhh:h!jhMh jm<ubah}(h]h]h]h]h]uhj9h jj<ubj:)}(hhh]h;)}(hCWithin boundary of
global array having a
reflector key set to
falseh]h/CWithin boundary of
global array having a
reflector key set to
false}(hj<h j<ubah}(h]h]h]h]h]uhh:h!jhMh j<ubah}(h]h]h]h]h]uhj9h jj<ubj:)}(hhh]h;)}(h
Not supportedh]h/
Not supported}(hj<h j<ubah}(h]h]h]h]h]uhh:h!jhMh j<ubah}(h]h]h]h]h]uhj9h jj<ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=0h]h/nst=0}(hj<h j<ubah}(h]h]h]h]h]uhh:h!jhMh j<ubah}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(h4A cuboid defined by
XSM, XSP, YSM, YSP,
ZSM, and ZSPh]h/4A cuboid defined by
XSM, XSP, YSM, YSP,
ZSM, and ZSP}(hj<h j<ubah}(h]h]h]h]h]uhh:h!jhMh j<ubah}(h]h]h]h]h]uhj9h j<ubj:)}(hhh]h;)}(h Supportedh]h/ Supported}(hj<h j<ubah}(h]h]h]h]h]uhh:h!jhMh j<ubah}(h]h]h]h]h]uhj9h j<ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=1h]h/nst=1}(hj=h j=ubah}(h]h]h]h]h]uhh:h!jhMh j =ubah}(h]h]h]h]h]uhj9h j=ubj:)}(hhh]h;)}(hNA cuboid defined by
XSM, XSP, YSM, YSP,
ZSM, and ZSP with
cosine distributionsh]h/NA cuboid defined by
XSM, XSP, YSM, YSP,
ZSM, and ZSP with
cosine distributions}(hj%=h j#=ubah}(h]h]h]h]h]uhh:h!jhMh j =ubah}(h]h]h]h]h]uhj9h j=ubj:)}(hhh]h;)}(h Supportedh]h/ Supported}(hj<=h j:=ubah}(h]h]h]h]h]uhh:h!jhMh j7=ubah}(h]h]h]h]h]uhj9h j=ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=2h]h/nst=2}(hj\=h jZ=ubah}(h]h]h]h]h]uhh:h!jhMh jW=ubah}(h]h]h]h]h]uhj9h jT=ubj:)}(hhh]h;)}(hArbitrary fraction
(FCT) in element NXS,
NYS, NZS of the
global array with the
remainder in a cuboid
defined by XSM, XSP,
YSM, YSP, ZSM, and
ZSP with cosine
distributionsh]h/Arbitrary fraction
(FCT) in element NXS,
NYS, NZS of the
global array with the
remainder in a cuboid
defined by XSM, XSP,
YSM, YSP, ZSM, and
ZSP with cosine
distributions}(hjs=h jq=ubah}(h]h]h]h]h]uhh:h!jhMh jn=ubah}(h]h]h]h]h]uhj9h jT=ubj:)}(hhh]h;)}(h8Supported for some
array types (see
:numref:`tab2-4a-8`)h](h/$Supported for some
array types (see
}(h$Supported for some
array types (see
h j=ubh_)}(h:numref:`tab2-4a-8`h]j)}(hj=h]h/ tab2-4a-8}(hhh j=ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j=ubah}(h]h]h]h]h]refdocj refdomainj=reftypenumrefrefexplicitrefwarnj tab2-4a-8uhh^h!jhMh j=ubh/)}(h)h j=ubeh}(h]h]h]h]h]uhh:h!jhMh j=ubah}(h]h]h]h]h]uhj9h jT=ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=3h]h/nst=3}(hj=h j=ubah}(h]h]h]h]h]uhh:h!jhMh j=ubah}(h]h]h]h]h]uhj9h j=ubj:)}(hhh]h;)}(hNAt the location TFX,
TFY, TFZ in the
element NXS, NYS, NZS
of the global arrayh]h/NAt the location TFX,
TFY, TFZ in the
element NXS, NYS, NZS
of the global array}(hj=h j=ubah}(h]h]h]h]h]uhh:h!jhMh j=ubah}(h]h]h]h]h]uhj9h j=ubj:)}(hhh]h;)}(h8Supported for some
array types (see
:numref:`tab2-4a-8`)h](h/$Supported for some
array types (see
}(h$Supported for some
array types (see
h j=ubh_)}(h:numref:`tab2-4a-8`h]j)}(hj>h]h/ tab2-4a-8}(hhh j >ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j>ubah}(h]h]h]h]h]refdocj refdomainj>reftypenumrefrefexplicitrefwarnj tab2-4a-8uhh^h!jhMh j=ubh/)}(hj=h j=ubeh}(h]h]h]h]h]uhh:h!jhMh j=ubah}(h]h]h]h]h]uhj9h j=ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=4h]h/nst=4}(hjC>h jA>ubah}(h]h]h]h]h]uhh:h!jhMh j>>ubah}(h]h]h]h]h]uhj9h j;>ubj:)}(hhh]h;)}(h>At the location TFX,
TFY, TFZ in units NBX
of the global arrayh]h/>At the location TFX,
TFY, TFZ in units NBX
of the global array}(hjZ>h jX>ubah}(h]h]h]h]h]uhh:h!jhMh jU>ubah}(h]h]h]h]h]uhj9h j;>ubj:)}(hhh]h;)}(h Supportedh]h/ Supported}(hjq>h jo>ubah}(h]h]h]h]h]uhh:h!jhMh jl>ubah}(h]h]h]h]h]uhj9h j;>ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=5h]h/nst=5}(hj>h j>ubah}(h]h]h]h]h]uhh:h!jhMh j>ubah}(h]h]h]h]h]uhj9h j>ubj:)}(hhh]h;)}(h$Across units NBX in
the global arrayh]h/$Across units NBX in
the global array}(hj>h j>ubah}(h]h]h]h]h]uhh:h!jhMh j>ubah}(h]h]h]h]h]uhj9h j>ubj:)}(hhh]h;)}(h
Not supportedh]h/
Not supported}(hj>h j>ubah}(h]h]h]h]h]uhh:h!jhMh j>ubah}(h]h]h]h]h]uhj9h j>ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=6h]h/nst=6}(hj>h j>ubah}(h]h]h]h]h]uhh:h!jhMh j>ubah}(h]h]h]h]h]uhj9h j>ubj:)}(hhh]h;)}(h2List of points TFX,
TFY, TFZ in global
coordinatesh]h/2List of points TFX,
TFY, TFZ in global
coordinates}(hj>h j>ubah}(h]h]h]h]h]uhh:h!jhMh j>ubah}(h]h]h]h]h]uhj9h j>ubj:)}(hhh]h;)}(hLimited to 1 pointh]h/Limited to 1 point}(hj
?h j?ubah}(h]h]h]h]h]uhh:h!jhMh j?ubah}(h]h]h]h]h]uhj9h j>ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=6h]h/nst=6}(hj-?h j+?ubah}(h]h]h]h]h]uhh:h!jhMh j(?ubah}(h]h]h]h]h]uhj9h j%?ubj:)}(hhh]h;)}(hIList of points TFX,
TFY, TFZ in element
NXS, NYS, NZS of the
global arrayh]h/IList of points TFX,
TFY, TFZ in element
NXS, NYS, NZS of the
global array}(hjD?h jB?ubah}(h]h]h]h]h]uhh:h!jhMh j??ubah}(h]h]h]h]h]uhj9h j%?ubj:)}(hhh]h;)}(hJLimited to 1 point
and only for some
array types (see
:numref:`tab2-4a-8`)h](h/6Limited to 1 point
and only for some
array types (see
}(h6Limited to 1 point
and only for some
array types (see
h jY?ubh_)}(h:numref:`tab2-4a-8`h]j)}(hjd?h]h/ tab2-4a-8}(hhh jf?ubah}(h]h](jstd
std-numrefeh]h]h]uhjh jb?ubah}(h]h]h]h]h]refdocj refdomainjp?reftypenumrefrefexplicitrefwarnj tab2-4a-8uhh^h!jhMh jY?ubh/)}(hj=h jY?ubeh}(h]h]h]h]h]uhh:h!jhMh jV?ubah}(h]h]h]h]h]uhj9h j%?ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=7h]h/nst=7}(hj?h j?ubah}(h]h]h]h]h]uhh:h!jhMh j?ubah}(h]h]h]h]h]uhj9h j?ubj:)}(hhh]h;)}(hwFlat distributions in
X and Y with
[1-cos\ :sup:`2`\ (z)]
in Z for a cuboid
defined by XSM, XSP,
YSM, YSP, ZSM, and
ZSPh](h/+Flat distributions in
X and Y with
[1-cos }(h+Flat distributions in
X and Y with
[1-cos\ h j?ubj)}(h:sup:`2`h]h/2}(hhh j?ubah}(h]h]h]h]h]uhjh j?ubh/D (z)]
in Z for a cuboid
defined by XSM, XSP,
YSM, YSP, ZSM, and
ZSP}(hD\ (z)]
in Z for a cuboid
defined by XSM, XSP,
YSM, YSP, ZSM, and
ZSPh j?ubeh}(h]h]h]h]h]uhh:h!jhMh j?ubah}(h]h]h]h]h]uhj9h j?ubj:)}(hhh]h;)}(h Supportedh]h/ Supported}(hj?h j?ubah}(h]h]h]h]h]uhh:h!jhMh j?ubah}(h]h]h]h]h]uhj9h j?ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=8h]h/nst=8}(hj@h j@ubah}(h]h]h]h]h]uhh:h!jhMh j?ubah}(h]h]h]h]h]uhj9h j?ubj:)}(hhh]h;)}(hyFlat distributions in
X and Y with a
segmented
distribution in Z for
a cuboid defined by
XSM, XSP, YSM, YSP,
ZSM, and ZSPh]h/yFlat distributions in
X and Y with a
segmented
distribution in Z for
a cuboid defined by
XSM, XSP, YSM, YSP,
ZSM, and ZSP}(hj@h j@ubah}(h]h]h]h]h]uhh:h!jhMh j@ubah}(h]h]h]h]h]uhj9h j?ubj:)}(hhh]h;)}(h
Not supportedh]h/
Not supported}(hj0@h j.@ubah}(h]h]h]h]h]uhh:h!jhMh j+@ubah}(h]h]h]h]h]uhj9h j?ubeh}(h]h]h]h]h]uhj4h j<ubj5)}(hhh](j:)}(hhh]h;)}(hnst=9h]h/nst=9}(hjP@h jN@ubah}(h]h]h]h]h]uhh:h!jhMh jK@ubah}(h]h]h]h]h]uhj9h jH@ubj:)}(hhh]h;)}(hUse a mesh source
lite fileh]h/Use a mesh source
lite file}(hjg@h je@ubah}(h]h]h]h]h]uhh:h!jhMh jb@ubah}(h]h]h]h]h]uhj9h jH@ubj:)}(hhh]h;)}(h
Not supportedh]h/
Not supported}(hj~@h j|@ubah}(h]h]h]h]h]uhh:h!jhMh jy@ubah}(h]h]h]h]h]uhj9h jH@ubeh}(h]h]h]h]h]uhj4h j<ubeh}(h]h]h]h]h]uhj/h j;ubeh}(h]h]h]h]h]colsKuhjh j;ubeh}(h](id110j;eh]h] tab2-4a-7ah]h]jcenteruhjh j);hhh!jhNj}j@j;sj}j;j;subh)}(h.. _tab2-4a-8:h]h}(h]h]h]h]h]h tab2-4a-8uhh
hM,h j);hhh!jubj)}(hhh](h))}(h*Supported array types for starting sourcesh]h/*Supported array types for starting sources}(hj@h j@ubah}(h]h]h]h]h]uhh(h!jhMh j@ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j@ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j@ubjs)}(hhh]j5)}(hhh](j:)}(hhh]h;)}(h no arraysh]h/ no arrays}(hj@h j@ubah}(h]h]h]h]h]uhh:h!jhMh j@ubah}(h]h]h]h]h]uhj9h j@ubj:)}(hhh]h;)}(h supportedh]h/ supported}(hjAh jAubah}(h]h]h]h]h]uhh:h!jhMh j@ubah}(h]h]h]h]h]uhj9h j@ubeh}(h]h]h]h]h]uhj4h j@ubah}(h]h]h]h]h]uhjrh j@ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hcuboidh]h/cuboid}(hj,Ah j*Aubah}(h]h]h]h]h]uhh:h!jhMh j'Aubah}(h]h]h]h]h]uhj9h j$Aubj:)}(hhh]h;)}(h supportedh]h/ supported}(hjCAh jAAubah}(h]h]h]h]h]uhh:h!jhMh j>Aubah}(h]h]h]h]h]uhj9h j$Aubeh}(h]h]h]h]h]uhj4h j!Aubj5)}(hhh](j:)}(hhh]h;)}(h hexagonalh]h/ hexagonal}(hjcAh jaAubah}(h]h]h]h]h]uhh:h!jhMh j^Aubah}(h]h]h]h]h]uhj9h j[Aubj:)}(hhh]h;)}(h supportedh]h/ supported}(hjzAh jxAubah}(h]h]h]h]h]uhh:h!jhMh juAubah}(h]h]h]h]h]uhj9h j[Aubeh}(h]h]h]h]h]uhj4h j!Aubj5)}(hhh](j:)}(hhh]h;)}(h
shexagonalh]h/
shexagonal}(hjAh jAubah}(h]h]h]h]h]uhh:h!jhMh jAubah}(h]h]h]h]h]uhj9h jAubj:)}(hhh]h;)}(hnoh]h/no}(hjAh jAubah}(h]h]h]h]h]uhh:h!jhMh jAubah}(h]h]h]h]h]uhj9h jAubeh}(h]h]h]h]h]uhj4h j!Aubj5)}(hhh](j:)}(hhh]h;)}(h
rhexagonalh]h/
rhexagonal}(hjAh jAubah}(h]h]h]h]h]uhh:h!jhMh jAubah}(h]h]h]h]h]uhj9h jAubj:)}(hhh]h;)}(hnoh]h/no}(hjAh jAubah}(h]h]h]h]h]uhh:h!jhMh jAubah}(h]h]h]h]h]uhj9h jAubeh}(h]h]h]h]h]uhj4h j!Aubj5)}(hhh](j:)}(hhh]h;)}(hdodecahedralh]h/dodecahedral}(hjBh jBubah}(h]h]h]h]h]uhh:h!jhMh jBubah}(h]h]h]h]h]uhj9h jBubj:)}(hhh]h;)}(hnoh]h/no}(hjBh jBubah}(h]h]h]h]h]uhh:h!jhMh jBubah}(h]h]h]h]h]uhj9h jBubeh}(h]h]h]h]h]uhj4h j!Aubeh}(h]h]h]h]h]uhj/h j@ubeh}(h]h]h]h]h]colsKuhjh j@ubeh}(h](id111j@eh]h] tab2-4a-8ah]h]jcenteruhjh j);hhh!jhNj}jIBj@sj}j@j@subh;)}(hThe starting source initialized in Denovo is always a volumetric source---\
DEVC does not create point sources (which would activate the first
collision option in Denovo).h]h/The starting source initialized in Denovo is always a volumetric source—
DEVC does not create point sources (which would activate the first
collision option in Denovo).}(hThe starting source initialized in Denovo is always a volumetric source---\
DEVC does not create point sources (which would activate the first
collision option in Denovo).h jOBhhh!NhNubah}(h]h]h]h]h]uhh:h!jhMh j);hhubeh}(h]starting-sources-blockah]h]starting sources blockah]h]uhh#h j-hhh!jhMubeh}(h]id57ah]h]h]jah]uhh#h jhhh!jhKdjmKubh$)}(hhh](h))}(hSequence Outputh]h/Sequence Output}(hjrBh jpBhhh!NhNubah}(h]h]h]h]h]uhh(h jmBhhh!jhMubh;)}(hThe main text output file consists of the output from the cross-section
processing codes and Denovo. The user should examine the output and pay
attention to any warnings or errors. :numref:`tab2-4a-9` lists the files
generated during the DEVC sequence.h](h/The main text output file consists of the output from the cross-section
processing codes and Denovo. The user should examine the output and pay
attention to any warnings or errors. }(hThe main text output file consists of the output from the cross-section
processing codes and Denovo. The user should examine the output and pay
attention to any warnings or errors. h j~Bhhh!NhNubh_)}(h:numref:`tab2-4a-9`h]j)}(hjBh]h/ tab2-4a-9}(hhh jBubah}(h]h](jstd
std-numrefeh]h]h]uhjh jBubah}(h]h]h]h]h]refdocj refdomainjBreftypenumrefrefexplicitrefwarnj tab2-4a-9uhh^h!jhMh j~Bubh/4 lists the files
generated during the DEVC sequence.}(h4 lists the files
generated during the DEVC sequence.h j~Bhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMh jmBhhubh)}(h.. _tab2-4a-9:h]h}(h]h]h]h]h]h tab2-4a-9uhh
hM6,h jmBhhh!jubj)}(hhh](h))}(h9Files created by DEVC for an input file named *input*.inph](h/.Files created by DEVC for an input file named }(h.Files created by DEVC for an input file named h jBubh)}(h*input*h]h/input}(hhh jBubah}(h]h]h]h]h]uhhh jBubh/.inp}(h.inph jBubeh}(h]h]h]h]h]uhh(h!jhMh jBubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jBubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jBubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jBubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jBubjs)}(hhh]j5)}(hhh](j:)}(hhh]h;)}(h**Filename**h]hA)}(hjCh]h/Filename}(hhh jCubah}(h]h]h]h]h]uhh@h jCubah}(h]h]h]h]h]uhh:h!jhMh jCubah}(h]h]h]h]h]uhj9h jCubj:)}(hhh]h}(h]h]h]h]h]uhj9h jCubj:)}(hhh]h;)}(h
**Viewer**h]hA)}(hjACh]h/Viewer}(hhh jCCubah}(h]h]h]h]h]uhh@h j?Cubah}(h]h]h]h]h]uhh:h!jhMh jJ}uhjh!jIhMJh jPNubeh}(h] list2-3-1ah]jDJah] list2-3-1ah]h]
literal_blockuhjJh jMhhh!hhNubjJ)}(hhh](j)}(h+STARBUCS input listing for sample problem 2h]h/+STARBUCS input listing for sample problem 2}(hjNh j}Nubah}(h]h]h]h]h]uhjh!jIhMh jzNubj)}(hX=starbucs
PWR 17x17 Fuel Assembly - 18-zone axial burnup profile
v7-238
read comp
' UO2 Fuel 2.0 wt% u-235
uo2 1 den=10.96 0.95 293.0 92235 2.0 92238 98.0 end
'Zircalloy
zirc4 2 1 end
'Water
h2o 3 1 end
'Gap
n 4 den=0.00125 1 end
end comp
read celldata
latticecell squarepitch pitch=1.259 3 fueld=0.805 1 cladd=0.95 2 gapd=0.822 4 end
end celldata
' Enter burnup credit control parameters
read control
arp=w17x17 nax=-18
nuc= u-234 u-235 u-236 u-238 pu-238 pu-240
pu-241 pu-242 am-241 am-242m am-243 np-237 end
fle=o-16 h-1 end
end control
read hist
power=35.001 burn=100 nlib=1 end
power=28.5 burn=230 down=100 nlib=2 end
power=24.001 burn=300 nlib=2 down=1826 end
end hist
read kenova
'**************************************
'* materials
'* 101-118 = uo2, 18-axial zone model
'* 2 = Zircaloy
'* 3 = Water
'* 4 = Gap
'**************************************
read param tme=10000 gen=510 nsk=10 npg=1000 end param
read geom
' Fuel Pin
global unit 1
cylinder 101 1 0.4025 -162.53 -182.85
cylinder 102 1 0.4025 -142.22 -182.85
cylinder 103 1 0.4025 -121.90 -182.85
cylinder 104 1 0.4025 -101.58 -182.85
cylinder 105 1 0.4025 -81.27 -182.85
cylinder 106 1 0.4025 -60.95 -182.85
cylinder 107 1 0.4025 -40.63 -182.85
cylinder 108 1 0.4025 -20.32 -182.85
cylinder 109 1 0.4025 0.00 -182.85
cylinder 110 1 0.4025 20.32 -182.85
cylinder 111 1 0.4025 40.63 -182.85
cylinder 112 1 0.4025 60.95 -182.85
cylinder 113 1 0.4025 81.27 -182.85
cylinder 114 1 0.4025 101.58 -182.85
cylinder 115 1 0.4025 121.90 -182.85
cylinder 116 1 0.4025 142.22 -182.85
cylinder 117 1 0.4025 162.53 -182.85
cylinder 118 1 0.4025 182.85 -182.85
cylinder 4 1 0.4110 182.85 -182.85
cylinder 2 1 0.4750 182.85 -182.85
cuboid 3 1 4p0.6295 182.85 -182.85
'
end geom
read bounds all=reflect end bounds
end data
end kenova
endh]h/X=starbucs
PWR 17x17 Fuel Assembly - 18-zone axial burnup profile
v7-238
read comp
' UO2 Fuel 2.0 wt% u-235
uo2 1 den=10.96 0.95 293.0 92235 2.0 92238 98.0 end
'Zircalloy
zirc4 2 1 end
'Water
h2o 3 1 end
'Gap
n 4 den=0.00125 1 end
end comp
read celldata
latticecell squarepitch pitch=1.259 3 fueld=0.805 1 cladd=0.95 2 gapd=0.822 4 end
end celldata
' Enter burnup credit control parameters
read control
arp=w17x17 nax=-18
nuc= u-234 u-235 u-236 u-238 pu-238 pu-240
pu-241 pu-242 am-241 am-242m am-243 np-237 end
fle=o-16 h-1 end
end control
read hist
power=35.001 burn=100 nlib=1 end
power=28.5 burn=230 down=100 nlib=2 end
power=24.001 burn=300 nlib=2 down=1826 end
end hist
read kenova
'**************************************
'* materials
'* 101-118 = uo2, 18-axial zone model
'* 2 = Zircaloy
'* 3 = Water
'* 4 = Gap
'**************************************
read param tme=10000 gen=510 nsk=10 npg=1000 end param
read geom
' Fuel Pin
global unit 1
cylinder 101 1 0.4025 -162.53 -182.85
cylinder 102 1 0.4025 -142.22 -182.85
cylinder 103 1 0.4025 -121.90 -182.85
cylinder 104 1 0.4025 -101.58 -182.85
cylinder 105 1 0.4025 -81.27 -182.85
cylinder 106 1 0.4025 -60.95 -182.85
cylinder 107 1 0.4025 -40.63 -182.85
cylinder 108 1 0.4025 -20.32 -182.85
cylinder 109 1 0.4025 0.00 -182.85
cylinder 110 1 0.4025 20.32 -182.85
cylinder 111 1 0.4025 40.63 -182.85
cylinder 112 1 0.4025 60.95 -182.85
cylinder 113 1 0.4025 81.27 -182.85
cylinder 114 1 0.4025 101.58 -182.85
cylinder 115 1 0.4025 121.90 -182.85
cylinder 116 1 0.4025 142.22 -182.85
cylinder 117 1 0.4025 162.53 -182.85
cylinder 118 1 0.4025 182.85 -182.85
cylinder 4 1 0.4110 182.85 -182.85
cylinder 2 1 0.4750 182.85 -182.85
cuboid 3 1 4p0.6295 182.85 -182.85
'
end geom
read bounds all=reflect end bounds
end data
end kenova
end}(hhh jNubah}(h]h]h]h]h]jjj;JjJ}uhjh!jIhMh jzNubeh}(h] list2-3-2ah]jDJah] list2-3-2ah]h]
literal_blockuhjJh jMhhh!hhNubeh}(h]sample-problem-2ah]h]sample problem 2ah]h]uhh#h juLhhh!jIhM,ubh$)}(hhh](h))}(hSample problem 3h]h/Sample problem 3}(hjNh jNhhh!NhNubah}(h]h]h]h]h]uhh(h jNhhh!jIhMubh;)}(hXSample problem 3, listed in :numref:`list2-3-3`, performs a burnup-credit
criticality safety calculation using the SCALE 238-group ENDF/B-VII
cross section library (V7-238) for an array of Combustion Engineering
(CE) 14 × 14 spent fuel assemblies in water. A subset of burnup-credit
actinides and fission products are included in the criticality
calculation. A user-supplied 18-axial-region-burnup profile of the
assemblies is input. This profile was obtained from the
axial-burnup-profile database :cite:`cacciapouti_axial_2000` for Maine Yankee assembly N863. Note
that the axial profile will be normalized automatically by the code
using NPR=yes (default). The normalization is performed such that the
average value of the profile values is unity (i.e., the sum of the
profile values is equal to the number of axial zones). The 3.3 wt %
enriched UO\ :sub:`2` fuel is assumed to achieve a discharge burnup of
37,626 MWd/MTU in three cycles of approximately 12.5 GWd/MTU per cycle
and a downtime per cycle of 80 days, followed by a cooling time of
5 years after discharge (1826 days). An average assembly power level of
32 MW/MTU is used for the depletion calculation. Two libraries per cycle
are requested during the depletion. Note that by increasing the number
of libraries generated per cycle, the cross sections used in the burnup
analysis are updated more frequently to reflect the changes that occur
with burnup. The nominal CE 14 × 14 assembly design specifications were
obtained from :cite:`dehart_extension_1996`. The assembly pitch in the criticality
calculations is 22.78 cm. A cross section view of the assembly geometry,
a 2 × 8 array of water reflected assemblies, is illustrated in
:numref:`fig2-3-5`.h](h/Sample problem 3, listed in }(hSample problem 3, listed in h jNhhh!NhNubh_)}(h:numref:`list2-3-3`h]j)}(hjNh]h/ list2-3-3}(hhh jNubah}(h]h](jstd
std-numrefeh]h]h]uhjh jNubah}(h]h]h]h]h]refdocj refdomainjNreftypenumrefrefexplicitrefwarnj list2-3-3uhh^h!jIhMh jNubh/X, performs a burnup-credit
criticality safety calculation using the SCALE 238-group ENDF/B-VII
cross section library (V7-238) for an array of Combustion Engineering
(CE) 14 × 14 spent fuel assemblies in water. A subset of burnup-credit
actinides and fission products are included in the criticality
calculation. A user-supplied 18-axial-region-burnup profile of the
assemblies is input. This profile was obtained from the
axial-burnup-profile database }(hX, performs a burnup-credit
criticality safety calculation using the SCALE 238-group ENDF/B-VII
cross section library (V7-238) for an array of Combustion Engineering
(CE) 14 × 14 spent fuel assemblies in water. A subset of burnup-credit
actinides and fission products are included in the criticality
calculation. A user-supplied 18-axial-region-burnup profile of the
assemblies is input. This profile was obtained from the
axial-burnup-profile database h jNhhh!NhNubh_)}(hcacciapouti_axial_2000h]he)}(hjNh]h/[cacciapouti_axial_2000]}(hhh jNubah}(h]h]h]h]h]uhhdh jNubah}(h]jJah]hwah]h]h] refdomainh|reftypeh~ reftargetjNrefwarnsupport_smartquotesuhh^h!jIhMh jNhhubh/XH for Maine Yankee assembly N863. Note
that the axial profile will be normalized automatically by the code
using NPR=yes (default). The normalization is performed such that the
average value of the profile values is unity (i.e., the sum of the
profile values is equal to the number of axial zones). The 3.3 wt %
enriched UO }(hXH for Maine Yankee assembly N863. Note
that the axial profile will be normalized automatically by the code
using NPR=yes (default). The normalization is performed such that the
average value of the profile values is unity (i.e., the sum of the
profile values is equal to the number of axial zones). The 3.3 wt %
enriched UO\ h jNhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jOubah}(h]h]h]h]h]uhjh jNubh/X fuel is assumed to achieve a discharge burnup of
37,626 MWd/MTU in three cycles of approximately 12.5 GWd/MTU per cycle
and a downtime per cycle of 80 days, followed by a cooling time of
5 years after discharge (1826 days). An average assembly power level of
32 MW/MTU is used for the depletion calculation. Two libraries per cycle
are requested during the depletion. Note that by increasing the number
of libraries generated per cycle, the cross sections used in the burnup
analysis are updated more frequently to reflect the changes that occur
with burnup. The nominal CE 14 × 14 assembly design specifications were
obtained from }(hX fuel is assumed to achieve a discharge burnup of
37,626 MWd/MTU in three cycles of approximately 12.5 GWd/MTU per cycle
and a downtime per cycle of 80 days, followed by a cooling time of
5 years after discharge (1826 days). An average assembly power level of
32 MW/MTU is used for the depletion calculation. Two libraries per cycle
are requested during the depletion. Note that by increasing the number
of libraries generated per cycle, the cross sections used in the burnup
analysis are updated more frequently to reflect the changes that occur
with burnup. The nominal CE 14 × 14 assembly design specifications were
obtained from h jNhhh!NhNubh_)}(hdehart_extension_1996h]he)}(hj!Oh]h/[dehart_extension_1996]}(hhh j#Oubah}(h]h]h]h]h]uhhdh jOubah}(h]jQKah]hwah]h]h] refdomainh|reftypeh~ reftargetj!Orefwarnsupport_smartquotesuhh^h!jIhMh jNhhubh/. The assembly pitch in the criticality
calculations is 22.78 cm. A cross section view of the assembly geometry,
a 2 × 8 array of water reflected assemblies, is illustrated in
}(h. The assembly pitch in the criticality
calculations is 22.78 cm. A cross section view of the assembly geometry,
a 2 × 8 array of water reflected assemblies, is illustrated in
h jNhhh!NhNubh_)}(h:numref:`fig2-3-5`h]j)}(hjBOh]h/fig2-3-5}(hhh jDOubah}(h]h](jstd
std-numrefeh]h]h]uhjh j@Oubah}(h]h]h]h]h]refdocj refdomainjNOreftypenumrefrefexplicitrefwarnjfig2-3-5uhh^h!jIhMh jNubh/.}(hjh jNhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jNhhubjJ)}(hhh](j)}(h)STARBUCS input listing for sample problemh]h/)STARBUCS input listing for sample problem}(hjoOh jmOubah}(h]h]h]h]h]uhjh!jIhMh jjOubj)}(hX =starbucs
CE 14x14 assembly 2 x 8 array
V7-238
read comp
' UO2 Fuel 3.3 wt% u235
uo2 1 den=10.045 1 273 92234 0.0294 92235 3.3 92236 0.0152 92238 96.6554 end
'Zircalloy
zirc4 2 1 end
'Water
h2o 3 1 end
end comp
read celldata
latticecell squarepitch pitch=1.473 3 fueld=0.968 1
cladd=1.118 2 gapd=0.985 0 end
end celldata
read control
arp=ce14x14 nax=18
axp=
0.67053 0.93322 1.02433 1.05329 1.06026 1.06185
1.06215 1.06249 1.06312 1.06408 1.06541 1.06702
1.06836 1.06760 1.05918 1.02515 0.92262 0.66935 end
nuc=
u-234 u-235 u-236 u-238 pu-238 pu-239 pu-240
pu-241 pu-242 am-241 np-237
mo-95 tc-99 ru-101 rh-103 ag-109 cs-133 nd-143
nd-145 sm-147 sm-149 sm-150 sm-151 eu-151 sm-152
eu-153 gd-155 end
end control
read hist
power=32.00 burn=391.937 nlib=2 down=80 end
power=32.00 burn=391.937 nlib=2 down=80 end
power=32.00 burn=391.937 nlib=2 down=1826 end
end hist
read keno
'
'******************************************
'* materials
'* 101 = uo2, lower axial region (0.67053)
'* 118 = uo2, upper axial region (0.66935)
'* 2 = Zircaloy
'* 3 = Water
'******************************************
read param
tme=10000 gen=510 nsk=10 npg=1000
end param
read geom
' Fuel Pin
unit 1
cylinder 101 1 0.484 -162.53 -182.85
cylinder 102 1 0.484 -142.22 -182.85
cylinder 103 1 0.484 -121.90 -182.85
cylinder 104 1 0.484 -101.58 -182.85
cylinder 105 1 0.484 -81.27 -182.85
cylinder 106 1 0.484 -60.95 -182.85
cylinder 107 1 0.484 -40.63 -182.85
cylinder 108 1 0.484 -20.32 -182.85
cylinder 109 1 0.484 0.00 -182.85
cylinder 110 1 0.484 20.32 -182.85
cylinder 111 1 0.484 40.63 -182.85
cylinder 112 1 0.484 60.95 -182.85
cylinder 113 1 0.484 81.27 -182.85
cylinder 114 1 0.484 101.58 -182.85
cylinder 115 1 0.484 121.90 -182.85
cylinder 116 1 0.484 142.22 -182.85
cylinder 117 1 0.484 162.53 -182.85
cylinder 118 1 0.484 182.85 -182.85
cylinder 0 1 0.4925 182.85 -182.85
cylinder 2 1 0.559 182.85 -182.85
cuboid 3 1 4p0.7365 182.85 -182.85
'
' 2 x 2 Array of Fuel Pins
unit 2
array 1 3*0
'
' Large Water Hole
unit 3
cylinder 3 1 1.3140 182.85 -182.85
cylinder 2 1 1.4160 182.85 -182.85
cuboid 3 1 4p1.473 182.85 -182.85
'
' Assembly Unit
unit 4
array 2 -10.311 -10.3124 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly Array (2x8)
global
unit 5
array 3 3*0
reflector 3 1 6r30.0 1
end geom
read array
ara=1 nux=2 nuy=2 nuz=1 fill
1 1
1 1 end fill
ara=2 nux=7 nuy=7 nuz=1 fill
2 2 2 2 2 2 2
2 3 2 2 2 3 2
2 2 2 2 2 2 2
2 2 2 3 2 2 2
2 2 2 2 2 2 2
2 3 2 2 2 3 2
2 2 2 2 2 2 2 end fill
ara=3 nux=2 nuy=8 nuz=1 fill
16r4 end fill
end array
read bounds all=void end bounds
end data
end keno
endh]h/X =starbucs
CE 14x14 assembly 2 x 8 array
V7-238
read comp
' UO2 Fuel 3.3 wt% u235
uo2 1 den=10.045 1 273 92234 0.0294 92235 3.3 92236 0.0152 92238 96.6554 end
'Zircalloy
zirc4 2 1 end
'Water
h2o 3 1 end
end comp
read celldata
latticecell squarepitch pitch=1.473 3 fueld=0.968 1
cladd=1.118 2 gapd=0.985 0 end
end celldata
read control
arp=ce14x14 nax=18
axp=
0.67053 0.93322 1.02433 1.05329 1.06026 1.06185
1.06215 1.06249 1.06312 1.06408 1.06541 1.06702
1.06836 1.06760 1.05918 1.02515 0.92262 0.66935 end
nuc=
u-234 u-235 u-236 u-238 pu-238 pu-239 pu-240
pu-241 pu-242 am-241 np-237
mo-95 tc-99 ru-101 rh-103 ag-109 cs-133 nd-143
nd-145 sm-147 sm-149 sm-150 sm-151 eu-151 sm-152
eu-153 gd-155 end
end control
read hist
power=32.00 burn=391.937 nlib=2 down=80 end
power=32.00 burn=391.937 nlib=2 down=80 end
power=32.00 burn=391.937 nlib=2 down=1826 end
end hist
read keno
'
'******************************************
'* materials
'* 101 = uo2, lower axial region (0.67053)
'* 118 = uo2, upper axial region (0.66935)
'* 2 = Zircaloy
'* 3 = Water
'******************************************
read param
tme=10000 gen=510 nsk=10 npg=1000
end param
read geom
' Fuel Pin
unit 1
cylinder 101 1 0.484 -162.53 -182.85
cylinder 102 1 0.484 -142.22 -182.85
cylinder 103 1 0.484 -121.90 -182.85
cylinder 104 1 0.484 -101.58 -182.85
cylinder 105 1 0.484 -81.27 -182.85
cylinder 106 1 0.484 -60.95 -182.85
cylinder 107 1 0.484 -40.63 -182.85
cylinder 108 1 0.484 -20.32 -182.85
cylinder 109 1 0.484 0.00 -182.85
cylinder 110 1 0.484 20.32 -182.85
cylinder 111 1 0.484 40.63 -182.85
cylinder 112 1 0.484 60.95 -182.85
cylinder 113 1 0.484 81.27 -182.85
cylinder 114 1 0.484 101.58 -182.85
cylinder 115 1 0.484 121.90 -182.85
cylinder 116 1 0.484 142.22 -182.85
cylinder 117 1 0.484 162.53 -182.85
cylinder 118 1 0.484 182.85 -182.85
cylinder 0 1 0.4925 182.85 -182.85
cylinder 2 1 0.559 182.85 -182.85
cuboid 3 1 4p0.7365 182.85 -182.85
'
' 2 x 2 Array of Fuel Pins
unit 2
array 1 3*0
'
' Large Water Hole
unit 3
cylinder 3 1 1.3140 182.85 -182.85
cylinder 2 1 1.4160 182.85 -182.85
cuboid 3 1 4p1.473 182.85 -182.85
'
' Assembly Unit
unit 4
array 2 -10.311 -10.3124 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly Array (2x8)
global
unit 5
array 3 3*0
reflector 3 1 6r30.0 1
end geom
read array
ara=1 nux=2 nuy=2 nuz=1 fill
1 1
1 1 end fill
ara=2 nux=7 nuy=7 nuz=1 fill
2 2 2 2 2 2 2
2 3 2 2 2 3 2
2 2 2 2 2 2 2
2 2 2 3 2 2 2
2 2 2 2 2 2 2
2 3 2 2 2 3 2
2 2 2 2 2 2 2 end fill
ara=3 nux=2 nuy=8 nuz=1 fill
16r4 end fill
end array
read bounds all=void end bounds
end data
end keno
end}(hhh j{Oubah}(h]h]h]h]h]jjj;JjJ}uhjh!jIhMh jjOubeh}(h] list2-3-3ah]jDJah] list2-3-3ah]h]
literal_blockuhjJh jNhhh!hhNubh)}(h
.. _fig2-3-5:h]h}(h]h]h]h]h]hfig2-3-5uhh
hM$h jNhhh!jIubj)}(hhh](j)}(h.. figure:: figs/STARBUCS/fig5.png
:align: center
:width: 500
Plot of the CE 14 × 14 assembly array geometry in sample problem 3.
h]h}(h]h]h]h]h]width500urifigs/STARBUCS/fig5.pngj}jjOsuhjh jOh!jIhMjubj)}(hDPlot of the CE 14 × 14 assembly array geometry in sample problem 3.h]h/DPlot of the CE 14 × 14 assembly array geometry in sample problem 3.}(hjOh jOubah}(h]h]h]h]h]uhjh!jIhMjh jOubeh}(h](id95jOeh]h]fig2-3-5ah]h]jcenteruhjhMjh jNhhh!jIj}jOjOsj}jOjOsubeh}(h]sample-problem-3ah]h]sample problem 3ah]h]uhh#h juLhhh!jIhMubh$)}(hhh](h))}(hSample problem 4h]h/Sample problem 4}(hjOh jOhhh!NhNubah}(h]h]h]h]h]uhh(h jOhhh!jIhMmubh;)}(hXSample problem 4, listed in :numref:`list2-3-4`, illustrates the application of
STARBUCS for a criticality safety analysis of a burnup-credit cask. The
cask geometry in this example is based on a 32-assembly generic
burnup-credit cask model and is illustrated in :numref:`fig2-3-6`.h](h/Sample problem 4, listed in }(hSample problem 4, listed in h jOhhh!NhNubh_)}(h:numref:`list2-3-4`h]j)}(hjOh]h/ list2-3-4}(hhh jOubah}(h]h](jstd
std-numrefeh]h]h]uhjh jOubah}(h]h]h]h]h]refdocj refdomainjOreftypenumrefrefexplicitrefwarnj list2-3-4uhh^h!jIhMoh jOubh/, illustrates the application of
STARBUCS for a criticality safety analysis of a burnup-credit cask. The
cask geometry in this example is based on a 32-assembly generic
burnup-credit cask model and is illustrated in }(h, illustrates the application of
STARBUCS for a criticality safety analysis of a burnup-credit cask. The
cask geometry in this example is based on a 32-assembly generic
burnup-credit cask model and is illustrated in h jOhhh!NhNubh_)}(h:numref:`fig2-3-6`h]j)}(hjPh]h/fig2-3-6}(hhh jPubah}(h]h](jstd
std-numrefeh]h]h]uhjh jPubah}(h]h]h]h]h]refdocj refdomainjPreftypenumrefrefexplicitrefwarnjfig2-3-6uhh^h!jIhMoh jOubh/.}(hjh jOhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMoh jOhhubh;)}(hX\The assemblies are assumed to be W 17 × 17 OFA assemblies with an
initial enrichment of 4.98 wt %. The standard composition description
for this problem includes the fuel assembly and all cask structural
material definitions. The analysis applies built-in 18-axial-zone
profiles, and actinide-only burnup credit (i.e., only a subset of
actinides and no fission products). The assembly is irradiated to an
average burnup of about 50 GWd/MTU. The axial-burnup profile is
automatically selected by the code based on the average assembly burnup.
Isotopic correction factors are applied to the calculated actinide
inventories. The correction factors were obtained from Ref. 4. An
axial-moderator density is also applied. Note that actual entries in the
MOD= array are not realistic for a PWR and are only intended to
illustrate the use of this feature. Since the ORIGEN library applied in
this calculation does not have variable moderator density, the values in
the MOD= array have no effect on the calculation. The criticality
evaluation of the cask is performed following a cooling time of
1826 days (5 years).h]h/X\The assemblies are assumed to be W 17 × 17 OFA assemblies with an
initial enrichment of 4.98 wt %. The standard composition description
for this problem includes the fuel assembly and all cask structural
material definitions. The analysis applies built-in 18-axial-zone
profiles, and actinide-only burnup credit (i.e., only a subset of
actinides and no fission products). The assembly is irradiated to an
average burnup of about 50 GWd/MTU. The axial-burnup profile is
automatically selected by the code based on the average assembly burnup.
Isotopic correction factors are applied to the calculated actinide
inventories. The correction factors were obtained from Ref. 4. An
axial-moderator density is also applied. Note that actual entries in the
MOD= array are not realistic for a PWR and are only intended to
illustrate the use of this feature. Since the ORIGEN library applied in
this calculation does not have variable moderator density, the values in
the MOD= array have no effect on the calculation. The criticality
evaluation of the cask is performed following a cooling time of
1826 days (5 years).}(hj=Ph j;Phhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMth jOhhubh)}(h
.. _fig2-3-6:h]h}(h]h]h]h]h]hfig2-3-6uhh
hM$h jOhhh!jIubj)}(hhh](j)}(h.. figure:: figs/STARBUCS/fig6.png
:align: center
:width: 500
Cutaway view of the generic 32-assembly burnup-credit cask showing the cask bottom half with a quarter of the model removed.
h]h}(h]h]h]h]h]width500urifigs/STARBUCS/fig6.pngj}jjdPsuhjh jTPh!jIhMubj)}(h|Cutaway view of the generic 32-assembly burnup-credit cask showing the cask bottom half with a quarter of the model removed.h]h/|Cutaway view of the generic 32-assembly burnup-credit cask showing the cask bottom half with a quarter of the model removed.}(hjhPh jfPubah}(h]h]h]h]h]uhjh!jIhMh jTPubeh}(h](id96jSPeh]h]fig2-3-6ah]h]jcenteruhjhMh jOhhh!jIj}jyPjIPsj}jSPjIPsubjJ)}(hhh](j)}(h+STARBUCS input listing for sample problem 4h]h/+STARBUCS input listing for sample problem 4}(hjPh jPubah}(h]h]h]h]h]uhjh!jIhMh jPubj)}(hX#=starbucs
PWR 18-axial zone W17x17 assembly, GBC-32 assembly cask model
v7-238
read comp
' UO2 Fuel Rod 4.98 wt % u235
uo2 1 den=10.96 0.95 293.0 92235 4.98 92238 95.02 end
'Zircalloy
zirc2 2 1 end
'Water
h2o 3 1 end
'Stainless Steel
ss304 4 1 end
' BORAL Center - B-10 loading of 0.0225 g/cm3
b-10 5 0 6.5795E-03 293.0 end
b-11 5 0 2.7260E-02 293.0 end
c 5 0 8.4547E-03 293.0 end
al 5 0 4.1795E-02 293.0 end
'Stainless Steel
ss304 6 1 end
' aluminum
al 7 0 0.0602 293.0 end
end comp
read celldata
latticecell squarepitch pitch=1.2598 3 fueld=0.7844 1 cladd=0.9144 2 gapd=0.8001 0 end
end celldata
read control
arp=w17x17_ofa nax=-18
nuc= u-234 0.635
u-235 1.085
u-236 0.910
u-238 0.992
pu-238 0.856
pu-239 1.076
pu-240 0.945
pu-241 1.087
pu-242 0.848
am-241 0.609
am-243 0.804
np-237 0.697 end
mod= 0.720 0.709 0.699 0.688 0.678 0.667 0.657
0.646 0.635 0.625 0.614 0.604 0.593 0.583
0.572 0.562 0.551 0.540 end
end control
read hist
power=32.89 burn=100 end
power=32.89 burn=200 end
power=32.89 burn=900 nlib=3 end
power=32.89 burn=320 down=-1826 end
end hist
read kenova
'**************************************
'* Assembly Type: Westinghouse 17x17 OFA/V5
'* Materials
'* 101 - 118 = uo2, axial regions 1 through 18
'* 2 = Zircaloy
'* 3 = Water
'* 4 = Stainless Steel
'* 5 = Boral
'* 6 = Stainless Steel
'* 7 = Al
'**************************************
read param tme=10000 gen=510 nsk=10 npg=1000 end param
read geom
unit 1
com='Fuel Pin'
cylinder 101 1 0.3922 -162.53 -182.85
cylinder 102 1 0.3922 -142.22 -182.85
cylinder 103 1 0.3922 -121.90 -182.85
cylinder 104 1 0.3922 -101.58 -182.85
cylinder 105 1 0.3922 -81.27 -182.85
cylinder 106 1 0.3922 -60.95 -182.85
cylinder 107 1 0.3922 -40.63 -182.85
cylinder 108 1 0.3922 -20.32 -182.85
cylinder 109 1 0.3922 0.00 -182.85
cylinder 110 1 0.3922 20.32 -182.85
cylinder 111 1 0.3922 40.63 -182.85
cylinder 112 1 0.3922 60.95 -182.85
cylinder 113 1 0.3922 81.27 -182.85
cylinder 114 1 0.3922 101.58 -182.85
cylinder 115 1 0.3922 121.90 -182.85
cylinder 116 1 0.3922 142.22 -182.85
cylinder 117 1 0.3922 162.53 -182.85
cylinder 118 1 0.3922 182.85 -182.85
cylinder 0 1 0.40005 182.85 -182.85
cylinder 2 1 0.4572 182.85 -182.85
cuboid 3 1 2p0.6299 2p0.6299 182.88 -182.88
unit 2
com='Guide Thimble/Instrument Tube'
cylinder 3 1 0.56135 365.76 0
cylinder 2 1 0.602 365.76 0
cuboid 3 1 0.6299 -0.6299 0.6299 -0.6299 365.76 0
unit 4
com='Top Half Horizontal Boral Panel'
cuboid 7 1 9.5250 -9.5250 0.02540 0.0 365.76 0.
cuboid 5 1 9.5250 -9.5250 0.12827 0.0 365.76 0.
cuboid 3 1 11.75 -11.75 0.12827 0 365.76 0
unit 5
com='Right-Hand Side Half Vertical Boral Panel'
cuboid 7 1 0.02540 0.0 9.5250 -9.5250 365.76 0.
cuboid 5 1 0.128270 0.0 9.5250 -9.5250 365.76 0.
cuboid 3 1 0.12827 0 11.75 -11.75 365.76 0
unit 6
com='Bottom Half Horizontal Boral Panel'
cuboid 7 1 9.5250 -9.5250 0.0 -0.0254 365.76 0.
cuboid 5 1 9.5250 -9.5250 0.0 -0.12827 365.76 0.
cuboid 3 1 11.75 -11.75 0.0 -0.12827 365.76 0
unit 7
com='Left-Hand Side Half Vertical Boral Panel'
cuboid 7 1 0.0 -0.0254 9.5250 -9.5250 365.76 0.
cuboid 5 1 0.0 -0.12827 9.5250 -9.5250 365.76 0.
cuboid 3 1 0.0 -0.12827 11.75 -11.75 365.76 0
unit 8
com='Empty Corner (Water)'
cuboid 3 1 0.12827 0 0.12827 0 365.76 0
unit 10
com='Top Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 9.525 -9.525 -0.7754 -0.87827 365.76 0
cuboid 7 1 9.525 -9.525 -0.75 -0.87827 365.76 0
cuboid 3 1 11.7500 -11.75 -0.75 -0.87827 365.76 0.
cuboid 4 1 11.7500 -11.75 0.0 -0.87827 365.76 0.
cuboid 3 1 11.87827 -11.87827 0.12827 -0.87827 365.76 0
unit 11
com='Bottom Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 9.525 -9.525 0.87827 0.7754 365.76 0
cuboid 7 1 9.525 -9.525 0.87827 0.75 365.76 0
cuboid 3 1 11.7500 -11.75 0.87827 0.75 365.76 0.
cuboid 4 1 11.7500 -11.75 0.87827 0.0 365.76 0.
cuboid 3 1 11.87827 -11.87827 0.87827 -0.12827 365.76 0
unit 12
com='Left-Hand Side Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 0.87827 0.7754 9.525 -9.525 365.76 0
cuboid 7 1 0.87827 0.75 9.525 -9.525 365.76 0
cuboid 3 1 0.87827 0.75 11.75 -11.75 365.76 0.
cuboid 4 1 0.87827 0.0 11.75 -11.75 365.76 0.
cuboid 3 1 0.87827 -0.12827 11.87827 -11.87827 365.76 0.
unit 13
com='Right-Hand Side Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 -0.7754 -0.87827 9.525 -9.525 365.76 0
cuboid 7 1 -0.75 -0.87827 9.525 -9.525 365.76 0
cuboid 3 1 -0.75 -0.87827 11.75 -11.75 365.76 0.
cuboid 4 1 0.0 -0.87827 11.75 -11.75 365.76 0.
cuboid 3 1 0.12827 -0.87827 11.87827 -11.87827 365.76 0
unit 20
com='Top Boral/Basket Plate'
cuboid 5 1 9.525 -9.525 -0.7754 -0.87827 365.76 0
cuboid 7 1 9.525 -9.525 -0.75 -0.87827 365.76 0
cuboid 3 1 11.7500 -11.75 -0.75 -0.87827 365.76 0.
cuboid 4 1 11.7500 -11.75 0.0 -0.87827 365.76 0.
unit 21
com='Bottom Boral/Basket Plate'
cuboid 5 1 9.525 -9.525 0.87827 0.7754 365.76 0
cuboid 7 1 9.525 -9.525 0.87827 0.75 365.76 0
cuboid 3 1 11.7500 -11.75 0.87827 0.75 365.76 0.
cuboid 4 1 11.7500 -11.75 0.87827 0.0 365.76 0.
unit 22
com='Left-Hand Side Boral/Basket Plate'
cuboid 5 1 0.87827 0.7754 9.525 -9.525 365.76 0
cuboid 7 1 0.87827 0.75 9.525 -9.525 365.76 0
cuboid 3 1 0.87827 0.75 10.9999 -10.9999 365.76 0.
cuboid 4 1 0.87827 0.0 10.9999 -10.9999 365.76 0.
unit 23
com='Right-Hand Side Boral/Basket Plate'
cuboid 5 1 -0.7754 -0.87827 9.525 -9.525 365.76 0
cuboid 7 1 -0.75 -0.87827 9.525 -9.525 365.76 0
cuboid 3 1 -0.75 -0.87827 10.9999 -10.9999 365.76 0.
cuboid 4 1 0.0 -0.87827 10.9999 -10.9999 365.76 0.
unit 100
com='17x17 Fuel Assembly in Basket'
array 1 -10.7083 -10.7083 0
cuboid 3 1 11 -11 11 -11 365.76 0
cuboid 0 1 11 -11 11 -11 365.76 0
cuboid 4 1 11.75 -11.75 11.75 -11.75 365.76 0
unit 101
com='17x17 Fuel Assembly in Basket with Half Boral Panels'
array 2 0 0 0
unit 112
com='Top Row of Fuel Assemblies'
array 12 -47.51308 -12.38154 0
unit 113
com='Left Row of Fuel Assemblies'
array 13 -12.38154 -47.51308 0
unit 114
com='Bottom Row of Fuel Assemblies'
array 14 -47.51308 -12.38154 0
unit 115
com='Right Row of Fuel Assemblies'
array 15 -12.38154 -47.51308 0
global unit 200
com='Cask with 32 Fuel Assemblies'
array 3 -47.51308 -47.51308 0
cylinder 3 1 87.5 395.76 -30
hole 112 0 59.89463 0
hole 114 0 -59.89463 0
hole 113 -59.89463 0 0
hole 115 59.89463 0 0
hole 20 59.39136 48.39136 0
hole 20 -59.39136 48.39136 0
hole 21 59.39136 -48.39136 0
hole 21 -59.39136 -48.39136 0
hole 22 -48.39136 59.39136 0
hole 22 -48.39136 -59.39136 0
hole 23 48.39136 59.39136 0
hole 23 48.39136 -59.39136 0
cylinder 6 1 107.5 425.76 -60
cuboid 0 1 108 -108 108 -108 425.76 -60
end geom
read array
ara=1 nux=17 nuy=17 nuz=1
fill 39*1 2 2*1 2 2*1 2 8*1 2 9*1 2 22*1 2 2*1 2 2*1 2 2*1 2 2*1 2 38*1 2 2*1 2
2*1 2 2*1 2 2*1 2 38*1 2 2*1 2 2*1 2 2*1 2 2*1 2 22*1 2 9*1 2 8*1 2 2*1 2 2*1
2 39*1
end fill
ara=2 nux=3 nuy=3 nuz=1
fill 8 4 8
5 100 7
8 6 8
end fill
ara=3 nux=4 nuy=4 nuz=1
fill f101 end fill
ara=12 nux=4 nuy=2 nuz=1
fill 101 101 101 101
10 10 10 10
end fill
ara=13 nux=2 nuy=4 nuz=1
fill 12 101
12 101
12 101
12 101
end fill
ara=14 nux=4 nuy=2 nuz=1
fill 11 11 11 11
101 101 101 101
end fill
ara=15 nux=2 nuy=4 nuz=1
fill 101 13
101 13
101 13
101 13
end fill
end array
read plot
ttl='2-d cross section of gbc-32 cask'
xul=-90 yul=90 zul=100
xlr=90 ylr=-90 zlr=100
nax=800
uax=1 vdn=-1 end
end plot
read bounds xyf=mirror end bounds
end data
end kenova
endh]h/X#=starbucs
PWR 18-axial zone W17x17 assembly, GBC-32 assembly cask model
v7-238
read comp
' UO2 Fuel Rod 4.98 wt % u235
uo2 1 den=10.96 0.95 293.0 92235 4.98 92238 95.02 end
'Zircalloy
zirc2 2 1 end
'Water
h2o 3 1 end
'Stainless Steel
ss304 4 1 end
' BORAL Center - B-10 loading of 0.0225 g/cm3
b-10 5 0 6.5795E-03 293.0 end
b-11 5 0 2.7260E-02 293.0 end
c 5 0 8.4547E-03 293.0 end
al 5 0 4.1795E-02 293.0 end
'Stainless Steel
ss304 6 1 end
' aluminum
al 7 0 0.0602 293.0 end
end comp
read celldata
latticecell squarepitch pitch=1.2598 3 fueld=0.7844 1 cladd=0.9144 2 gapd=0.8001 0 end
end celldata
read control
arp=w17x17_ofa nax=-18
nuc= u-234 0.635
u-235 1.085
u-236 0.910
u-238 0.992
pu-238 0.856
pu-239 1.076
pu-240 0.945
pu-241 1.087
pu-242 0.848
am-241 0.609
am-243 0.804
np-237 0.697 end
mod= 0.720 0.709 0.699 0.688 0.678 0.667 0.657
0.646 0.635 0.625 0.614 0.604 0.593 0.583
0.572 0.562 0.551 0.540 end
end control
read hist
power=32.89 burn=100 end
power=32.89 burn=200 end
power=32.89 burn=900 nlib=3 end
power=32.89 burn=320 down=-1826 end
end hist
read kenova
'**************************************
'* Assembly Type: Westinghouse 17x17 OFA/V5
'* Materials
'* 101 - 118 = uo2, axial regions 1 through 18
'* 2 = Zircaloy
'* 3 = Water
'* 4 = Stainless Steel
'* 5 = Boral
'* 6 = Stainless Steel
'* 7 = Al
'**************************************
read param tme=10000 gen=510 nsk=10 npg=1000 end param
read geom
unit 1
com='Fuel Pin'
cylinder 101 1 0.3922 -162.53 -182.85
cylinder 102 1 0.3922 -142.22 -182.85
cylinder 103 1 0.3922 -121.90 -182.85
cylinder 104 1 0.3922 -101.58 -182.85
cylinder 105 1 0.3922 -81.27 -182.85
cylinder 106 1 0.3922 -60.95 -182.85
cylinder 107 1 0.3922 -40.63 -182.85
cylinder 108 1 0.3922 -20.32 -182.85
cylinder 109 1 0.3922 0.00 -182.85
cylinder 110 1 0.3922 20.32 -182.85
cylinder 111 1 0.3922 40.63 -182.85
cylinder 112 1 0.3922 60.95 -182.85
cylinder 113 1 0.3922 81.27 -182.85
cylinder 114 1 0.3922 101.58 -182.85
cylinder 115 1 0.3922 121.90 -182.85
cylinder 116 1 0.3922 142.22 -182.85
cylinder 117 1 0.3922 162.53 -182.85
cylinder 118 1 0.3922 182.85 -182.85
cylinder 0 1 0.40005 182.85 -182.85
cylinder 2 1 0.4572 182.85 -182.85
cuboid 3 1 2p0.6299 2p0.6299 182.88 -182.88
unit 2
com='Guide Thimble/Instrument Tube'
cylinder 3 1 0.56135 365.76 0
cylinder 2 1 0.602 365.76 0
cuboid 3 1 0.6299 -0.6299 0.6299 -0.6299 365.76 0
unit 4
com='Top Half Horizontal Boral Panel'
cuboid 7 1 9.5250 -9.5250 0.02540 0.0 365.76 0.
cuboid 5 1 9.5250 -9.5250 0.12827 0.0 365.76 0.
cuboid 3 1 11.75 -11.75 0.12827 0 365.76 0
unit 5
com='Right-Hand Side Half Vertical Boral Panel'
cuboid 7 1 0.02540 0.0 9.5250 -9.5250 365.76 0.
cuboid 5 1 0.128270 0.0 9.5250 -9.5250 365.76 0.
cuboid 3 1 0.12827 0 11.75 -11.75 365.76 0
unit 6
com='Bottom Half Horizontal Boral Panel'
cuboid 7 1 9.5250 -9.5250 0.0 -0.0254 365.76 0.
cuboid 5 1 9.5250 -9.5250 0.0 -0.12827 365.76 0.
cuboid 3 1 11.75 -11.75 0.0 -0.12827 365.76 0
unit 7
com='Left-Hand Side Half Vertical Boral Panel'
cuboid 7 1 0.0 -0.0254 9.5250 -9.5250 365.76 0.
cuboid 5 1 0.0 -0.12827 9.5250 -9.5250 365.76 0.
cuboid 3 1 0.0 -0.12827 11.75 -11.75 365.76 0
unit 8
com='Empty Corner (Water)'
cuboid 3 1 0.12827 0 0.12827 0 365.76 0
unit 10
com='Top Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 9.525 -9.525 -0.7754 -0.87827 365.76 0
cuboid 7 1 9.525 -9.525 -0.75 -0.87827 365.76 0
cuboid 3 1 11.7500 -11.75 -0.75 -0.87827 365.76 0.
cuboid 4 1 11.7500 -11.75 0.0 -0.87827 365.76 0.
cuboid 3 1 11.87827 -11.87827 0.12827 -0.87827 365.76 0
unit 11
com='Bottom Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 9.525 -9.525 0.87827 0.7754 365.76 0
cuboid 7 1 9.525 -9.525 0.87827 0.75 365.76 0
cuboid 3 1 11.7500 -11.75 0.87827 0.75 365.76 0.
cuboid 4 1 11.7500 -11.75 0.87827 0.0 365.76 0.
cuboid 3 1 11.87827 -11.87827 0.87827 -0.12827 365.76 0
unit 12
com='Left-Hand Side Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 0.87827 0.7754 9.525 -9.525 365.76 0
cuboid 7 1 0.87827 0.75 9.525 -9.525 365.76 0
cuboid 3 1 0.87827 0.75 11.75 -11.75 365.76 0.
cuboid 4 1 0.87827 0.0 11.75 -11.75 365.76 0.
cuboid 3 1 0.87827 -0.12827 11.87827 -11.87827 365.76 0.
unit 13
com='Right-Hand Side Boral/Basket Plate with water added to fit array dimensions'
cuboid 5 1 -0.7754 -0.87827 9.525 -9.525 365.76 0
cuboid 7 1 -0.75 -0.87827 9.525 -9.525 365.76 0
cuboid 3 1 -0.75 -0.87827 11.75 -11.75 365.76 0.
cuboid 4 1 0.0 -0.87827 11.75 -11.75 365.76 0.
cuboid 3 1 0.12827 -0.87827 11.87827 -11.87827 365.76 0
unit 20
com='Top Boral/Basket Plate'
cuboid 5 1 9.525 -9.525 -0.7754 -0.87827 365.76 0
cuboid 7 1 9.525 -9.525 -0.75 -0.87827 365.76 0
cuboid 3 1 11.7500 -11.75 -0.75 -0.87827 365.76 0.
cuboid 4 1 11.7500 -11.75 0.0 -0.87827 365.76 0.
unit 21
com='Bottom Boral/Basket Plate'
cuboid 5 1 9.525 -9.525 0.87827 0.7754 365.76 0
cuboid 7 1 9.525 -9.525 0.87827 0.75 365.76 0
cuboid 3 1 11.7500 -11.75 0.87827 0.75 365.76 0.
cuboid 4 1 11.7500 -11.75 0.87827 0.0 365.76 0.
unit 22
com='Left-Hand Side Boral/Basket Plate'
cuboid 5 1 0.87827 0.7754 9.525 -9.525 365.76 0
cuboid 7 1 0.87827 0.75 9.525 -9.525 365.76 0
cuboid 3 1 0.87827 0.75 10.9999 -10.9999 365.76 0.
cuboid 4 1 0.87827 0.0 10.9999 -10.9999 365.76 0.
unit 23
com='Right-Hand Side Boral/Basket Plate'
cuboid 5 1 -0.7754 -0.87827 9.525 -9.525 365.76 0
cuboid 7 1 -0.75 -0.87827 9.525 -9.525 365.76 0
cuboid 3 1 -0.75 -0.87827 10.9999 -10.9999 365.76 0.
cuboid 4 1 0.0 -0.87827 10.9999 -10.9999 365.76 0.
unit 100
com='17x17 Fuel Assembly in Basket'
array 1 -10.7083 -10.7083 0
cuboid 3 1 11 -11 11 -11 365.76 0
cuboid 0 1 11 -11 11 -11 365.76 0
cuboid 4 1 11.75 -11.75 11.75 -11.75 365.76 0
unit 101
com='17x17 Fuel Assembly in Basket with Half Boral Panels'
array 2 0 0 0
unit 112
com='Top Row of Fuel Assemblies'
array 12 -47.51308 -12.38154 0
unit 113
com='Left Row of Fuel Assemblies'
array 13 -12.38154 -47.51308 0
unit 114
com='Bottom Row of Fuel Assemblies'
array 14 -47.51308 -12.38154 0
unit 115
com='Right Row of Fuel Assemblies'
array 15 -12.38154 -47.51308 0
global unit 200
com='Cask with 32 Fuel Assemblies'
array 3 -47.51308 -47.51308 0
cylinder 3 1 87.5 395.76 -30
hole 112 0 59.89463 0
hole 114 0 -59.89463 0
hole 113 -59.89463 0 0
hole 115 59.89463 0 0
hole 20 59.39136 48.39136 0
hole 20 -59.39136 48.39136 0
hole 21 59.39136 -48.39136 0
hole 21 -59.39136 -48.39136 0
hole 22 -48.39136 59.39136 0
hole 22 -48.39136 -59.39136 0
hole 23 48.39136 59.39136 0
hole 23 48.39136 -59.39136 0
cylinder 6 1 107.5 425.76 -60
cuboid 0 1 108 -108 108 -108 425.76 -60
end geom
read array
ara=1 nux=17 nuy=17 nuz=1
fill 39*1 2 2*1 2 2*1 2 8*1 2 9*1 2 22*1 2 2*1 2 2*1 2 2*1 2 2*1 2 38*1 2 2*1 2
2*1 2 2*1 2 2*1 2 38*1 2 2*1 2 2*1 2 2*1 2 2*1 2 22*1 2 9*1 2 8*1 2 2*1 2 2*1
2 39*1
end fill
ara=2 nux=3 nuy=3 nuz=1
fill 8 4 8
5 100 7
8 6 8
end fill
ara=3 nux=4 nuy=4 nuz=1
fill f101 end fill
ara=12 nux=4 nuy=2 nuz=1
fill 101 101 101 101
10 10 10 10
end fill
ara=13 nux=2 nuy=4 nuz=1
fill 12 101
12 101
12 101
12 101
end fill
ara=14 nux=4 nuy=2 nuz=1
fill 11 11 11 11
101 101 101 101
end fill
ara=15 nux=2 nuy=4 nuz=1
fill 101 13
101 13
101 13
101 13
end fill
end array
read plot
ttl='2-d cross section of gbc-32 cask'
xul=-90 yul=90 zul=100
xlr=90 ylr=-90 zlr=100
nax=800
uax=1 vdn=-1 end
end plot
read bounds xyf=mirror end bounds
end data
end kenova
end}(hhh jPubah}(h]h]h]h]h]jjj;JjJ}uhjh!jIhMh jPubeh}(h] list2-3-4ah]jDJah] list2-3-4ah]h]
literal_blockuhjJh jOhhh!hhNubeh}(h]sample-problem-4ah]h]sample problem 4ah]h]uhh#h juLhhh!jIhMmubh$)}(hhh](h))}(hSample problem 5h]h/Sample problem 5}(hjPh jPhhh!NhNubah}(h]h]h]h]h]uhh(h jPhhh!jIhMubh;)}(hXSample problem 5, listed in :numref:`list2-3-5`, uses the CE 14 × 14 assembly
design from problem 3, and performs a burnup-credit calculation using
the horizontal burnup-profile option. The assembly configuration is
taken to be a simple 2 × 2 assembly array with water reflection. This
problem is only designed to illustrate the basic features of the
horizontal profile option. In this example, it is assumed that there is
a burnup gradient across the assemblies, such that half the fuel pins
have a burnup exceeding the average assembly burnup by 10% and half the
pins have a burnup of 10% less than the average, with the two burnup
regions separated by the assembly diagonal. The input card required to
simulate the two horizontal burnup regions in an assembly ish](h/Sample problem 5, listed in }(hSample problem 5, listed in h jPhhh!NhNubh_)}(h:numref:`list2-3-5`h]j)}(hjPh]h/ list2-3-5}(hhh jPubah}(h]h](jstd
std-numrefeh]h]h]uhjh jPubah}(h]h]h]h]h]refdocj refdomainjPreftypenumrefrefexplicitrefwarnj list2-3-5uhh^h!jIhMh jPubh/X, uses the CE 14 × 14 assembly
design from problem 3, and performs a burnup-credit calculation using
the horizontal burnup-profile option. The assembly configuration is
taken to be a simple 2 × 2 assembly array with water reflection. This
problem is only designed to illustrate the basic features of the
horizontal profile option. In this example, it is assumed that there is
a burnup gradient across the assemblies, such that half the fuel pins
have a burnup exceeding the average assembly burnup by 10% and half the
pins have a burnup of 10% less than the average, with the two burnup
regions separated by the assembly diagonal. The input card required to
simulate the two horizontal burnup regions in an assembly is}(hX, uses the CE 14 × 14 assembly
design from problem 3, and performs a burnup-credit calculation using
the horizontal burnup-profile option. The assembly configuration is
taken to be a simple 2 × 2 assembly array with water reflection. This
problem is only designed to illustrate the basic features of the
horizontal profile option. In this example, it is assumed that there is
a burnup gradient across the assemblies, such that half the fuel pins
have a burnup exceeding the average assembly burnup by 10% and half the
pins have a burnup of 10% less than the average, with the two burnup
regions separated by the assembly diagonal. The input card required to
simulate the two horizontal burnup regions in an assembly ish jPhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jPhhubj)}(hhzp= 0.9 1.1 endh]h/hzp= 0.9 1.1 end}(hhh jPubah}(h]h]h]h]h]jjuhjh!jIhMh jPhhubh;)}(hX`STARBUCS applies these factors to calculate compositions for each of the
horizontally-varying burnup regions in each zone of the problem. It is
important to note that the option inherently assumes that there is an
equal volume/mass of fuel in each of the horizontal (or axial) zones
since the code weights all regions equally when determining the average
assembly burnup. To illustrate this, consider modeling an assembly with
**only one quadrant** having a burnup that is 10% higher than the other
three quadrants. The user would enter data for each of the four
horizontal assembly quadrants or zones, e.g.,h](h/XSTARBUCS applies these factors to calculate compositions for each of the
horizontally-varying burnup regions in each zone of the problem. It is
important to note that the option inherently assumes that there is an
equal volume/mass of fuel in each of the horizontal (or axial) zones
since the code weights all regions equally when determining the average
assembly burnup. To illustrate this, consider modeling an assembly with
}(hXSTARBUCS applies these factors to calculate compositions for each of the
horizontally-varying burnup regions in each zone of the problem. It is
important to note that the option inherently assumes that there is an
equal volume/mass of fuel in each of the horizontal (or axial) zones
since the code weights all regions equally when determining the average
assembly burnup. To illustrate this, consider modeling an assembly with
h jQhhh!NhNubhA)}(h**only one quadrant**h]h/only one quadrant}(hhh j
Qubah}(h]h]h]h]h]uhh@h jQubh/ having a burnup that is 10% higher than the other
three quadrants. The user would enter data for each of the four
horizontal assembly quadrants or zones, e.g.,}(h having a burnup that is 10% higher than the other
three quadrants. The user would enter data for each of the four
horizontal assembly quadrants or zones, e.g.,h jQhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jPhhubj)}(h$hzp= 0.9766 0.9766 0.9766 1.0700 endh]h/$hzp= 0.9766 0.9766 0.9766 1.0700 end}(hhh j&Qubah}(h]h]h]h]h]jjuhjh!jIhMh jPhhubh;)}(hX]such that the average of the HZP array entries is unity. This ensures
that the average assembly burnup will be that specified in the power
history data block. Note that this array is automatically normalized if
NPR=yes (default). However, the user could substantially reduce the
computational time involved by specifying only two fuel regions, e.g.,h]h/X]such that the average of the HZP array entries is unity. This ensures
that the average assembly burnup will be that specified in the power
history data block. Note that this array is automatically normalized if
NPR=yes (default). However, the user could substantially reduce the
computational time involved by specifying only two fuel regions, e.g.,}(hj6Qh j4Qhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jPhhubj)}(hhzp= 0.9766 1.0700 endh]h/hzp= 0.9766 1.0700 end}(hhh jBQubah}(h]h]h]h]h]jjuhjh!jIhMh jPhhubh;)}(hX+and turning off the normalization option (e.g., NPR=no). The
normalization option must be turned off to prevent the profile from
being altered (since the sum is not equal to 2). This allows the user to
account for the fact that, in this scenario, there are three quadrants
having a lower burnup (and consequently three times the mass) and just
one quadrant having an elevated burnup compared to the average. However,
it is the responsibility of the user to ensure that the profiles and the
KENO V.a problem description produce the desired average burnup.h]h/X+and turning off the normalization option (e.g., NPR=no). The
normalization option must be turned off to prevent the profile from
being altered (since the sum is not equal to 2). This allows the user to
account for the fact that, in this scenario, there are three quadrants
having a lower burnup (and consequently three times the mass) and just
one quadrant having an elevated burnup compared to the average. However,
it is the responsibility of the user to ensure that the profiles and the
KENO V.a problem description produce the desired average burnup.}(hjRQh jPQhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jPhhubh;)}(hXIn this sample problem the four assemblies are aligned so the lower
burnup regions of the assemblies are adjacent to one another to maximize
the system reactivity. The assembly geometry showing the different
burnup regions of the assemblies is illustrated in :numref:`fig2-3-7`. The
criticality calculation is performed using the SCALE ENDF/B-VII
continuous cross section library (CE_V7).h](h/XIn this sample problem the four assemblies are aligned so the lower
burnup regions of the assemblies are adjacent to one another to maximize
the system reactivity. The assembly geometry showing the different
burnup regions of the assemblies is illustrated in }(hXIn this sample problem the four assemblies are aligned so the lower
burnup regions of the assemblies are adjacent to one another to maximize
the system reactivity. The assembly geometry showing the different
burnup regions of the assemblies is illustrated in h j^Qhhh!NhNubh_)}(h:numref:`fig2-3-7`h]j)}(hjiQh]h/fig2-3-7}(hhh jkQubah}(h]h](jstd
std-numrefeh]h]h]uhjh jgQubah}(h]h]h]h]h]refdocj refdomainjuQreftypenumrefrefexplicitrefwarnjfig2-3-7uhh^h!jIhMh j^Qubh/o. The
criticality calculation is performed using the SCALE ENDF/B-VII
continuous cross section library (CE_V7).}(ho. The
criticality calculation is performed using the SCALE ENDF/B-VII
continuous cross section library (CE_V7).h j^Qhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jPhhubh;)}(hXFollowing the STARBUCS calculation, the KENO V.a geometry model could be
readily altered to simulate other assembly configurations (e.g., shuffle
the fuel assembly locations). The CSAS5 case could subsequently be
executed as a standalone case since all of the material compositions
have already been created during the initial STARBUCS run. This
facilitates the rapid evaluation of different fuel configurations
without the need to regenerate the material compositions using STARBUCS.h]h/XFollowing the STARBUCS calculation, the KENO V.a geometry model could be
readily altered to simulate other assembly configurations (e.g., shuffle
the fuel assembly locations). The CSAS5 case could subsequently be
executed as a standalone case since all of the material compositions
have already been created during the initial STARBUCS run. This
facilitates the rapid evaluation of different fuel configurations
without the need to regenerate the material compositions using STARBUCS.}(hjQh jQhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jPhhubjJ)}(hhh](j)}(h+STARBUCS input listing for sample problem 5h]h/+STARBUCS input listing for sample problem 5}(hjQh jQubah}(h]h]h]h]h]uhjh!jIhMh jQubj)}(hX=starbucs
CE 14x14 assembly 4x4 array - horizontal burnup gradient
ce_v7
read comp
' UO2 Fuel Rod 3.038 wt %
uo2 1 den=10.045 1 273
92234 0.027 92235 3.038 92236 0.014 92238 96.921 end
'Zircalloy
arbmzirc 6.44 4 0 0 1 40000 97.91 26000 0.5 50116 0.86 50120 0.73 2 1 620 end
'Water
h2o 3 1 end
end comp
read celldata
latticecell squarepitch pitch=1.473 3 fueld=0.968 1 cladd=1.118 2 gapd=0.985 0 end
end
end celldata
read control
arp=ce14x14
nax=18
axp=
0.67053 0.93322 1.02433 1.05329 1.06026 1.06185
1.06215 1.06249 1.06312 1.06408 1.06541 1.06702
1.06836 1.06760 1.05918 1.02515 0.92262 0.66935 end
nhz= 2
hzp= 0.9 1.1 end
nuc=
u-234 u-235 u-236 u-238 pu-238 pu-239 pu-240
pu-241 pu-242 am-241 am-242m am-243 np-237 end
end control
read hist
power=28.00 burn=520.833 nlib=2 down=80 end
power=28.00 burn=520.833 nlib=2 down=80 end
power=28.00 burn=520.833 nlib=2 down=-1865 end
end hist
read kenova
'*************************************************************
'* materials
'* 101 = uo2, lower axial region, low burnup region
'* 118 = uo2, upper axial region, low burnup region
'* 201 = uo2, lower axial region, high burnup region
'* 218 = uo2, upper axial region, high burnup region
'* 2 = Zircaloy
'* 3 = Water
'*************************************************************
read param
tme=10000 gen=510 nsk=10 npg=1000
end parm
read geom
' Fuel Pin, Low Burnup Region
unit 1
cylinder 101 1 0.484 -162.53 -182.85
cylinder 102 1 0.484 -142.22 -182.85
cylinder 103 1 0.484 -121.90 -182.85
cylinder 104 1 0.484 -101.58 -182.85
cylinder 105 1 0.484 -81.27 -182.85
cylinder 106 1 0.484 -60.95 -182.85
cylinder 107 1 0.484 -40.63 -182.85
cylinder 108 1 0.484 -20.32 -182.85
cylinder 109 1 0.484 0.00 -182.85
cylinder 110 1 0.484 20.32 -182.85
cylinder 111 1 0.484 40.63 -182.85
cylinder 112 1 0.484 60.95 -182.85
cylinder 113 1 0.484 81.27 -182.85
cylinder 114 1 0.484 101.58 -182.85
cylinder 115 1 0.484 121.90 -182.85
cylinder 116 1 0.484 142.22 -182.85
cylinder 117 1 0.484 162.53 -182.85
cylinder 118 1 0.484 182.85 -182.85
cylinder 0 1 0.4925 182.85 -182.85
cylinder 2 1 0.559 182.85 -182.85
cuboid 3 1 4p0.7365 182.85 -182.85
'
' Fuel Pin, High Burnup Region
unit 2
cylinder 201 1 0.484 -162.53 -182.85
cylinder 202 1 0.484 -142.22 -182.85
cylinder 203 1 0.484 -121.90 -182.85
cylinder 204 1 0.484 -101.58 -182.85
cylinder 205 1 0.484 -81.27 -182.85
cylinder 206 1 0.484 -60.95 -182.85
cylinder 207 1 0.484 -40.63 -182.85
cylinder 208 1 0.484 -20.32 -182.85
cylinder 209 1 0.484 0.00 -182.85
cylinder 210 1 0.484 20.32 -182.85
cylinder 211 1 0.484 40.63 -182.85
cylinder 212 1 0.484 60.95 -182.85
cylinder 213 1 0.484 81.27 -182.85
cylinder 214 1 0.484 101.58 -182.85
cylinder 215 1 0.484 121.90 -182.85
cylinder 216 1 0.484 142.22 -182.85
cylinder 217 1 0.484 162.53 -182.85
cylinder 218 1 0.484 182.85 -182.85
cylinder 0 1 0.4925 182.85 -182.85
cylinder 2 1 0.559 182.85 -182.85
cuboid 3 1 4p0.7365 182.85 -182.85
'
' 2 x 2 Array of Lower Burnup Fuel Pins
unit 3
array 1 3*0
'
' 2 x 2 Array of Higher Burnup Fuel Pins
unit 4
array 2 3*0
'
' Large Water Hole
unit 5
cylinder 3 1 1.3140 182.85 -182.85
cylinder 2 1 1.4160 182.85 -182.85
cuboid 3 1 4p1.473 182.85 -182.85
'
' Assembly 1 Unit
unit 6
array 3 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly 2 Unit
unit 7
array 4 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly 3 Unit
unit 8
array 5 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly 4 Unit
unit 9
array 6 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly Array (2 x 2)
global
unit 10
array 7 3*0
reflector 3 1 6r30.0 1
end geom
read array
ara=1 nux=2 nuy=2 nuz=1 fill
1 1
1 1 end fill
ara=2 nux=2 nuy=2 nuz=1 fill
2 2
2 2 end fill
ara=3 nux=7 nuy=7 nuz=1 fill
3 3 3 3 3 3 3
3 5 3 3 3 5 4
3 3 3 3 4 4 4
3 3 3 5 4 4 4
3 3 3 4 4 4 4
3 5 4 4 4 5 4
4 4 4 4 4 4 4 end fill
ara=4 nux=7 nuy=7 nuz=1 fill
3 3 3 3 3 3 3
4 5 3 3 3 5 3
4 4 4 3 3 3 3
4 4 4 5 3 3 3
4 4 4 4 3 3 3
4 5 4 4 4 5 3
4 4 4 4 4 4 4 end fill
ara=5 nux=7 nuy=7 nuz=1 fill
4 4 4 4 4 4 3
4 5 4 4 4 5 3
4 4 4 4 4 3 3
4 4 4 5 3 3 3
4 4 3 3 3 3 3
4 5 3 3 3 5 3
4 3 3 3 3 3 3 end fill
ara=6 nux=7 nuy=7 nuz=1 fill
3 4 4 4 4 4 4
3 5 4 4 4 5 4
3 3 4 4 4 4 4
3 3 3 5 4 4 4
3 3 3 3 3 4 4
3 5 3 3 3 5 4
3 3 3 3 3 3 4 end fill
'
ara=7 nux=2 nuy=2 nuz=1 fill
8 9
7 6 end fill
end array
read bounds all=void end bounds
end data
end kenova
endh]h/X=starbucs
CE 14x14 assembly 4x4 array - horizontal burnup gradient
ce_v7
read comp
' UO2 Fuel Rod 3.038 wt %
uo2 1 den=10.045 1 273
92234 0.027 92235 3.038 92236 0.014 92238 96.921 end
'Zircalloy
arbmzirc 6.44 4 0 0 1 40000 97.91 26000 0.5 50116 0.86 50120 0.73 2 1 620 end
'Water
h2o 3 1 end
end comp
read celldata
latticecell squarepitch pitch=1.473 3 fueld=0.968 1 cladd=1.118 2 gapd=0.985 0 end
end
end celldata
read control
arp=ce14x14
nax=18
axp=
0.67053 0.93322 1.02433 1.05329 1.06026 1.06185
1.06215 1.06249 1.06312 1.06408 1.06541 1.06702
1.06836 1.06760 1.05918 1.02515 0.92262 0.66935 end
nhz= 2
hzp= 0.9 1.1 end
nuc=
u-234 u-235 u-236 u-238 pu-238 pu-239 pu-240
pu-241 pu-242 am-241 am-242m am-243 np-237 end
end control
read hist
power=28.00 burn=520.833 nlib=2 down=80 end
power=28.00 burn=520.833 nlib=2 down=80 end
power=28.00 burn=520.833 nlib=2 down=-1865 end
end hist
read kenova
'*************************************************************
'* materials
'* 101 = uo2, lower axial region, low burnup region
'* 118 = uo2, upper axial region, low burnup region
'* 201 = uo2, lower axial region, high burnup region
'* 218 = uo2, upper axial region, high burnup region
'* 2 = Zircaloy
'* 3 = Water
'*************************************************************
read param
tme=10000 gen=510 nsk=10 npg=1000
end parm
read geom
' Fuel Pin, Low Burnup Region
unit 1
cylinder 101 1 0.484 -162.53 -182.85
cylinder 102 1 0.484 -142.22 -182.85
cylinder 103 1 0.484 -121.90 -182.85
cylinder 104 1 0.484 -101.58 -182.85
cylinder 105 1 0.484 -81.27 -182.85
cylinder 106 1 0.484 -60.95 -182.85
cylinder 107 1 0.484 -40.63 -182.85
cylinder 108 1 0.484 -20.32 -182.85
cylinder 109 1 0.484 0.00 -182.85
cylinder 110 1 0.484 20.32 -182.85
cylinder 111 1 0.484 40.63 -182.85
cylinder 112 1 0.484 60.95 -182.85
cylinder 113 1 0.484 81.27 -182.85
cylinder 114 1 0.484 101.58 -182.85
cylinder 115 1 0.484 121.90 -182.85
cylinder 116 1 0.484 142.22 -182.85
cylinder 117 1 0.484 162.53 -182.85
cylinder 118 1 0.484 182.85 -182.85
cylinder 0 1 0.4925 182.85 -182.85
cylinder 2 1 0.559 182.85 -182.85
cuboid 3 1 4p0.7365 182.85 -182.85
'
' Fuel Pin, High Burnup Region
unit 2
cylinder 201 1 0.484 -162.53 -182.85
cylinder 202 1 0.484 -142.22 -182.85
cylinder 203 1 0.484 -121.90 -182.85
cylinder 204 1 0.484 -101.58 -182.85
cylinder 205 1 0.484 -81.27 -182.85
cylinder 206 1 0.484 -60.95 -182.85
cylinder 207 1 0.484 -40.63 -182.85
cylinder 208 1 0.484 -20.32 -182.85
cylinder 209 1 0.484 0.00 -182.85
cylinder 210 1 0.484 20.32 -182.85
cylinder 211 1 0.484 40.63 -182.85
cylinder 212 1 0.484 60.95 -182.85
cylinder 213 1 0.484 81.27 -182.85
cylinder 214 1 0.484 101.58 -182.85
cylinder 215 1 0.484 121.90 -182.85
cylinder 216 1 0.484 142.22 -182.85
cylinder 217 1 0.484 162.53 -182.85
cylinder 218 1 0.484 182.85 -182.85
cylinder 0 1 0.4925 182.85 -182.85
cylinder 2 1 0.559 182.85 -182.85
cuboid 3 1 4p0.7365 182.85 -182.85
'
' 2 x 2 Array of Lower Burnup Fuel Pins
unit 3
array 1 3*0
'
' 2 x 2 Array of Higher Burnup Fuel Pins
unit 4
array 2 3*0
'
' Large Water Hole
unit 5
cylinder 3 1 1.3140 182.85 -182.85
cylinder 2 1 1.4160 182.85 -182.85
cuboid 3 1 4p1.473 182.85 -182.85
'
' Assembly 1 Unit
unit 6
array 3 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly 2 Unit
unit 7
array 4 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly 3 Unit
unit 8
array 5 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly 4 Unit
unit 9
array 6 -10.311 -10.311 -182.85
cuboid 3 1 4p11.390 182.85 -182.85
'
' Assembly Array (2 x 2)
global
unit 10
array 7 3*0
reflector 3 1 6r30.0 1
end geom
read array
ara=1 nux=2 nuy=2 nuz=1 fill
1 1
1 1 end fill
ara=2 nux=2 nuy=2 nuz=1 fill
2 2
2 2 end fill
ara=3 nux=7 nuy=7 nuz=1 fill
3 3 3 3 3 3 3
3 5 3 3 3 5 4
3 3 3 3 4 4 4
3 3 3 5 4 4 4
3 3 3 4 4 4 4
3 5 4 4 4 5 4
4 4 4 4 4 4 4 end fill
ara=4 nux=7 nuy=7 nuz=1 fill
3 3 3 3 3 3 3
4 5 3 3 3 5 3
4 4 4 3 3 3 3
4 4 4 5 3 3 3
4 4 4 4 3 3 3
4 5 4 4 4 5 3
4 4 4 4 4 4 4 end fill
ara=5 nux=7 nuy=7 nuz=1 fill
4 4 4 4 4 4 3
4 5 4 4 4 5 3
4 4 4 4 4 3 3
4 4 4 5 3 3 3
4 4 3 3 3 3 3
4 5 3 3 3 5 3
4 3 3 3 3 3 3 end fill
ara=6 nux=7 nuy=7 nuz=1 fill
3 4 4 4 4 4 4
3 5 4 4 4 5 4
3 3 4 4 4 4 4
3 3 3 5 4 4 4
3 3 3 3 3 4 4
3 5 3 3 3 5 4
3 3 3 3 3 3 4 end fill
'
ara=7 nux=2 nuy=2 nuz=1 fill
8 9
7 6 end fill
end array
read bounds all=void end bounds
end data
end kenova
end}(hhh jQubah}(h]h]h]h]h]jjj;JjJ}uhjh!jIhMh jQubeh}(h] list2-3-5ah]jDJah] list2-3-5ah]h]
literal_blockuhjJh jPhhh!hhNubh)}(h
.. _fig2-3-7:h]h}(h]h]h]h]h]hfig2-3-7uhh
hM&h jPhhh!jIubj)}(hhh](j)}(h.. figure:: figs/STARBUCS/fig7.png
:align: center
:width: 600
Plot of the 2 x 2 array of CE 14 14 assemblies with burnup gradient.
h]h}(h]h]h]h]h]width600urifigs/STARBUCS/fig7.pngj}jjQsuhjh jQh!jIhM ubj)}(hEPlot of the 2 x 2 array of CE 14 14 assemblies with burnup gradient.h]h/EPlot of the 2 x 2 array of CE 14 14 assemblies with burnup gradient.}(hjQh jQubah}(h]h]h]h]h]uhjh!jIhM h jQubeh}(h](id97jQeh]h]fig2-3-7ah]h]jcenteruhjhM h jPhhh!jIj}jQjQsj}jQjQsubeh}(h]sample-problem-5ah]h]sample problem 5ah]h]uhh#h juLhhh!jIhMubjIeh}(h]id41ah]h]h]sample problemsah]uhh#h h$)}(hhh](h))}(h^STARBUCS: A Scale Control Module for Automated Criticality Safety Analyses Using Burnup Credith]h/^STARBUCS: A Scale Control Module for Automated Criticality Safety Analyses Using Burnup Credit}(hjRh jRhhh!NhNubah}(h]h]h]h]h]uhh(h jRhhh!jIhKubh;)}(h*G. Radulescu and I. C. Gauld*h]h)}(hj#Rh]h/G. Radulescu and I. C. Gauld}(hhh j%Rubah}(h]h]h]h]h]uhhh j!Rubah}(h]h]h]h]h]uhh:h!jIhKh jRhhubh;)}(hXSTARBUCS is an analysis sequence in SCALE for automating criticality
safety and burnup loading curve analyses of spent fuel systems employing
burnup credit. STARBUCS requires only the fresh fuel composition, an
irradiation history, and the KENO model for a spent fuel configuration
to be provided in an input file. It automatically performs all necessary
calculations to determine spent fuel compositions, self-shielded cross
sections, and the *k*\ :sub:`eff` of the spent fuel configuration. In addition,
for burnup loading curve analyses, STARBUCS performs iterative
calculations to search for initial fuel enrichments that result in an
upper subcritical limit. STARBUCS allows the user to simulate axial- and
horizontal-burnup gradients in a spent fuel assembly, select the
specific actinides and/or fission products that are to be included in
the criticality analysis, and apply isotopic correction factors to the
predicted spent fuel nuclide inventory to account for calculational bias
and uncertainties. A depletion analysis calculation for each of the
burnup-dependent regions of a spent fuel assembly, or any other system
containing spent nuclear fuel, is performed using the ORIGEN-ARP
sequence of SCALE. For criticality safety calculations employing
multigroup cross section data, the spent fuel compositions are used to
generate resonance self-shielded cross sections for each region of the
problem. The region dependent nuclide concentrations and cross sections
are applied in a three-dimensional criticality safety calculation using
the KENO code. Both KENO V.a and KENO-VI criticality codes are supported
for single criticality safety calculations using burnup credit, but only
KENO V.a can be used in criticality calculations for burnup loading
curve analyses. Although STARBUCS was developed specifically to address
the burnup-credit analysis needs for spent fuel transport and storage
applications, it provides sufficient flexibility to allow criticality
safety assessments involving many different potential configurations of
UO\ :sub:`2` spent nuclear fuel.h](h/XSTARBUCS is an analysis sequence in SCALE for automating criticality
safety and burnup loading curve analyses of spent fuel systems employing
burnup credit. STARBUCS requires only the fresh fuel composition, an
irradiation history, and the KENO model for a spent fuel configuration
to be provided in an input file. It automatically performs all necessary
calculations to determine spent fuel compositions, self-shielded cross
sections, and the }(hXSTARBUCS is an analysis sequence in SCALE for automating criticality
safety and burnup loading curve analyses of spent fuel systems employing
burnup credit. STARBUCS requires only the fresh fuel composition, an
irradiation history, and the KENO model for a spent fuel configuration
to be provided in an input file. It automatically performs all necessary
calculations to determine spent fuel compositions, self-shielded cross
sections, and the h j8Rhhh!NhNubh)}(h*k*h]h/k}(hhh jARubah}(h]h]h]h]h]uhhh j8Rubh/ }(h\ h j8Rhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jTRubah}(h]h]h]h]h]uhjh j8Rubh/X8 of the spent fuel configuration. In addition,
for burnup loading curve analyses, STARBUCS performs iterative
calculations to search for initial fuel enrichments that result in an
upper subcritical limit. STARBUCS allows the user to simulate axial- and
horizontal-burnup gradients in a spent fuel assembly, select the
specific actinides and/or fission products that are to be included in
the criticality analysis, and apply isotopic correction factors to the
predicted spent fuel nuclide inventory to account for calculational bias
and uncertainties. A depletion analysis calculation for each of the
burnup-dependent regions of a spent fuel assembly, or any other system
containing spent nuclear fuel, is performed using the ORIGEN-ARP
sequence of SCALE. For criticality safety calculations employing
multigroup cross section data, the spent fuel compositions are used to
generate resonance self-shielded cross sections for each region of the
problem. The region dependent nuclide concentrations and cross sections
are applied in a three-dimensional criticality safety calculation using
the KENO code. Both KENO V.a and KENO-VI criticality codes are supported
for single criticality safety calculations using burnup credit, but only
KENO V.a can be used in criticality calculations for burnup loading
curve analyses. Although STARBUCS was developed specifically to address
the burnup-credit analysis needs for spent fuel transport and storage
applications, it provides sufficient flexibility to allow criticality
safety assessments involving many different potential configurations of
UO }(hX8 of the spent fuel configuration. In addition,
for burnup loading curve analyses, STARBUCS performs iterative
calculations to search for initial fuel enrichments that result in an
upper subcritical limit. STARBUCS allows the user to simulate axial- and
horizontal-burnup gradients in a spent fuel assembly, select the
specific actinides and/or fission products that are to be included in
the criticality analysis, and apply isotopic correction factors to the
predicted spent fuel nuclide inventory to account for calculational bias
and uncertainties. A depletion analysis calculation for each of the
burnup-dependent regions of a spent fuel assembly, or any other system
containing spent nuclear fuel, is performed using the ORIGEN-ARP
sequence of SCALE. For criticality safety calculations employing
multigroup cross section data, the spent fuel compositions are used to
generate resonance self-shielded cross sections for each region of the
problem. The region dependent nuclide concentrations and cross sections
are applied in a three-dimensional criticality safety calculation using
the KENO code. Both KENO V.a and KENO-VI criticality codes are supported
for single criticality safety calculations using burnup credit, but only
KENO V.a can be used in criticality calculations for burnup loading
curve analyses. Although STARBUCS was developed specifically to address
the burnup-credit analysis needs for spent fuel transport and storage
applications, it provides sufficient flexibility to allow criticality
safety assessments involving many different potential configurations of
UO\ h j8Rhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jgRubah}(h]h]h]h]h]uhjh j8Rubh/ spent nuclear fuel.}(h spent nuclear fuel.h j8Rhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKh jRhhubh$)}(hhh](h))}(hIntroductionh]h/Introduction}(hjRh jRhhh!NhNubah}(h]h]h]h]h]uhh(h jRhhh!jIhK(ubh;)}(hXThe U.S. Nuclear Regulatory Commission (NRC) issued Revision 3 of the
Interim Staff Guidance 8 (ISG-8) (:cite:`us_nuclear_regulatory_commission_burnup_2012`) on burnup credit in
September, 2012. ISG-8 provides guidance on the application of
burnup-credit in criticality safety analyses for pressurized-water
reactor (PWR) spent fuel in transportation and storage casks. Burnup
credit is the concept of taking credit for the reduction in reactivity
in spent fuel due to burnup. The reduction in reactivity that occurs
with fuel burnup is due to the change in concentration (net reduction)
of fissile nuclides and the production of actinide and fission-product
neutron absorbers. In contrast to criticality safety analyses that
employ a fresh-fuel assumption (i.e., conservatively assuming
unirradiated fuel compositions), credit for burnup requires the
prediction of both fissile material and absorber nuclide concentrations
in spent nuclear fuel (SNF) and consideration of many burnup-related
phenomena, in addition to the criticality issues.h](h/kThe U.S. Nuclear Regulatory Commission (NRC) issued Revision 3 of the
Interim Staff Guidance 8 (ISG-8) (}(hkThe U.S. Nuclear Regulatory Commission (NRC) issued Revision 3 of the
Interim Staff Guidance 8 (ISG-8) (h jRhhh!NhNubh_)}(h,us_nuclear_regulatory_commission_burnup_2012h]he)}(hjRh]h/.[us_nuclear_regulatory_commission_burnup_2012]}(hhh jRubah}(h]h]h]h]h]uhhdh jRubah}(h]id37ah]hwah]h]h] refdomainh|reftypeh~ reftargetjRrefwarnsupport_smartquotesuhh^h!jIhK*h jRhhubh/Xv) on burnup credit in
September, 2012. ISG-8 provides guidance on the application of
burnup-credit in criticality safety analyses for pressurized-water
reactor (PWR) spent fuel in transportation and storage casks. Burnup
credit is the concept of taking credit for the reduction in reactivity
in spent fuel due to burnup. The reduction in reactivity that occurs
with fuel burnup is due to the change in concentration (net reduction)
of fissile nuclides and the production of actinide and fission-product
neutron absorbers. In contrast to criticality safety analyses that
employ a fresh-fuel assumption (i.e., conservatively assuming
unirradiated fuel compositions), credit for burnup requires the
prediction of both fissile material and absorber nuclide concentrations
in spent nuclear fuel (SNF) and consideration of many burnup-related
phenomena, in addition to the criticality issues.}(hXv) on burnup credit in
September, 2012. ISG-8 provides guidance on the application of
burnup-credit in criticality safety analyses for pressurized-water
reactor (PWR) spent fuel in transportation and storage casks. Burnup
credit is the concept of taking credit for the reduction in reactivity
in spent fuel due to burnup. The reduction in reactivity that occurs
with fuel burnup is due to the change in concentration (net reduction)
of fissile nuclides and the production of actinide and fission-product
neutron absorbers. In contrast to criticality safety analyses that
employ a fresh-fuel assumption (i.e., conservatively assuming
unirradiated fuel compositions), credit for burnup requires the
prediction of both fissile material and absorber nuclide concentrations
in spent nuclear fuel (SNF) and consideration of many burnup-related
phenomena, in addition to the criticality issues.h jRhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhK*h jRhhubh;)}(hXConsideration of the depletion aspects in the criticality assessment of
SNF places an increasing reliance on computational tools and methods,
and significantly increases the overall complexity of the criticality
safety analysis. The use of spent fuel nuclide concentrations in the
criticality evaluation also necessitates consideration of many
additional sources of uncertainty associated with fuel depletion. ISG-8
highlights, for example, the need for applicants employing burnup credit
in criticality safety assessments to address the axial and horizontal
variation of the burnup within a spent fuel assembly, uncertainties and
bias in the nuclide predictions, and the additional reactivity margin
available from fission products and actinides not credited in the
licensing basis.h]h/XConsideration of the depletion aspects in the criticality assessment of
SNF places an increasing reliance on computational tools and methods,
and significantly increases the overall complexity of the criticality
safety analysis. The use of spent fuel nuclide concentrations in the
criticality evaluation also necessitates consideration of many
additional sources of uncertainty associated with fuel depletion. ISG-8
highlights, for example, the need for applicants employing burnup credit
in criticality safety assessments to address the axial and horizontal
variation of the burnup within a spent fuel assembly, uncertainties and
bias in the nuclide predictions, and the additional reactivity margin
available from fission products and actinides not credited in the
licensing basis.}(hjRh jRhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhK:h jRhhubh;)}(hXTo assist in performing and reviewing criticality safety assessments of
transport and storage casks that apply burnup credit, a new control
sequence called STARBUCS (**St**\ andardized **A**\ nalysis of
**R**\ eactivity for **Bu**\ rnup **C**\ redit using **S**\ CALE) was
developed in SCALE 5. STARBUCS automates the generation of
spatially-varying nuclide compositions in a spent fuel assembly, and
applies the assembly compositions in a three-dimensional (3-D)
Monte Carlo analysis of the system. STARBUCS automatically prepares
input files for each of the modules in the sequence, executes the
modules through the SCALE driver, and performs all flow control, module
interface, and data management functions. The STARBUCS sequence uses
well-established code modules currently available in SCALE. STARBUCS
also performs iterations over a range of initial fuel enrichments to
determine the initial enrichments below which UO\ :sub:`2` commercial
spent fuel may be loaded in a transport/storage cask for specified
burnup values. With this capability, STARBUCS assists in generating
burnup loading curves for criticality safety analyses of spent fuel in
transport and storage casks.h](h/To assist in performing and reviewing criticality safety assessments of
transport and storage casks that apply burnup credit, a new control
sequence called STARBUCS (}(hTo assist in performing and reviewing criticality safety assessments of
transport and storage casks that apply burnup credit, a new control
sequence called STARBUCS (h jRhhh!NhNubhA)}(h**St**h]h/St}(hhh jRubah}(h]h]h]h]h]uhh@h jRubh/
andardized }(h
\ andardized h jRhhh!NhNubhA)}(h**A**h]h/A}(hhh jRubah}(h]h]h]h]h]uhh@h jRubh/
nalysis of
}(h
\ nalysis of
h jRhhh!NhNubhA)}(h**R**h]h/R}(hhh jRubah}(h]h]h]h]h]uhh@h jRubh/ eactivity for }(h\ eactivity for h jRhhh!NhNubhA)}(h**Bu**h]h/Bu}(hhh jSubah}(h]h]h]h]h]uhh@h jRubh/ rnup }(h\ rnup h jRhhh!NhNubhA)}(h**C**h]h/C}(hhh j%Subah}(h]h]h]h]h]uhh@h jRubh/ redit using }(h\ redit using h jRhhh!NhNubhA)}(h**S**h]h/S}(hhh j8Subah}(h]h]h]h]h]uhh@h jRubh/X CALE) was
developed in SCALE 5. STARBUCS automates the generation of
spatially-varying nuclide compositions in a spent fuel assembly, and
applies the assembly compositions in a three-dimensional (3-D)
Monte Carlo analysis of the system. STARBUCS automatically prepares
input files for each of the modules in the sequence, executes the
modules through the SCALE driver, and performs all flow control, module
interface, and data management functions. The STARBUCS sequence uses
well-established code modules currently available in SCALE. STARBUCS
also performs iterations over a range of initial fuel enrichments to
determine the initial enrichments below which UO }(hX\ CALE) was
developed in SCALE 5. STARBUCS automates the generation of
spatially-varying nuclide compositions in a spent fuel assembly, and
applies the assembly compositions in a three-dimensional (3-D)
Monte Carlo analysis of the system. STARBUCS automatically prepares
input files for each of the modules in the sequence, executes the
modules through the SCALE driver, and performs all flow control, module
interface, and data management functions. The STARBUCS sequence uses
well-established code modules currently available in SCALE. STARBUCS
also performs iterations over a range of initial fuel enrichments to
determine the initial enrichments below which UO\ h jRhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jKSubah}(h]h]h]h]h]uhjh jRubh/ commercial
spent fuel may be loaded in a transport/storage cask for specified
burnup values. With this capability, STARBUCS assists in generating
burnup loading curves for criticality safety analyses of spent fuel in
transport and storage casks.}(h commercial
spent fuel may be loaded in a transport/storage cask for specified
burnup values. With this capability, STARBUCS assists in generating
burnup loading curves for criticality safety analyses of spent fuel in
transport and storage casks.h jRhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKGh jRhhubh;)}(hXThe STARBUCS sequence automates the depletion calculations using the
ORIGEN-ARP methodology to perform a series of cross section preparation
and depletion calculations to generate a comprehensive set of spent fuel
isotopic inventories for each spatially-varying burnup region of an
assembly. The spent fuel nuclide concentrations are subsequently input
to either CSAS5 or CSAS6 to and perform a criticality calculation of the
system using the KENO V.a or KENO-VI code, respectively, to determine
the neutron multiplication factor (*k*\ :sub:`eff`) for the system. Only
minimal input is required by the user to perform a typical burnup-credit
analysis. The user can specify the assembly-average irradiation history,
the axial density variation of the reactor moderator, the axial- and
horizontal-burnup profile, and the nuclides that are to be applied in
the criticality safety analysis. Nuclide correction factors may also be
applied to the predicted concentrations to account for known bias and/or
uncertainty in the predicted SNF compositions.h](h/XThe STARBUCS sequence automates the depletion calculations using the
ORIGEN-ARP methodology to perform a series of cross section preparation
and depletion calculations to generate a comprehensive set of spent fuel
isotopic inventories for each spatially-varying burnup region of an
assembly. The spent fuel nuclide concentrations are subsequently input
to either CSAS5 or CSAS6 to and perform a criticality calculation of the
system using the KENO V.a or KENO-VI code, respectively, to determine
the neutron multiplication factor (}(hXThe STARBUCS sequence automates the depletion calculations using the
ORIGEN-ARP methodology to perform a series of cross section preparation
and depletion calculations to generate a comprehensive set of spent fuel
isotopic inventories for each spatially-varying burnup region of an
assembly. The spent fuel nuclide concentrations are subsequently input
to either CSAS5 or CSAS6 to and perform a criticality calculation of the
system using the KENO V.a or KENO-VI code, respectively, to determine
the neutron multiplication factor (Bh jdShhh!NhNubh)}(h*k*h]h/k}(hhh jmSubah}(h]h]h]h]h]uhhh jdSubh/ }(h\ h jdShhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jSubah}(h]h]h]h]h]uhjh jdSubh/X) for the system. Only
minimal input is required by the user to perform a typical burnup-credit
analysis. The user can specify the assembly-average irradiation history,
the axial density variation of the reactor moderator, the axial- and
horizontal-burnup profile, and the nuclides that are to be applied in
the criticality safety analysis. Nuclide correction factors may also be
applied to the predicted concentrations to account for known bias and/or
uncertainty in the predicted SNF compositions.}(hX) for the system. Only
minimal input is required by the user to perform a typical burnup-credit
analysis. The user can specify the assembly-average irradiation history,
the axial density variation of the reactor moderator, the axial- and
horizontal-burnup profile, and the nuclides that are to be applied in
the criticality safety analysis. Nuclide correction factors may also be
applied to the predicted concentrations to account for known bias and/or
uncertainty in the predicted SNF compositions.h jdShhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKZh jRhhubeh}(h]id36ah]h]h]introductionah]uhh#h jRhhh!jIhK(jmKubh$)}(hhh](h))}(hMethodologyh]h/Methodology}(hjSh jShhh!NhNubah}(h]h]h]h]h]uhh(h jShhh!jIhKkubh;)}(hXnThe STARBUCS control module is a burnup-credit sequence designed to
perform 3-D Monte Carlo criticality safety calculations that include the
effects of spatially-varying burnup in SNF configurations. STARBUCS
offers two options: either perform a single criticality safety
calculation with burnup credit or perform iterative calculations for
burnup loading curve analyses of commercial UO\ :sub:`2` spent fuels.
The sequence contains a set of instructions designed to automatically
process input data, execute code modules currently available in SCALE
for depletion, resonance cross section, and criticality calculations. In
addition, for burnup loading curve analyses, STARBUCS checks whether
*k*\ :sub:`eff` converges to a user-provided upper subcritical limit, adjusts
the initial fuel enrichment using the least squares method, and repeats
the sequence until either convergence is achieved or determine that no
solution can be found. The overall program structures and flow for a
single criticality calculation and for burnup loading curve calculations
are illustrated in :numref:`fig2-3-1` and :numref:`fig2-3-2`, respectively.h](h/XThe STARBUCS control module is a burnup-credit sequence designed to
perform 3-D Monte Carlo criticality safety calculations that include the
effects of spatially-varying burnup in SNF configurations. STARBUCS
offers two options: either perform a single criticality safety
calculation with burnup credit or perform iterative calculations for
burnup loading curve analyses of commercial UO }(hXThe STARBUCS control module is a burnup-credit sequence designed to
perform 3-D Monte Carlo criticality safety calculations that include the
effects of spatially-varying burnup in SNF configurations. STARBUCS
offers two options: either perform a single criticality safety
calculation with burnup credit or perform iterative calculations for
burnup loading curve analyses of commercial UO\ h jShhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jSubah}(h]h]h]h]h]uhjh jSubh/X* spent fuels.
The sequence contains a set of instructions designed to automatically
process input data, execute code modules currently available in SCALE
for depletion, resonance cross section, and criticality calculations. In
addition, for burnup loading curve analyses, STARBUCS checks whether
}(hX* spent fuels.
The sequence contains a set of instructions designed to automatically
process input data, execute code modules currently available in SCALE
for depletion, resonance cross section, and criticality calculations. In
addition, for burnup loading curve analyses, STARBUCS checks whether
h jShhh!NhNubh)}(h*k*h]h/k}(hhh jSubah}(h]h]h]h]h]uhhh jSubh/ }(h\ h jShhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jSubah}(h]h]h]h]h]uhjh jSubh/Xo converges to a user-provided upper subcritical limit, adjusts
the initial fuel enrichment using the least squares method, and repeats
the sequence until either convergence is achieved or determine that no
solution can be found. The overall program structures and flow for a
single criticality calculation and for burnup loading curve calculations
are illustrated in }(hXo converges to a user-provided upper subcritical limit, adjusts
the initial fuel enrichment using the least squares method, and repeats
the sequence until either convergence is achieved or determine that no
solution can be found. The overall program structures and flow for a
single criticality calculation and for burnup loading curve calculations
are illustrated in h jShhh!NhNubh_)}(h:numref:`fig2-3-1`h]j)}(hjSh]h/fig2-3-1}(hhh jSubah}(h]h](jstd
std-numrefeh]h]h]uhjh jSubah}(h]h]h]h]h]refdocj refdomainjTreftypenumrefrefexplicitrefwarnjfig2-3-1uhh^h!jIhKmh jSubh/ and }(h and h jShhh!NhNubh_)}(h:numref:`fig2-3-2`h]j)}(hjTh]h/fig2-3-2}(hhh jTubah}(h]h](jstd
std-numrefeh]h]h]uhjh jTubah}(h]h]h]h]h]refdocj refdomainj'Treftypenumrefrefexplicitrefwarnjfig2-3-2uhh^h!jIhKmh jSubh/, respectively.}(h, respectively.h jShhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKmh jShhubh;)}(hXThe sequence uses well-established code modules currently available in
the SCALE code system. These modules include ARP and ORIGEN to perform
the depletion analysis phase of the calculations. ORIGEN-ARP is a
sequence within the SCALE system that serves as a faster alternative to
the TRITON depletion sequence of SCALE to perform point-irradiation
calculations with the ORIGEN code using problem-dependent cross
sections. ARP uses an algorithm that enables the generation of cross
section libraries for the ORIGEN code by interpolation over pregenerated
cross section libraries. The ORIGEN code performs isotopic generation
and depletion calculations to obtain the spent fuel nuclide
compositions. For criticality safety calculations using multigroup cross
section data, problem dependent cross sections are processed with the
resonance self-shielding capabilities of XSProc using the
region-dependent compositions from the depletion analyses. Finally, the
region dependent nuclide concentrations and cross sections are applied
in a 3-D criticality calculation for the system using either KENO V.a or
KENO-VI to calculate the *k*\ :sub:`eff` value.h](h/XiThe sequence uses well-established code modules currently available in
the SCALE code system. These modules include ARP and ORIGEN to perform
the depletion analysis phase of the calculations. ORIGEN-ARP is a
sequence within the SCALE system that serves as a faster alternative to
the TRITON depletion sequence of SCALE to perform point-irradiation
calculations with the ORIGEN code using problem-dependent cross
sections. ARP uses an algorithm that enables the generation of cross
section libraries for the ORIGEN code by interpolation over pregenerated
cross section libraries. The ORIGEN code performs isotopic generation
and depletion calculations to obtain the spent fuel nuclide
compositions. For criticality safety calculations using multigroup cross
section data, problem dependent cross sections are processed with the
resonance self-shielding capabilities of XSProc using the
region-dependent compositions from the depletion analyses. Finally, the
region dependent nuclide concentrations and cross sections are applied
in a 3-D criticality calculation for the system using either KENO V.a or
KENO-VI to calculate the }(hXiThe sequence uses well-established code modules currently available in
the SCALE code system. These modules include ARP and ORIGEN to perform
the depletion analysis phase of the calculations. ORIGEN-ARP is a
sequence within the SCALE system that serves as a faster alternative to
the TRITON depletion sequence of SCALE to perform point-irradiation
calculations with the ORIGEN code using problem-dependent cross
sections. ARP uses an algorithm that enables the generation of cross
section libraries for the ORIGEN code by interpolation over pregenerated
cross section libraries. The ORIGEN code performs isotopic generation
and depletion calculations to obtain the spent fuel nuclide
compositions. For criticality safety calculations using multigroup cross
section data, problem dependent cross sections are processed with the
resonance self-shielding capabilities of XSProc using the
region-dependent compositions from the depletion analyses. Finally, the
region dependent nuclide concentrations and cross sections are applied
in a 3-D criticality calculation for the system using either KENO V.a or
KENO-VI to calculate the h jDThhh!NhNubh)}(h*k*h]h/k}(hhh jMTubah}(h]h]h]h]h]uhhh jDTubh/ }(h\ h jDThhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j`Tubah}(h]h]h]h]h]uhjh jDTubh/ value.}(h value.h jDThhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhK~h jShhubh;)}(hXThe ORIGEN-ARP depletion analysis methodology represents a significant
increase in computational speed as compared to equivalent calculations
performed using the SCALE depletion analysis sequences that use
two-dimensional transport methods, with virtually no sacrifice in
accuracy. ARP uses an algorithm that enables the generation of cross
sections for the ORIGEN code by interpolating on cross sections
available in pre-generated data libraries. For uranium-based fuels the
interpolation parameters available are initial fuel enrichment, burnup
and, optionally, moderator density. STARBUCS creates input files for ARP
and ORIGEN for each burnup-dependent region of an assembly and
calculates the spent fuel nuclide concentrations for the region using a
user-specified assembly irradiation history, cooling time, and burnup
profiles. The ORIGEN libraries must be available in advance of a
STARBUCS burnup-credit calculation. These libraries may be created using
TRITON. The libraries include the effects of assembly design and
operating conditions on the neutron cross sections used in the burnup
analysis. Several ORIGEN libraries are distributed in the SCALE code
system and can be applied in a STARBUCS analysis. Alternatively, a user
may create a specific ORIGEN library for other assembly types or
operating conditions not available in the default libraries. The
generation of ORIGEN reactor libraries is discussed in the ORIGEN
Reactor Libraries chapter.h]h/XThe ORIGEN-ARP depletion analysis methodology represents a significant
increase in computational speed as compared to equivalent calculations
performed using the SCALE depletion analysis sequences that use
two-dimensional transport methods, with virtually no sacrifice in
accuracy. ARP uses an algorithm that enables the generation of cross
sections for the ORIGEN code by interpolating on cross sections
available in pre-generated data libraries. For uranium-based fuels the
interpolation parameters available are initial fuel enrichment, burnup
and, optionally, moderator density. STARBUCS creates input files for ARP
and ORIGEN for each burnup-dependent region of an assembly and
calculates the spent fuel nuclide concentrations for the region using a
user-specified assembly irradiation history, cooling time, and burnup
profiles. The ORIGEN libraries must be available in advance of a
STARBUCS burnup-credit calculation. These libraries may be created using
TRITON. The libraries include the effects of assembly design and
operating conditions on the neutron cross sections used in the burnup
analysis. Several ORIGEN libraries are distributed in the SCALE code
system and can be applied in a STARBUCS analysis. Alternatively, a user
may create a specific ORIGEN library for other assembly types or
operating conditions not available in the default libraries. The
generation of ORIGEN reactor libraries is discussed in the ORIGEN
Reactor Libraries chapter.}(hj{Th jyThhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jShhubh;)}(hXThe depletion phase of the analysis is performed using ARP and ORIGEN to
calculate the compositions of each discrete fuel region (axial or
horizontal). After a single ORIGEN-ARP depletion calculation is
completed, control is passed back to the STARBUCS module which reads the
spent fuel nuclide inventories generated by ORIGEN, saves them, prepares
the ARP and ORIGEN input files for the next burnup region, and executes
the codes in sequence. This cycle continues until the fuel compositions
for all axial and horizontal regions have been calculated and saved,
completing the depletion phase of the analysis. The depletion
calculations for each axial and radial zone are performed using an
initial fuel basis of 1 MTHM (10:sup:`6` g heavy metal).h](h/XThe depletion phase of the analysis is performed using ARP and ORIGEN to
calculate the compositions of each discrete fuel region (axial or
horizontal). After a single ORIGEN-ARP depletion calculation is
completed, control is passed back to the STARBUCS module which reads the
spent fuel nuclide inventories generated by ORIGEN, saves them, prepares
the ARP and ORIGEN input files for the next burnup region, and executes
the codes in sequence. This cycle continues until the fuel compositions
for all axial and horizontal regions have been calculated and saved,
completing the depletion phase of the analysis. The depletion
calculations for each axial and radial zone are performed using an
initial fuel basis of 1 MTHM (10:sup:}(hXThe depletion phase of the analysis is performed using ARP and ORIGEN to
calculate the compositions of each discrete fuel region (axial or
horizontal). After a single ORIGEN-ARP depletion calculation is
completed, control is passed back to the STARBUCS module which reads the
spent fuel nuclide inventories generated by ORIGEN, saves them, prepares
the ARP and ORIGEN input files for the next burnup region, and executes
the codes in sequence. This cycle continues until the fuel compositions
for all axial and horizontal regions have been calculated and saved,
completing the depletion phase of the analysis. The depletion
calculations for each axial and radial zone are performed using an
initial fuel basis of 1 MTHM (10:sup:h jThhh!NhNubjV)}(h`6`h]h/6}(hhh jTubah}(h]h]h]h]h]uhjUh jTubh/ g heavy metal).}(h g heavy metal).h jThhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKh jShhubh;)}(hXAfter all depletion calculations are completed, STARBUCS reads the spent
fuel nuclide inventories for all regions and prepares input for the
criticality calculation. The concentrations of all nuclides in the
ORIGEN depletion analysis are converted from gram-atom units (per MTU)
to units of atoms/b-cm applied in the criticality calculation. The
criticality calculation is performed using the capabilities in the CSAS5
or CSAS6 control module of SCALE. Specifically, STARBUCS prepares input
for the CSAS5 module when criticality calculations are to be performed
using KENO V.a, and for the CSAS6 sequence when using KENO-VI. Note that
only the criticality safety sequence CSAS5 of SCALE can be used for
burnup loading curve calculations.h]h/XAfter all depletion calculations are completed, STARBUCS reads the spent
fuel nuclide inventories for all regions and prepares input for the
criticality calculation. The concentrations of all nuclides in the
ORIGEN depletion analysis are converted from gram-atom units (per MTU)
to units of atoms/b-cm applied in the criticality calculation. The
criticality calculation is performed using the capabilities in the CSAS5
or CSAS6 control module of SCALE. Specifically, STARBUCS prepares input
for the CSAS5 module when criticality calculations are to be performed
using KENO V.a, and for the CSAS6 sequence when using KENO-VI. Note that
only the criticality safety sequence CSAS5 of SCALE can be used for
burnup loading curve calculations.}(hjTh jThhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jShhubh;)}(hXFor burnup loading curve iterative calculations, STARBUCS employs the
search algorithm described in CSAS5 section on *Optimum
(Minimum/Maximum) Search* to determine initial fuel enrichments that
satisfy a convergence criterion for the k\ :sub:`eff` of the spent fuel
configuration. If convergence is not achieved in a search pass, the
initial fuel enrichment is automatically adjusted. This sequence repeats
until either k\ *eff* converges to an upper subcritical limit or until
the algorithm determines that a solution is not possible. The procedure
is repeated for each requested burnup value. The maximum allowable
iterations, upper subcritical limit, tolerance for convergence, and a
range of initial fuel enrichments can be set by the user. The lower and
upper enrichment bounds as well as the burnup values for spent fuel
regions must be contained within the range of enrichment and burnup
values used to generate the applicable ORIGEN library. The control
module prepares a STARBUCS input file for each search pass requesting a
single criticality calculation using the calculated spent fuel
compositions. In this input file, the burnup history data block and/or
the fuel mixture compositions are updated based on the outcome of the
search sequence. The pre-burnup compositions for the two minor uranium
isotopes, :sup:`234`\ U and :sup:`236`\ U, are updated in the STARBUCS
input file for a new pass only if they were included in the initial
input file prepared by the user. Their updated weight percentages are
based on the assumption that the mass ratios
:sup:`234`\ U/\ :sup:`235`\ U and :sup:`236`\ U/\ :sup:`235`\ U do not
change with fuel enrichment.h](h/uFor burnup loading curve iterative calculations, STARBUCS employs the
search algorithm described in CSAS5 section on }(huFor burnup loading curve iterative calculations, STARBUCS employs the
search algorithm described in CSAS5 section on h jThhh!NhNubh)}(h"*Optimum
(Minimum/Maximum) Search*h]h/ Optimum
(Minimum/Maximum) Search}(hhh jTubah}(h]h]h]h]h]uhhh jTubh/W to determine initial fuel enrichments that
satisfy a convergence criterion for the k }(hW to determine initial fuel enrichments that
satisfy a convergence criterion for the k\ h jThhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jTubah}(h]h]h]h]h]uhjh jTubh/ of the spent fuel
configuration. If convergence is not achieved in a search pass, the
initial fuel enrichment is automatically adjusted. This sequence repeats
until either k }(h of the spent fuel
configuration. If convergence is not achieved in a search pass, the
initial fuel enrichment is automatically adjusted. This sequence repeats
until either k\ h jThhh!NhNubh)}(h*eff*h]h/eff}(hhh jTubah}(h]h]h]h]h]uhhh jTubh/X{ converges to an upper subcritical limit or until
the algorithm determines that a solution is not possible. The procedure
is repeated for each requested burnup value. The maximum allowable
iterations, upper subcritical limit, tolerance for convergence, and a
range of initial fuel enrichments can be set by the user. The lower and
upper enrichment bounds as well as the burnup values for spent fuel
regions must be contained within the range of enrichment and burnup
values used to generate the applicable ORIGEN library. The control
module prepares a STARBUCS input file for each search pass requesting a
single criticality calculation using the calculated spent fuel
compositions. In this input file, the burnup history data block and/or
the fuel mixture compositions are updated based on the outcome of the
search sequence. The pre-burnup compositions for the two minor uranium
isotopes, }(hX{ converges to an upper subcritical limit or until
the algorithm determines that a solution is not possible. The procedure
is repeated for each requested burnup value. The maximum allowable
iterations, upper subcritical limit, tolerance for convergence, and a
range of initial fuel enrichments can be set by the user. The lower and
upper enrichment bounds as well as the burnup values for spent fuel
regions must be contained within the range of enrichment and burnup
values used to generate the applicable ORIGEN library. The control
module prepares a STARBUCS input file for each search pass requesting a
single criticality calculation using the calculated spent fuel
compositions. In this input file, the burnup history data block and/or
the fuel mixture compositions are updated based on the outcome of the
search sequence. The pre-burnup compositions for the two minor uranium
isotopes, h jThhh!NhNubj)}(h
:sup:`234`h]h/234}(hhh jTubah}(h]h]h]h]h]uhjh jTubh/ U and }(h\ U and h jThhh!NhNubj)}(h
:sup:`236`h]h/236}(hhh jUubah}(h]h]h]h]h]uhjh jTubh/ U, are updated in the STARBUCS
input file for a new pass only if they were included in the initial
input file prepared by the user. Their updated weight percentages are
based on the assumption that the mass ratios
}(h\ U, are updated in the STARBUCS
input file for a new pass only if they were included in the initial
input file prepared by the user. Their updated weight percentages are
based on the assumption that the mass ratios
h jThhh!NhNubj)}(h
:sup:`234`h]h/234}(hhh jUubah}(h]h]h]h]h]uhjh jTubh/ U/ }(h\ U/\ h jThhh!NhNubj)}(h
:sup:`235`h]h/235}(hhh j2Uubah}(h]h]h]h]h]uhjh jTubh/ U and }(hjUh jTubj)}(h
:sup:`236`h]h/236}(hhh jDUubah}(h]h]h]h]h]uhjh jTubh/ U/ }(hj1Uh jTubj)}(h
:sup:`235`h]h/235}(hhh jVUubah}(h]h]h]h]h]uhjh jTubh/' U do not
change with fuel enrichment.}(h'\ U do not
change with fuel enrichment.h jThhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKh jShhubh)}(h
.. _fig2-3-1:h]h}(h]h]h]h]h]hfig2-3-1uhh
hMh jShhh!jIubj)}(hhh](j)}(h.. figure:: figs/STARBUCS/fig1.png
:align: center
:width: 600
Modules and flow of STARBUCS sequence for criticality calculations.
h]h}(h]h]h]h]h]width600urifigs/STARBUCS/fig1.pngj}jjUsuhjh jzUh!jIhKubj)}(hCModules and flow of STARBUCS sequence for criticality calculations.h]h/CModules and flow of STARBUCS sequence for criticality calculations.}(hjUh jUubah}(h]h]h]h]h]uhjh!jIhKh jzUubeh}(h](id84jyUeh]h]fig2-3-1ah]h]jcenteruhjhKh jShhh!jIj}jUjoUsj}jyUjoUsubh)}(h
.. _fig2-3-2:h]h}(h]h]h]h]h]hfig2-3-2uhh
hM
h jShhh!jIubj)}(hhh](j)}(h.. figure:: figs/STARBUCS/fig2.png
:align: center
:width: 600
Modules and flow of STARBUCS sequence for burnup loading curve calculations.
h]h}(h]h]h]h]h]width600urifigs/STARBUCS/fig2.pngj}jjUsuhjh jUh!jIhKubj)}(hLModules and flow of STARBUCS sequence for burnup loading curve calculations.h]h/LModules and flow of STARBUCS sequence for burnup loading curve calculations.}(hjUh jUubah}(h]h]h]h]h]uhjh!jIhKh jUubeh}(h](id85jUeh]h]fig2-3-2ah]h]jcenteruhjhKh jShhh!jIj}jUjUsj}jUjUsubh)}(h.. _cap-and-lim:h]h}(h]h]h]h]h]hcap-and-limuhh
hMh jShhh!jIubeh}(h]methodologyah]h]methodologyah]h]uhh#h jRhhh!jIhKkubh$)}(hhh](h))}(hCapabilities and Limitationsh]h/Capabilities and Limitations}(hjUh jUhhh!NhNubah}(h]h]h]h]h]uhh(h jUhhh!jIhKubh;)}(hX|STARBUCS is designed to facilitate criticality safety analyses employing
burnup credit by automating and linking the depletion and criticality
calculations. The STARBUCS sequence has been designed to readily allow
analysts and reviewers to assess the subcritical margins associated with
many of the important phenomena that need to be evaluated in the context
of the current regulatory guidance on burnup credit. However, STARBUCS
is sufficiently general to allow virtually any configuration involving
irradiated nuclear material to be analyzed. Limitations and some of the
key capabilities of the STARBUCS sequence are described below.h]h/X|STARBUCS is designed to facilitate criticality safety analyses employing
burnup credit by automating and linking the depletion and criticality
calculations. The STARBUCS sequence has been designed to readily allow
analysts and reviewers to assess the subcritical margins associated with
many of the important phenomena that need to be evaluated in the context
of the current regulatory guidance on burnup credit. However, STARBUCS
is sufficiently general to allow virtually any configuration involving
irradiated nuclear material to be analyzed. Limitations and some of the
key capabilities of the STARBUCS sequence are described below.}(hjVh jUhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jUhhubj )}(hhh](j)}(hXSTARBUCS limitations include the use of a single UO\ :sub:`2` fuel
type and, for analyses employing multigroup cross section data, the
use of geometry configurations consisting of spent fuel rod arrays.
However, the type of spent fuel configurations that can be analyzed
is entirely general. STARBUCS can be used to perform criticality
safety assessments of individual fuel assemblies, a spent fuel cask,
a spent fuel storage pool, or any nuclear system containing
UO\ :sub:`2` irradiated nuclear fuel.
h]h;)}(hXSTARBUCS limitations include the use of a single UO\ :sub:`2` fuel
type and, for analyses employing multigroup cross section data, the
use of geometry configurations consisting of spent fuel rod arrays.
However, the type of spent fuel configurations that can be analyzed
is entirely general. STARBUCS can be used to perform criticality
safety assessments of individual fuel assemblies, a spent fuel cask,
a spent fuel storage pool, or any nuclear system containing
UO\ :sub:`2` irradiated nuclear fuel.h](h/5STARBUCS limitations include the use of a single UO }(h5STARBUCS limitations include the use of a single UO\ h jVubj)}(h:sub:`2`h]h/2}(hhh jVubah}(h]h]h]h]h]uhjh jVubh/X fuel
type and, for analyses employing multigroup cross section data, the
use of geometry configurations consisting of spent fuel rod arrays.
However, the type of spent fuel configurations that can be analyzed
is entirely general. STARBUCS can be used to perform criticality
safety assessments of individual fuel assemblies, a spent fuel cask,
a spent fuel storage pool, or any nuclear system containing
UO }(hX fuel
type and, for analyses employing multigroup cross section data, the
use of geometry configurations consisting of spent fuel rod arrays.
However, the type of spent fuel configurations that can be analyzed
is entirely general. STARBUCS can be used to perform criticality
safety assessments of individual fuel assemblies, a spent fuel cask,
a spent fuel storage pool, or any nuclear system containing
UO\ h jVubj)}(h:sub:`2`h]h/2}(hhh j0Vubah}(h]h]h]h]h]uhjh jVubh/ irradiated nuclear fuel.}(h irradiated nuclear fuel.h jVubeh}(h]h]h]h]h]uhh:h!jIhKh jVubah}(h]h]h]h]h]uhjh j
Vhhh!jIhNubj)}(hOnly the criticality safety sequence CSAS5 of SCALE can be used for
burnup loading curve calculations; therefore KENO V.a geometry
description must be available in a STARBUCS input file for burnup
loading curve calculations.
h]h;)}(hOnly the criticality safety sequence CSAS5 of SCALE can be used for
burnup loading curve calculations; therefore KENO V.a geometry
description must be available in a STARBUCS input file for burnup
loading curve calculations.h]h/Only the criticality safety sequence CSAS5 of SCALE can be used for
burnup loading curve calculations; therefore KENO V.a geometry
description must be available in a STARBUCS input file for burnup
loading curve calculations.}(hjUVh jSVubah}(h]h]h]h]h]uhh:h!jIhKh jOVubah}(h]h]h]h]h]uhjh j
Vhhh!jIhNubj)}(hXIBurnup calculations can incorporate any desired operating history.
The user may enter the specific power, cycle lengths, cycle down
time, post-irradiation cooling time, etc. The axial-water-moderator
density variation may also be specified in the depletion analysis,
provided the ORIGEN cross section library contains such data.
h]h;)}(hXHBurnup calculations can incorporate any desired operating history.
The user may enter the specific power, cycle lengths, cycle down
time, post-irradiation cooling time, etc. The axial-water-moderator
density variation may also be specified in the depletion analysis,
provided the ORIGEN cross section library contains such data.h]h/XHBurnup calculations can incorporate any desired operating history.
The user may enter the specific power, cycle lengths, cycle down
time, post-irradiation cooling time, etc. The axial-water-moderator
density variation may also be specified in the depletion analysis,
provided the ORIGEN cross section library contains such data.}(hjmVh jkVubah}(h]h]h]h]h]uhh:h!jIhMh jgVubah}(h]h]h]h]h]uhjh j
Vhhh!jIhNubj)}(hXThe effects of assembly design, soluble boron concentrations,
burnable poison exposure, reactor operating conditions, etc., are
accounted for in the ORIGEN cross section libraries used in the
ORIGEN depletion calculations. Libraries for several fuel assembly
designs are distributed with SCALE. These libraries can also be
readily created for any reactor and fuel assembly design that can be
represented in the depletion analysis sequences of the SCALE system.
h]h;)}(hXThe effects of assembly design, soluble boron concentrations,
burnable poison exposure, reactor operating conditions, etc., are
accounted for in the ORIGEN cross section libraries used in the
ORIGEN depletion calculations. Libraries for several fuel assembly
designs are distributed with SCALE. These libraries can also be
readily created for any reactor and fuel assembly design that can be
represented in the depletion analysis sequences of the SCALE system.h]h/XThe effects of assembly design, soluble boron concentrations,
burnable poison exposure, reactor operating conditions, etc., are
accounted for in the ORIGEN cross section libraries used in the
ORIGEN depletion calculations. Libraries for several fuel assembly
designs are distributed with SCALE. These libraries can also be
readily created for any reactor and fuel assembly design that can be
represented in the depletion analysis sequences of the SCALE system.}(hjVh jVubah}(h]h]h]h]h]uhh:h!jIhM
h jVubah}(h]h]h]h]h]uhjh j
Vhhh!jIhNubj)}(hThe user can select the specific actinide and/or fission product
nuclides to be included in the criticality safety analysis. The user
also has the option to perform a criticality calculation employing
all nuclides for which cross section data exist.
h]h;)}(hThe user can select the specific actinide and/or fission product
nuclides to be included in the criticality safety analysis. The user
also has the option to perform a criticality calculation employing
all nuclides for which cross section data exist.h]h/The user can select the specific actinide and/or fission product
nuclides to be included in the criticality safety analysis. The user
also has the option to perform a criticality calculation employing
all nuclides for which cross section data exist.}(hjVh jVubah}(h]h]h]h]h]uhh:h!jIhMh jVubah}(h]h]h]h]h]uhjh j
Vhhh!jIhNubj)}(hIsotopic correction factors may be input to adjust the calculated
nuclide inventories to account for known bias and/or uncertainties
associated with the depletion calculations.
h]h;)}(hIsotopic correction factors may be input to adjust the calculated
nuclide inventories to account for known bias and/or uncertainties
associated with the depletion calculations.h]h/Isotopic correction factors may be input to adjust the calculated
nuclide inventories to account for known bias and/or uncertainties
associated with the depletion calculations.}(hjVh jVubah}(h]h]h]h]h]uhh:h!jIhMh jVubah}(h]h]h]h]h]uhjh j
Vhhh!jIhNubeh}(h]h]h]h]h]j j j hj juhj h jUhhh!jIhKubh;)}(hXtMinimal user input is required to perform many types of analyses.
Default values are supplied for many of the input parameter keywords.
The user may select from built-in burnup-dependent 18-axial-zone
profiles taken from :cite:`lancaster_actinide-only_1998`, or the user may input an arbitrary
user-defined burnup distribution with up to 100-axial zones and up to
7-horizontal zones. The depletion analysis calculations for each zone
are performed for all nuclides (the ORIGEN data libraries contain cross
section and decay data for more than 1000 unique actinides, fission
products, and structural activation products). The specific nuclides to
be considered in the *k*\ :sub:`eff` analysis may be input by the user. If no
nuclide set is explicitly selected, then all nuclides that have cross
section data in the ORIGEN library are automatically applied in the
criticality analysis, resulting in a “full” burnup-credit criticality
assessment. A capability to adjust the calculated isotopic inventories
using correction factors that can account for biases and/or
uncertainties in the calculated isotopic concentrations is also
provided.h](h/Minimal user input is required to perform many types of analyses.
Default values are supplied for many of the input parameter keywords.
The user may select from built-in burnup-dependent 18-axial-zone
profiles taken from }(hMinimal user input is required to perform many types of analyses.
Default values are supplied for many of the input parameter keywords.
The user may select from built-in burnup-dependent 18-axial-zone
profiles taken from h jVhhh!NhNubh_)}(hlancaster_actinide-only_1998h]he)}(hjVh]h/[lancaster_actinide-only_1998]}(hhh jVubah}(h]h]h]h]h]uhhdh jVubah}(h]jKah]hwah]h]h] refdomainh|reftypeh~ reftargetjVrefwarnsupport_smartquotesuhh^h!jIhMh jVhhubh/X, or the user may input an arbitrary
user-defined burnup distribution with up to 100-axial zones and up to
7-horizontal zones. The depletion analysis calculations for each zone
are performed for all nuclides (the ORIGEN data libraries contain cross
section and decay data for more than 1000 unique actinides, fission
products, and structural activation products). The specific nuclides to
be considered in the }(hX, or the user may input an arbitrary
user-defined burnup distribution with up to 100-axial zones and up to
7-horizontal zones. The depletion analysis calculations for each zone
are performed for all nuclides (the ORIGEN data libraries contain cross
section and decay data for more than 1000 unique actinides, fission
products, and structural activation products). The specific nuclides to
be considered in the h jVhhh!NhNubh)}(h*k*h]h/k}(hhh jVubah}(h]h]h]h]h]uhhh jVubh/ }(h\ h jVhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j
Wubah}(h]h]h]h]h]uhjh jVubh/X analysis may be input by the user. If no
nuclide set is explicitly selected, then all nuclides that have cross
section data in the ORIGEN library are automatically applied in the
criticality analysis, resulting in a “full” burnup-credit criticality
assessment. A capability to adjust the calculated isotopic inventories
using correction factors that can account for biases and/or
uncertainties in the calculated isotopic concentrations is also
provided.}(hX analysis may be input by the user. If no
nuclide set is explicitly selected, then all nuclides that have cross
section data in the ORIGEN library are automatically applied in the
criticality analysis, resulting in a “full” burnup-credit criticality
assessment. A capability to adjust the calculated isotopic inventories
using correction factors that can account for biases and/or
uncertainties in the calculated isotopic concentrations is also
provided.h jVhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jUhhubh;)}(hXAn appropriate ORIGEN cross section library for UO\ :sub:`2` fuel must
be available for the depletion analysis using STARBUCS. The user may use
the libraries distributed with SCALE (e.g., ge7×7-0, ge8×8-4, ce14×14,
w15×15, w17×17_ofa) or the user may generate their own problem-specific
libraries using the TRITON depletion analysis sequence available in
SCALE. A complete list of ORIGEN libraries distributed with SCALE and
methods for generating ORIGEN libraries are both described in the ORIGEN
Reactor Libraries chapter. The range of initial fuel enrichment and
requested burnup values to be used in the STARBUCS calculations must be
contained within the range of the enrichments and burnups used to
generate the applicable ORIGEN library.h](h/4An appropriate ORIGEN cross section library for UO }(h4An appropriate ORIGEN cross section library for UO\ h j#Whhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j,Wubah}(h]h]h]h]h]uhjh j#Wubh/X fuel must
be available for the depletion analysis using STARBUCS. The user may use
the libraries distributed with SCALE (e.g., ge7×7-0, ge8×8-4, ce14×14,
w15×15, w17×17_ofa) or the user may generate their own problem-specific
libraries using the TRITON depletion analysis sequence available in
SCALE. A complete list of ORIGEN libraries distributed with SCALE and
methods for generating ORIGEN libraries are both described in the ORIGEN
Reactor Libraries chapter. The range of initial fuel enrichment and
requested burnup values to be used in the STARBUCS calculations must be
contained within the range of the enrichments and burnups used to
generate the applicable ORIGEN library.}(hX fuel must
be available for the depletion analysis using STARBUCS. The user may use
the libraries distributed with SCALE (e.g., ge7×7-0, ge8×8-4, ce14×14,
w15×15, w17×17_ofa) or the user may generate their own problem-specific
libraries using the TRITON depletion analysis sequence available in
SCALE. A complete list of ORIGEN libraries distributed with SCALE and
methods for generating ORIGEN libraries are both described in the ORIGEN
Reactor Libraries chapter. The range of initial fuel enrichment and
requested burnup values to be used in the STARBUCS calculations must be
contained within the range of the enrichments and burnups used to
generate the applicable ORIGEN library.h j#Whhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhM-h jUhhubh;)}(hXThe user is required to provide a complete KENO V.a model of the spent
fuel configuration for burnup loading curve calculations and a complete
KENO V.a or KENO-VI model of the spent fuel configuration for single
criticality calculations using burnup credit. The initial material
composition information is defined in a standard composition data block.
The fuel material is automatically depleted in the sequence for each of
the burnup-dependent regions or zones in the problem. The nuclide
concentrations after irradiation and decay are automatically applied to
the KENO criticality analysis. The mixture numbers for each of the fuel
regions are identified by unique mixture numbers assigned automatically
by STARBUCS based on the axial and horizontal regions in the problem
(see :numref:`fig2-3-3`). The user is required to specify the geometry/extent
of the axial and horizontal zones in the KENO model and apply the
appropriate mixture numbers for the desired configuration based on the
mixture identifying scheme. STARBUCS performs no checking of the
criticality model to verify that all mixtures in the problem have been
used or that the order of the mixture numbers in the KENO model
corresponds to the corresponding order of the input burnup profile. This
provides the user a great deal of flexibility in setting up problems.
However, it also requires that the user accurately prepare the input
files to ensure that the spent fuel zone mixtures are assigned to the
correct KENO V.a or KENO-VI geometry regions. For instance, the user
could (intentionally) reverse the order of the axial-material
identifiers in the KENO model to simulate inverted fuel, or zone
mixtures could be omitted to simulate a problem using only a subset of
the available fuel zones that were simulated in the depletion analysis.h](h/XThe user is required to provide a complete KENO V.a model of the spent
fuel configuration for burnup loading curve calculations and a complete
KENO V.a or KENO-VI model of the spent fuel configuration for single
criticality calculations using burnup credit. The initial material
composition information is defined in a standard composition data block.
The fuel material is automatically depleted in the sequence for each of
the burnup-dependent regions or zones in the problem. The nuclide
concentrations after irradiation and decay are automatically applied to
the KENO criticality analysis. The mixture numbers for each of the fuel
regions are identified by unique mixture numbers assigned automatically
by STARBUCS based on the axial and horizontal regions in the problem
(see }(hXThe user is required to provide a complete KENO V.a model of the spent
fuel configuration for burnup loading curve calculations and a complete
KENO V.a or KENO-VI model of the spent fuel configuration for single
criticality calculations using burnup credit. The initial material
composition information is defined in a standard composition data block.
The fuel material is automatically depleted in the sequence for each of
the burnup-dependent regions or zones in the problem. The nuclide
concentrations after irradiation and decay are automatically applied to
the KENO criticality analysis. The mixture numbers for each of the fuel
regions are identified by unique mixture numbers assigned automatically
by STARBUCS based on the axial and horizontal regions in the problem
(see h jEWhhh!NhNubh_)}(h:numref:`fig2-3-3`h]j)}(hjPWh]h/fig2-3-3}(hhh jRWubah}(h]h](jstd
std-numrefeh]h]h]uhjh jNWubah}(h]h]h]h]h]refdocj refdomainj\Wreftypenumrefrefexplicitrefwarnjfig2-3-3uhh^h!jIhM9h jEWubh/X). The user is required to specify the geometry/extent
of the axial and horizontal zones in the KENO model and apply the
appropriate mixture numbers for the desired configuration based on the
mixture identifying scheme. STARBUCS performs no checking of the
criticality model to verify that all mixtures in the problem have been
used or that the order of the mixture numbers in the KENO model
corresponds to the corresponding order of the input burnup profile. This
provides the user a great deal of flexibility in setting up problems.
However, it also requires that the user accurately prepare the input
files to ensure that the spent fuel zone mixtures are assigned to the
correct KENO V.a or KENO-VI geometry regions. For instance, the user
could (intentionally) reverse the order of the axial-material
identifiers in the KENO model to simulate inverted fuel, or zone
mixtures could be omitted to simulate a problem using only a subset of
the available fuel zones that were simulated in the depletion analysis.}(hX). The user is required to specify the geometry/extent
of the axial and horizontal zones in the KENO model and apply the
appropriate mixture numbers for the desired configuration based on the
mixture identifying scheme. STARBUCS performs no checking of the
criticality model to verify that all mixtures in the problem have been
used or that the order of the mixture numbers in the KENO model
corresponds to the corresponding order of the input burnup profile. This
provides the user a great deal of flexibility in setting up problems.
However, it also requires that the user accurately prepare the input
files to ensure that the spent fuel zone mixtures are assigned to the
correct KENO V.a or KENO-VI geometry regions. For instance, the user
could (intentionally) reverse the order of the axial-material
identifiers in the KENO model to simulate inverted fuel, or zone
mixtures could be omitted to simulate a problem using only a subset of
the available fuel zones that were simulated in the depletion analysis.h jEWhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhM9h jUhhubh)}(h
.. _fig2-3-3:h]h}(h]h]h]h]h]hfig2-3-3uhh
hMh jUhhh!jIubj)}(hhh](j)}(h.. figure:: figs/STARBUCS/fig3.png
:align: center
:width: 600
Fuel and material mixture numbering convention used in STARBUCS.
h]h}(h]h]h]h]h]width600urifigs/STARBUCS/fig3.pngj}jjWsuhjh jWh!jIhMYubj)}(h@Fuel and material mixture numbering convention used in STARBUCS.h]h/@Fuel and material mixture numbering convention used in STARBUCS.}(hjWh jWubah}(h]h]h]h]h]uhjh!jIhMYh jWubeh}(h](id86jWeh]h]fig2-3-3ah]h]jcenteruhjhMYh jUhhh!jIj}jWjyWsj}jWjyWsubh)}(h
.. _fig2-3-4:h]h}(h]h]h]h]h]hfig2-3-4uhh
hMh jUhhh!jIubj)}(hhh](j)}(h{.. figure:: figs/STARBUCS/fig4.png
:align: center
:width: 600
Example of mixture numbering scheme used in STARBUCS.
h]h}(h]h]h]h]h]width600urifigs/STARBUCS/fig4.pngj}jjWsuhjh jWh!jIhM`ubj)}(h5Example of mixture numbering scheme used in STARBUCS.h]h/5Example of mixture numbering scheme used in STARBUCS.}(hjWh jWubah}(h]h]h]h]h]uhjh!jIhM`h jWubeh}(h](id87jWeh]h]fig2-3-4ah]h]jcenteruhjhM`h jUhhh!jIj}jWjWsj}jWjWsubh;)}(hThere are several conventions that must be followed when using STARBUCS.
In general, these relate to the specification of materials and mixture
numbering of the cross section mixing table.h]h/There are several conventions that must be followed when using STARBUCS.
In general, these relate to the specification of materials and mixture
numbering of the cross section mixing table.}(hjWh jWhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMbh jUhhubj )}(hhh](j)}(hXThe maximum number of horizontal zones is restricted to seven if
there is no gap or second moderator mixture, six if a gap or second
moderator mixture is defined, and five if both a gap and a second
moderator are defined. The number of axial-fuel zones is limited such
that the product of horizontal zones ∗ axial zones is less than or
equal to 100. These limits constrain the maximum mixture number used
for burned fuel in the KENO criticality calculation to less than 1000
and assign unique mixture numbers to clad, moderator, and gap
mixtures for lattice cell descriptions. The convention used to number
the depleted fuel zones is to start at mixture 101 and increment by 1
for each axial-burnup region. Thus, for a case with 10 axial-burnup
regions, the fuel mixtures used in the criticality analysis would
range from 101 to 110. For a similar case having two horizontal zones
in addition to the axial zones, the mixture numbers would also
include mixtures 201 to 210.
h]h;)}(hXThe maximum number of horizontal zones is restricted to seven if
there is no gap or second moderator mixture, six if a gap or second
moderator mixture is defined, and five if both a gap and a second
moderator are defined. The number of axial-fuel zones is limited such
that the product of horizontal zones ∗ axial zones is less than or
equal to 100. These limits constrain the maximum mixture number used
for burned fuel in the KENO criticality calculation to less than 1000
and assign unique mixture numbers to clad, moderator, and gap
mixtures for lattice cell descriptions. The convention used to number
the depleted fuel zones is to start at mixture 101 and increment by 1
for each axial-burnup region. Thus, for a case with 10 axial-burnup
regions, the fuel mixtures used in the criticality analysis would
range from 101 to 110. For a similar case having two horizontal zones
in addition to the axial zones, the mixture numbers would also
include mixtures 201 to 210.h]h/XThe maximum number of horizontal zones is restricted to seven if
there is no gap or second moderator mixture, six if a gap or second
moderator mixture is defined, and five if both a gap and a second
moderator are defined. The number of axial-fuel zones is limited such
that the product of horizontal zones ∗ axial zones is less than or
equal to 100. These limits constrain the maximum mixture number used
for burned fuel in the KENO criticality calculation to less than 1000
and assign unique mixture numbers to clad, moderator, and gap
mixtures for lattice cell descriptions. The convention used to number
the depleted fuel zones is to start at mixture 101 and increment by 1
for each axial-burnup region. Thus, for a case with 10 axial-burnup
regions, the fuel mixtures used in the criticality analysis would
range from 101 to 110. For a similar case having two horizontal zones
in addition to the axial zones, the mixture numbers would also
include mixtures 201 to 210.}(hjWh jWubah}(h]h]h]h]h]uhh:h!jIhMfh jWubah}(h]h]h]h]h]uhjh jWhhh!jIhNubj)}(hXMixture numbers for the clad, gap (if applicable), and moderator may
also be used directly in the KENO model. Additional unique mixture
numbers are required by the code for the lattice cell descriptions
for each separate fuel zone (except for mixture 0 for void). These
additional mixtures are assigned automatically by the code and are
shown in :numref:`fig2-3-3` for a lattice cell consisting of fuel, gap,
clad, and moderator. The additional mixture numbers may also be used
directly in the KENO model. Mixture number allocation is illustrated
in :numref:`fig2-3-4` for an example case where the number of different
horizontal zones is four and the maximum number of axial zones is
limited to 25.
h]h;)}(hXMixture numbers for the clad, gap (if applicable), and moderator may
also be used directly in the KENO model. Additional unique mixture
numbers are required by the code for the lattice cell descriptions
for each separate fuel zone (except for mixture 0 for void). These
additional mixtures are assigned automatically by the code and are
shown in :numref:`fig2-3-3` for a lattice cell consisting of fuel, gap,
clad, and moderator. The additional mixture numbers may also be used
directly in the KENO model. Mixture number allocation is illustrated
in :numref:`fig2-3-4` for an example case where the number of different
horizontal zones is four and the maximum number of axial zones is
limited to 25.h](h/X[Mixture numbers for the clad, gap (if applicable), and moderator may
also be used directly in the KENO model. Additional unique mixture
numbers are required by the code for the lattice cell descriptions
for each separate fuel zone (except for mixture 0 for void). These
additional mixtures are assigned automatically by the code and are
shown in }(hX[Mixture numbers for the clad, gap (if applicable), and moderator may
also be used directly in the KENO model. Additional unique mixture
numbers are required by the code for the lattice cell descriptions
for each separate fuel zone (except for mixture 0 for void). These
additional mixtures are assigned automatically by the code and are
shown in h jXubh_)}(h:numref:`fig2-3-3`h]j)}(hjXh]h/fig2-3-3}(hhh jXubah}(h]h](jstd
std-numrefeh]h]h]uhjh jXubah}(h]h]h]h]h]refdocj refdomainj)Xreftypenumrefrefexplicitrefwarnjfig2-3-3uhh^h!jIhMvh jXubh/ for a lattice cell consisting of fuel, gap,
clad, and moderator. The additional mixture numbers may also be used
directly in the KENO model. Mixture number allocation is illustrated
in }(h for a lattice cell consisting of fuel, gap,
clad, and moderator. The additional mixture numbers may also be used
directly in the KENO model. Mixture number allocation is illustrated
in h jXubh_)}(h:numref:`fig2-3-4`h]j)}(hjBXh]h/fig2-3-4}(hhh jDXubah}(h]h](jstd
std-numrefeh]h]h]uhjh j@Xubah}(h]h]h]h]h]refdocj refdomainjNXreftypenumrefrefexplicitrefwarnjfig2-3-4uhh^h!jIhMvh jXubh/ for an example case where the number of different
horizontal zones is four and the maximum number of axial zones is
limited to 25.}(h for an example case where the number of different
horizontal zones is four and the maximum number of axial zones is
limited to 25.h jXubeh}(h]h]h]h]h]uhh:h!jIhMvh jXubah}(h]h]h]h]h]uhjh jWhhh!jIhNubj)}(hXAll structural materials in the problem must have mixture numbers
different from the numbers automatically generated by the code (see
:numref:`fig2-3-4` for an example of available mixture numbers). For the
example shown in :numref:`fig2-3-4`, mixtures 5–100, 126–200, 226–300,
326–400, 501, 601, 701, 426–500, and 801–2147 are not allocated by
STARBUCS and may be defined by the user in the composition data block
and used in the geometry model. If the constraints in paragraph 1 are
followed, mixture numbers less than 100 that were not used for fuel,
gap, clad, moderator and mixture numbers from 1001 to 2147 are always
available for structural materials. Note that STARBUCS does not
provide a warning or stop program execution if a mixture number
assigned to a structural material has also been generated internally
by the computer code. The mixture numbers for structural materials
are not changed and are thus applied in the KENO model in a
one-to-one correspondence with the standard composition mixture as
done for typical CSAS calculations. Therefore, the use of a mixture
number for structural materials that is identical to one of the
mixture numbers automatically generated by the code results in the
combination of both materials in the composition for the mixture
number.
h]h;)}(hXAll structural materials in the problem must have mixture numbers
different from the numbers automatically generated by the code (see
:numref:`fig2-3-4` for an example of available mixture numbers). For the
example shown in :numref:`fig2-3-4`, mixtures 5–100, 126–200, 226–300,
326–400, 501, 601, 701, 426–500, and 801–2147 are not allocated by
STARBUCS and may be defined by the user in the composition data block
and used in the geometry model. If the constraints in paragraph 1 are
followed, mixture numbers less than 100 that were not used for fuel,
gap, clad, moderator and mixture numbers from 1001 to 2147 are always
available for structural materials. Note that STARBUCS does not
provide a warning or stop program execution if a mixture number
assigned to a structural material has also been generated internally
by the computer code. The mixture numbers for structural materials
are not changed and are thus applied in the KENO model in a
one-to-one correspondence with the standard composition mixture as
done for typical CSAS calculations. Therefore, the use of a mixture
number for structural materials that is identical to one of the
mixture numbers automatically generated by the code results in the
combination of both materials in the composition for the mixture
number.h](h/All structural materials in the problem must have mixture numbers
different from the numbers automatically generated by the code (see
}(hAll structural materials in the problem must have mixture numbers
different from the numbers automatically generated by the code (see
h juXubh_)}(h:numref:`fig2-3-4`h]j)}(hjXh]h/fig2-3-4}(hhh jXubah}(h]h](jstd
std-numrefeh]h]h]uhjh j~Xubah}(h]h]h]h]h]refdocj refdomainjXreftypenumrefrefexplicitrefwarnjfig2-3-4uhh^h!jIhMh juXubh/H for an example of available mixture numbers). For the
example shown in }(hH for an example of available mixture numbers). For the
example shown in h juXubh_)}(h:numref:`fig2-3-4`h]j)}(hjXh]h/fig2-3-4}(hhh jXubah}(h]h](jstd
std-numrefeh]h]h]uhjh jXubah}(h]h]h]h]h]refdocj refdomainjXreftypenumrefrefexplicitrefwarnjfig2-3-4uhh^h!jIhMh juXubh/X , mixtures 5–100, 126–200, 226–300,
326–400, 501, 601, 701, 426–500, and 801–2147 are not allocated by
STARBUCS and may be defined by the user in the composition data block
and used in the geometry model. If the constraints in paragraph 1 are
followed, mixture numbers less than 100 that were not used for fuel,
gap, clad, moderator and mixture numbers from 1001 to 2147 are always
available for structural materials. Note that STARBUCS does not
provide a warning or stop program execution if a mixture number
assigned to a structural material has also been generated internally
by the computer code. The mixture numbers for structural materials
are not changed and are thus applied in the KENO model in a
one-to-one correspondence with the standard composition mixture as
done for typical CSAS calculations. Therefore, the use of a mixture
number for structural materials that is identical to one of the
mixture numbers automatically generated by the code results in the
combination of both materials in the composition for the mixture
number.}(hX , mixtures 5–100, 126–200, 226–300,
326–400, 501, 601, 701, 426–500, and 801–2147 are not allocated by
STARBUCS and may be defined by the user in the composition data block
and used in the geometry model. If the constraints in paragraph 1 are
followed, mixture numbers less than 100 that were not used for fuel,
gap, clad, moderator and mixture numbers from 1001 to 2147 are always
available for structural materials. Note that STARBUCS does not
provide a warning or stop program execution if a mixture number
assigned to a structural material has also been generated internally
by the computer code. The mixture numbers for structural materials
are not changed and are thus applied in the KENO model in a
one-to-one correspondence with the standard composition mixture as
done for typical CSAS calculations. Therefore, the use of a mixture
number for structural materials that is identical to one of the
mixture numbers automatically generated by the code results in the
combination of both materials in the composition for the mixture
number.h juXubeh}(h]h]h]h]h]uhh:h!jIhMh jqXubah}(h]h]h]h]h]uhjh jWhhh!jIhNubj)}(hXNot all SCALE standard composition alphanumeric names (see the
Standard Composition Library chapter) are currently recognized by
STARBUCS. The use of special materials (e.g., C-GRAPHITE, NIINCONEL,
H-POLY), particularly as fuel materials, that have nuclide
identifiers that are not readily translated to ORIGEN ZA numbers
should be avoided since these materials cannot be depleted.
h]h;)}(hX~Not all SCALE standard composition alphanumeric names (see the
Standard Composition Library chapter) are currently recognized by
STARBUCS. The use of special materials (e.g., C-GRAPHITE, NIINCONEL,
H-POLY), particularly as fuel materials, that have nuclide
identifiers that are not readily translated to ORIGEN ZA numbers
should be avoided since these materials cannot be depleted.h]h/X~Not all SCALE standard composition alphanumeric names (see the
Standard Composition Library chapter) are currently recognized by
STARBUCS. The use of special materials (e.g., C-GRAPHITE, NIINCONEL,
H-POLY), particularly as fuel materials, that have nuclide
identifiers that are not readily translated to ORIGEN ZA numbers
should be avoided since these materials cannot be depleted.}(hjXh jXubah}(h]h]h]h]h]uhh:h!jIhMh jXubah}(h]h]h]h]h]uhjh jWhhh!jIhNubj)}(hXA single STARBUCS calculation is limited to a single initial fuel
type (composition, enrichment, assembly design, etc.). Configurations
involving multiple fuel types may be solved by running a separate
STARBUCS case for each type, saving the corresponding CSAS cases
generated by STARBUCS that contain the irradiated fuel nuclide
compositions, and manually merging the cases in such a way that all
required fuel types are represented in the final case.
h]h;)}(hXA single STARBUCS calculation is limited to a single initial fuel
type (composition, enrichment, assembly design, etc.). Configurations
involving multiple fuel types may be solved by running a separate
STARBUCS case for each type, saving the corresponding CSAS cases
generated by STARBUCS that contain the irradiated fuel nuclide
compositions, and manually merging the cases in such a way that all
required fuel types are represented in the final case.h]h/XA single STARBUCS calculation is limited to a single initial fuel
type (composition, enrichment, assembly design, etc.). Configurations
involving multiple fuel types may be solved by running a separate
STARBUCS case for each type, saving the corresponding CSAS cases
generated by STARBUCS that contain the irradiated fuel nuclide
compositions, and manually merging the cases in such a way that all
required fuel types are represented in the final case.}(hjXh jXubah}(h]h]h]h]h]uhh:h!jIhMh jXubah}(h]h]h]h]h]uhjh jWhhh!jIhNubeh}(h]h]h]h]h]j j j hj juhj h jUhhh!jIhMfubeh}(h](capabilities-and-limitationsjUeh]h](capabilities and limitationscap-and-limeh]h]uhh#h jRhhh!jIhKj}jYjUsj}jUjUsubh$)}(hhh](h))}(hInput Descriptionh]h/Input Description}(hjYh jYhhh!NhNubah}(h]h]h]h]h]uhh(h jYhhh!jIhMubh;)}(hX,STARBUCS input is divided into different data blocks containing related
types of information. The standard composition data block used to define
initial (fresh) fuel composition and all other materials in the
criticality analysis problem, is read and processed by the material and
cross section processing module of SCALE (XSProc) and conforms to the
standard input conventions (see
Chapter \ 7 (SECTIONREFERENCE)
In addition to the standard composition data, three more input data
blocks are required by STARBUCS. The data blocks are entered in the formh]h/X,STARBUCS input is divided into different data blocks containing related
types of information. The standard composition data block used to define
initial (fresh) fuel composition and all other materials in the
criticality analysis problem, is read and processed by the material and
cross section processing module of SCALE (XSProc) and conforms to the
standard input conventions (see
Chapter 7 (SECTIONREFERENCE)
In addition to the standard composition data, three more input data
blocks are required by STARBUCS. The data blocks are entered in the form}(hX,STARBUCS input is divided into different data blocks containing related
types of information. The standard composition data block used to define
initial (fresh) fuel composition and all other materials in the
criticality analysis problem, is read and processed by the material and
cross section processing module of SCALE (XSProc) and conforms to the
standard input conventions (see
Chapter \ 7 (SECTIONREFERENCE)
In addition to the standard composition data, three more input data
blocks are required by STARBUCS. The data blocks are entered in the formh j&Yhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jYhhubj)}(hhh]h}(h]h]h]h]h]langscaleforcelinenothresholduhjh jYhhh!jIhMubj)}(h"READ XXXX input data END XXXXh]h/"READ XXXX input data END XXXX}(hhh jBYubah}(h]h]h]h]h]jjuhjh!jIhMh jYhhubh;)}(hXQwhere **XXXX** is the data block keyword for the type of data being
entered. The types of data blocks that are entered include general
control parameter information, irradiation history and decay data or
search parameter data, and the KENO V.a or KENO-VI input specifications.
The valid block keywords for a single criticality safety calculation
using burnup credit and for burnup loading curve calculations are listed
in :numref:`tab2-3-1` and :numref:`tab2-3-2`, respectively. A minimum of four
characters is required for most keywords. The exception is the
criticality model input data block READ KENOVA or READ KENOVI in which
case the code must check additional character positions to determine the
CSAS control sequence to be executed. The keywords can be up to twelve
characters long, the first four of which must be input exactly as listed
in the table. Entering the words **READ XXXX** followed by one or more
blanks activates the data block input. All input data pertinent to block
**XXXX** are then entered. Entering **END XXXX** followed by two or more
blanks terminates data block **XXXX**.h](h/where }(hwhere h jPYhhh!NhNubhA)}(h**XXXX**h]h/XXXX}(hhh jYYubah}(h]h]h]h]h]uhh@h jPYubh/X is the data block keyword for the type of data being
entered. The types of data blocks that are entered include general
control parameter information, irradiation history and decay data or
search parameter data, and the KENO V.a or KENO-VI input specifications.
The valid block keywords for a single criticality safety calculation
using burnup credit and for burnup loading curve calculations are listed
in }(hX is the data block keyword for the type of data being
entered. The types of data blocks that are entered include general
control parameter information, irradiation history and decay data or
search parameter data, and the KENO V.a or KENO-VI input specifications.
The valid block keywords for a single criticality safety calculation
using burnup credit and for burnup loading curve calculations are listed
in h jPYhhh!NhNubh_)}(h:numref:`tab2-3-1`h]j)}(hjnYh]h/tab2-3-1}(hhh jpYubah}(h]h](jstd
std-numrefeh]h]h]uhjh jlYubah}(h]h]h]h]h]refdocj refdomainjzYreftypenumrefrefexplicitrefwarnjtab2-3-1uhh^h!jIhMh jPYubh/ and }(h and h jPYhhh!NhNubh_)}(h:numref:`tab2-3-2`h]j)}(hjYh]h/tab2-3-2}(hhh jYubah}(h]h](jstd
std-numrefeh]h]h]uhjh jYubah}(h]h]h]h]h]refdocj refdomainjYreftypenumrefrefexplicitrefwarnjtab2-3-2uhh^h!jIhMh jPYubh/X, respectively. A minimum of four
characters is required for most keywords. The exception is the
criticality model input data block READ KENOVA or READ KENOVI in which
case the code must check additional character positions to determine the
CSAS control sequence to be executed. The keywords can be up to twelve
characters long, the first four of which must be input exactly as listed
in the table. Entering the words }(hX, respectively. A minimum of four
characters is required for most keywords. The exception is the
criticality model input data block READ KENOVA or READ KENOVI in which
case the code must check additional character positions to determine the
CSAS control sequence to be executed. The keywords can be up to twelve
characters long, the first four of which must be input exactly as listed
in the table. Entering the words h jPYhhh!NhNubhA)}(h
**READ XXXX**h]h/ READ XXXX}(hhh jYubah}(h]h]h]h]h]uhh@h jPYubh/b followed by one or more
blanks activates the data block input. All input data pertinent to block
}(hb followed by one or more
blanks activates the data block input. All input data pertinent to block
h jPYhhh!NhNubhA)}(h**XXXX**h]h/XXXX}(hhh jYubah}(h]h]h]h]h]uhh@h jPYubh/ are then entered. Entering }(h are then entered. Entering h jPYhhh!NhNubhA)}(h**END XXXX**h]h/END XXXX}(hhh jYubah}(h]h]h]h]h]uhh@h jPYubh/6 followed by two or more
blanks terminates data block }(h6 followed by two or more
blanks terminates data block h jPYhhh!NhNubhA)}(h**XXXX**h]h/XXXX}(hhh jYubah}(h]h]h]h]h]uhh@h jPYubh/.}(hjh jPYhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jYhhubh)}(h
.. _tab2-3-1:h]h}(h]h]h]h]h]htab2-3-1uhh
hMh jYhhh!jIubj)}(hhh](h))}(hYValid data block keywords for a single criticality safety calculation using burnup credith]h/YValid data block keywords for a single criticality safety calculation using burnup credit}(hjZh jZubah}(h]h]h]h]h]uhh(h!jIhMh jZubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j#Zubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j#Zubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(h**Data block type**h]hA)}(hjEZh]h/Data block type}(hhh jGZubah}(h]h]h]h]h]uhh@h jCZubah}(h]h]h]h]h]uhh:h!jIhMh j@Zubah}(h]h]h]h]h]uhj9h j=Zubj:)}(hhh]h;)}(h**Block keyword**h]hA)}(hjeZh]h/
Block keyword}(hhh jgZubah}(h]h]h]h]h]uhh@h jcZubah}(h]h]h]h]h]uhh:h!jIhMh j`Zubah}(h]h]h]h]h]uhj9h j=Zubeh}(h]h]h]h]h]uhj4h j:Zubj5)}(hhh](j:)}(hhh]h;)}(hControl parametersh]h/Control parameters}(hjZh jZubah}(h]h]h]h]h]uhh:h!jIhMh jZubah}(h]h]h]h]h]uhj9h jZubj:)}(hhh]h;)}(hCONTROLh]h/CONTROL}(hjZh jZubah}(h]h]h]h]h]uhh:h!jIhMh jZubah}(h]h]h]h]h]uhj9h jZubeh}(h]h]h]h]h]uhj4h j:Zubj5)}(hhh](j:)}(hhh]h;)}(hBurnup historyh]h/Burnup history}(hjZh jZubah}(h]h]h]h]h]uhh:h!jIhMh jZubah}(h]h]h]h]h]uhj9h jZubj:)}(hhh]h;)}(hHISTORY or BURNDATAh]h/HISTORY or BURNDATA}(hjZh jZubah}(h]h]h]h]h]uhh:h!jIhMh jZubah}(h]h]h]h]h]uhj9h jZubeh}(h]h]h]h]h]uhj4h j:Zubj5)}(hhh](j:)}(hhh]h;)}(hKENO V.a inputh]h/KENO V.a input}(hjZh jZubah}(h]h]h]h]h]uhh:h!jIhMh jZubah}(h]h]h]h]h]uhj9h jZubj:)}(hhh]h;)}(hKENOVA or KENO5h]h/KENOVA or KENO5}(hj[h j[ubah}(h]h]h]h]h]uhh:h!jIhMh j[ubah}(h]h]h]h]h]uhj9h jZubeh}(h]h]h]h]h]uhj4h j:Zubj5)}(hhh](j:)}(hhh]h;)}(h
KENO-VI inputh]h/
KENO-VI input}(hj3[h j1[ubah}(h]h]h]h]h]uhh:h!jIhMh j.[ubah}(h]h]h]h]h]uhj9h j+[ubj:)}(hhh]h;)}(hKENOVI or KENO6h]h/KENOVI or KENO6}(hjJ[h jH[ubah}(h]h]h]h]h]uhh:h!jIhMh jE[ubah}(h]h]h]h]h]uhj9h j+[ubeh}(h]h]h]h]h]uhj4h j:Zubeh}(h]h]h]h]h]uhj/h j#Zubeh}(h]h]h]h]h]colsKuhjh jZubeh}(h](id88jZeh]h]tab2-3-1ah]h]jcenteruhjh jYhhh!jIhNj}jt[jZsj}jZjZsubh)}(h
.. _tab2-3-2:h]h}(h]h]h]h]h]htab2-3-2uhh
hM h jYhhh!jIubj)}(hhh](h))}(h@Valid data block keywords for burnup loading curve calculations.h]h/@Valid data block keywords for burnup loading curve calculations.}(hj[h j[ubah}(h]h]h]h]h]uhh(h!jIhMh j[ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j[ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j[ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(h**Data block type**h]hA)}(hj[h]h/Data block type}(hhh j[ubah}(h]h]h]h]h]uhh@h j[ubah}(h]h]h]h]h]uhh:h!jIhMh j[ubah}(h]h]h]h]h]uhj9h j[ubj:)}(hhh]h;)}(h**Block keyword**h]hA)}(hj[h]h/
Block keyword}(hhh j[ubah}(h]h]h]h]h]uhh@h j[ubah}(h]h]h]h]h]uhh:h!jIhMh j[ubah}(h]h]h]h]h]uhj9h j[ubeh}(h]h]h]h]h]uhj4h j[ubj5)}(hhh](j:)}(hhh]h;)}(hControl parametersh]h/Control parameters}(hj\h j[ubah}(h]h]h]h]h]uhh:h!jIhMh j[ubah}(h]h]h]h]h]uhj9h j[ubj:)}(hhh]h;)}(hCONTROLh]h/CONTROL}(hj\h j\ubah}(h]h]h]h]h]uhh:h!jIhMh j\ubah}(h]h]h]h]h]uhj9h j[ubeh}(h]h]h]h]h]uhj4h j[ubj5)}(hhh](j:)}(hhh]h;)}(hSearch parametersh]h/Search parameters}(hj8\h j6\ubah}(h]h]h]h]h]uhh:h!jIhMh j3\ubah}(h]h]h]h]h]uhj9h j0\ubj:)}(hhh]h;)}(hSEARCHh]h/SEARCH}(hjO\h jM\ubah}(h]h]h]h]h]uhh:h!jIhMh jJ\ubah}(h]h]h]h]h]uhj9h j0\ubeh}(h]h]h]h]h]uhj4h j[ubj5)}(hhh](j:)}(hhh]h;)}(hKENO V.a inputh]h/KENO V.a input}(hjo\h jm\ubah}(h]h]h]h]h]uhh:h!jIhMh jj\ubah}(h]h]h]h]h]uhj9h jg\ubj:)}(hhh]h;)}(hKENOVA or KENO5h]h/KENOVA or KENO5}(hj\h j\ubah}(h]h]h]h]h]uhh:h!jIhMh j\ubah}(h]h]h]h]h]uhj9h jg\ubeh}(h]h]h]h]h]uhj4h j[ubeh}(h]h]h]h]h]uhj/h j[ubeh}(h]h]h]h]h]colsKuhjh j[ubeh}(h](id89j[eh]h]tab2-3-2ah]h]jcenteruhjh jYhhh!jIhNj}j\jz[sj}j[jz[subh;)}(hX:All input within a data block is entered using keywords and is free
format. Keyword entries may be of variable or array type. Variable
keyword entries include the keyword plus the “=”, followed by the value.
Array keywords are usually followed by a series of entries, each
separated by a blank or comma, and must always be terminated with an END
that does not begin in column one. In some instances a single value may
be input as an array entry; however, the word END is still always
required. Within a given input data block the keyword entries may be in
any order.h]h/X:All input within a data block is entered using keywords and is free
format. Keyword entries may be of variable or array type. Variable
keyword entries include the keyword plus the “=”, followed by the value.
Array keywords are usually followed by a series of entries, each
separated by a blank or comma, and must always be terminated with an END
that does not begin in column one. In some instances a single value may
be input as an array entry; however, the word END is still always
required. Within a given input data block the keyword entries may be in
any order.}(hj\h j\hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jYhhubh;)}(hXA single data entry may be entered anywhere on a line but cannot be
divided between two lines; however, array data entries may be divided
over many lines. The code identifies data keywords using only the first
four (maximum) characters in the keyword name. Beyond the first four
characters, the user may enter any alphanumeric or special character
acceptable in FORTRAN, including single blanks, before the “=”
character. Floating-point data may be entered in various forms; for
example, the value 12340.0 may be entered as: 12340, 12340.0, 1.234+4,
1.234E+4, 1.234E4, or 1.234E+04. Also, the value 0.012 may be entered as
12E−3, 12−3, 1.2−2, etc. Numeric data must be followed immediately by
one or more blanks or a comma.h]h/XA single data entry may be entered anywhere on a line but cannot be
divided between two lines; however, array data entries may be divided
over many lines. The code identifies data keywords using only the first
four (maximum) characters in the keyword name. Beyond the first four
characters, the user may enter any alphanumeric or special character
acceptable in FORTRAN, including single blanks, before the “=”
character. Floating-point data may be entered in various forms; for
example, the value 12340.0 may be entered as: 12340, 12340.0, 1.234+4,
1.234E+4, 1.234E4, or 1.234E+04. Also, the value 0.012 may be entered as
12E−3, 12−3, 1.2−2, etc. Numeric data must be followed immediately by
one or more blanks or a comma.}(hj\h j\hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jYhhubh$)}(hhh](h))}(hOverview of input structureh]h/Overview of input structure}(hj\h j\hhh!NhNubah}(h]h]h]h]h]uhh(h j\hhh!jIhMubh;)}(hXAn overview of the input to the STARBUCS sequence is given in
:numref:`tab2-3-3`. This table provides an outline of the input data block
structure. The input data in positions 1 to 5 (see :numref:`tab2-3-3`) are read
and processed by the material and cross section processing module of
SCALE (XSProc). These are the first data read by the code and must be in
the order indicated. Data positions 6, 7 or 8, and 9 are read directly
by STARBUCS and may be entered in any order.h](h/>An overview of the input to the STARBUCS sequence is given in
}(h>An overview of the input to the STARBUCS sequence is given in
h j\hhh!NhNubh_)}(h:numref:`tab2-3-3`h]j)}(hj\h]h/tab2-3-3}(hhh j\ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j\ubah}(h]h]h]h]h]refdocj refdomainj\reftypenumrefrefexplicitrefwarnjtab2-3-3uhh^h!jIhMh j\ubh/m. This table provides an outline of the input data block
structure. The input data in positions 1 to 5 (see }(hm. This table provides an outline of the input data block
structure. The input data in positions 1 to 5 (see h j\hhh!NhNubh_)}(h:numref:`tab2-3-3`h]j)}(hj]h]h/tab2-3-3}(hhh j]ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j]ubah}(h]h]h]h]h]refdocj refdomainj]reftypenumrefrefexplicitrefwarnjtab2-3-3uhh^h!jIhMh j\ubh/X
) are read
and processed by the material and cross section processing module of
SCALE (XSProc). These are the first data read by the code and must be in
the order indicated. Data positions 6, 7 or 8, and 9 are read directly
by STARBUCS and may be entered in any order.}(hX
) are read
and processed by the material and cross section processing module of
SCALE (XSProc). These are the first data read by the code and must be in
the order indicated. Data positions 6, 7 or 8, and 9 are read directly
by STARBUCS and may be entered in any order.h j\hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh j\hhubh)}(h
.. _tab2-3-3:h]h}(h]h]h]h]h]htab2-3-3uhh
hM8h j\hhh!jIubj)}(hhh](h))}(h/Outline of input data for the STARBUCS sequenceh]h//Outline of input data for the STARBUCS sequence}(hjL]h jJ]ubah}(h]h]h]h]h]uhh(h!jIhMh jG]ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jX]ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jX]ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jX]ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jX]ubj0)}(hhh](j5)}(hhh](j:)}(hhh](h;)}(h**Data**h]hA)}(hj]h]h/Data}(hhh j]ubah}(h]h]h]h]h]uhh@h j]ubah}(h]h]h]h]h]uhh:h!jIhMh j]ubh;)}(h**position**h]hA)}(hj]h]h/position}(hhh j]ubah}(h]h]h]h]h]uhh@h j]ubah}(h]h]h]h]h]uhh:h!jIhMh j]ubeh}(h]h]h]h]h]uhj9h j]ubj:)}(hhh]h;)}(h**Type of
data**h]hA)}(hj]h]h/Type of
data}(hhh j]ubah}(h]h]h]h]h]uhh@h j]ubah}(h]h]h]h]h]uhh:h!jIhMh j]ubah}(h]h]h]h]h]uhj9h j]ubj:)}(hhh]h;)}(h**Data entry**h]hA)}(hj]h]h/
Data entry}(hhh j]ubah}(h]h]h]h]h]uhh@h j]ubah}(h]h]h]h]h]uhh:h!jIhMh j]ubah}(h]h]h]h]h]uhj9h j]ubj:)}(hhh]h;)}(h**Comments**h]hA)}(hj^h]h/Comments}(hhh j^ubah}(h]h]h]h]h]uhh@h j^ubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j]ubeh}(h]h]h]h]h]uhj4h j]ubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h j&^ubj:)}(hhh]h;)}(h
Sequence nameh]h/
Sequence name}(hj7^h j5^ubah}(h]h]h]h]h]uhh:h!jIhMh j2^ubah}(h]h]h]h]h]uhj9h j&^ubj:)}(hhh]h;)}(h =STARBUCSh]h/ =STARBUCS}(hjN^h jL^ubah}(h]h]h]h]h]uhh:h!jIhMh jI^ubah}(h]h]h]h]h]uhj9h j&^ubj:)}(hhh]h;)}(hStart in column
oneh]h/Start in column
one}(hje^h jc^ubah}(h]h]h]h]h]uhh:h!jIhMh j`^ubah}(h]h]h]h]h]uhj9h j&^ubeh}(h]h]h]h]h]uhj4h j]ubj5)}(hhh](j:)}(hhh]h;)}(hjzh]h/1}(hjzh j^ubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j}^ubj:)}(hhh]h;)}(hTITLEh]h/TITLE}(hj^h j^ubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j}^ubj:)}(hhh]h;)}(h
Enter a titleh]h/
Enter a title}(hj^h j^ubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j}^ubj:)}(hhh]h;)}(h
80 charactersh]h/
80 characters}(hj^h j^ubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j}^ubeh}(h]h]h]h]h]uhj4h j]ubj5)}(hhh](j:)}(hhh]h;)}(hj+h]h/2}(hj+h j^ubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j^ubj:)}(hhh](h;)}(hDStandard SCALE
pointwise or
multigroup
cross section
library name orh]h/DStandard SCALE
pointwise or
multigroup
cross section
library name or}(hj^h j^ubah}(h]h]h]h]h]uhh:h!jIhMh j^ubh;)}(haubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh]h;)}(h%Enter the
desired data
for each cycleh]h/%Enter the
desired data
for each cycle}(hjZah jXaubah}(h]h]h]h]h]uhh:h!jIhMUh jUaubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh]h;)}(hBegins this
data block with
READ HISTORY
(or BURNDATA)
and terminate
with
END HISTORY (or
BURNDATA).
See Burnup hist/
ory data sec.h]h/Begins this
data block with
READ HISTORY
(or BURNDATA)
and terminate
with
END HISTORY (or
BURNDATA).
See Burnup hist/
ory data sec.}(hjqah joaubah}(h]h]h]h]h]uhh:h!jIhMUh jlaubah}(h]h]h]h]h]uhj9h jaubeh}(h]h]h]h]h]uhj4h j]ubj5)}(hhh](j:)}(hhh]h;)}(h8\ :sup:`b`h](h/8 }(h8\ h jaubj)}(h:sup:`b`h]h/b}(hhh jaubah}(h]h]h]h]h]uhjh jaubeh}(h]h]h]h]h]uhh:h!jIhM`h jaubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh]h;)}(hSearch
parameter datah]h/Search
parameter data}(hjah jaubah}(h]h]h]h]h]uhh:h!jIhM`h jaubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh]h;)}(hEnter the
desired datah]h/Enter the
desired data}(hjah jaubah}(h]h]h]h]h]uhh:h!jIhM`h jaubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh]h;)}(hiBegins this
data block with
READ SEARCH and
terminate with
END SEARCH.
See Search para/
meter data sec.h]h/iBegins this
data block with
READ SEARCH and
terminate with
END SEARCH.
See Search para/
meter data sec.}(hjah jaubah}(h]h]h]h]h]uhh:h!jIhM`h jaubah}(h]h]h]h]h]uhj9h jaubeh}(h]h]h]h]h]uhj4h j]ubj5)}(hhh](j:)}(hhh]h;)}(h9h]h/9}(hjbh jbubah}(h]h]h]h]h]uhh:h!jIhMhh jbubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh]h;)}(h KENO datah]h/ KENO data}(hjbh jbubah}(h]h]h]h]h]uhh:h!jIhMhh jbubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh]h;)}(hEnter KENO
criticality
modelh]h/Enter KENO
criticality
model}(hj3bh j1bubah}(h]h]h]h]h]uhh:h!jIhMhh j.bubah}(h]h]h]h]h]uhj9h jaubj:)}(hhh](h;)}(h]Begins this
data block with
READ KENOVA (or
KENO5) and
terminate with
END KENOVA (or
KENO5).h]h/]Begins this
data block with
READ KENOVA (or
KENO5) and
terminate with
END KENOVA (or
KENO5).}(hjJbh jHbubah}(h]h]h]h]h]uhh:h!jIhMhh jEbubh;)}(hdFor KENO-VI use
block keyword
KENOVI (or
KENO6) in place
of KENOVA
(or KENO5). See
Keno Input Data.h]h/dFor KENO-VI use
block keyword
KENOVI (or
KENO6) in place
of KENOVA
(or KENO5). See
Keno Input Data.}(hjXbh jVbubah}(h]h]h]h]h]uhh:h!jIhMph jEbubeh}(h]h]h]h]h]uhj9h jaubeh}(h]h]h]h]h]uhj4h j]ubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jpbubj:)}(hhh]h;)}(hTerminate inputh]h/Terminate input}(hjbh jbubah}(h]h]h]h]h]uhh:h!jIhMxh j|bubah}(h]h]h]h]h]uhj9h jpbubj:)}(hhh]h;)}(hENDh]h/END}(hjbh jbubah}(h]h]h]h]h]uhh:h!jIhMxh jbubah}(h]h]h]h]h]uhj9h jpbubj:)}(hhh]h;)}(hMust begin in
column 1.h]h/Must begin in
column 1.}(hjbh jbubah}(h]h]h]h]h]uhh:h!jIhMxh jbubah}(h]h]h]h]h]uhj9h jpbubeh}(h]h]h]h]h]uhj4h j]ubj5)}(hhh](j:)}(hhh](h;)}(h:sup:`a` \Input
data required o\
nly for critica\
lity calculatio\
ns employing
multigroup
cross section
libraries. Only
one unit cell
may be defined
in the cell
data block for
STARBUCS.h](j)}(h:sup:`a`h]h/a}(hhh jbubah}(h]h]h]h]h]uhjh jbubh/ Input
data required o
nly for critica
lity calculatio
ns employing
multigroup
cross section
libraries. Only
one unit cell
may be defined
in the cell
data block for
STARBUCS.}(h \Input
data required o\
nly for critica\
lity calculatio\
ns employing
multigroup
cross section
libraries. Only
one unit cell
may be defined
in the cell
data block for
STARBUCS.h jbubeh}(h]h]h]h]h]uhh:h!jIhM{h jbubh;)}(hi:sup:`b` Either
burnup history
specification
or search
parameter data
may be defined
in a STARBUCS
input.h](j)}(h:sup:`b`h]h/b}(hhh jbubah}(h]h]h]h]h]uhjh jbubh/a Either
burnup history
specification
or search
parameter data
may be defined
in a STARBUCS
input.}(ha Either
burnup history
specification
or search
parameter data
may be defined
in a STARBUCS
input.h jbubeh}(h]h]h]h]h]uhh:h!jIhMh jbubeh}(h]h]h]h]h]uhj9h jbubj:)}(hhh]h}(h]h]h]h]h]uhj9h jbubj:)}(hhh]h}(h]h]h]h]h]uhj9h jbubj:)}(hhh]h}(h]h]h]h]h]uhj9h jbubeh}(h]h]h]h]h]uhj4h j]ubeh}(h]h]h]h]h]uhj/h jX]ubeh}(h]h]h]h]h]colsKuhjh jG]ubeh}(h](id90jF]eh]h]tab2-3-3ah]h]jcenteruhjh j\hhh!jIhNj}j@cj<]sj}jF]j<]subeh}(h]overview-of-input-structureah]h]overview of input structureah]h]uhh#h jYhhh!jIhMubh$)}(hhh](h))}(hSequence specification cardh]h/Sequence specification card}(hjSch jQchhh!NhNubah}(h]h]h]h]h]uhh(h jNchhh!jIhMubh;)}(hXThe STARBUCS analytical sequence is initiated with “=STARBUCS” beginning
in column 1 of the input. This instructs the SCALE driver module to
execute the STARBUCS sequence. The input data are then entered in
free-format. The input is terminated with the word “END” starting in
column 1. An “END” is a special data item, which may be used to delimit
an input data block, end an array of input items, and terminate the
input for the case. In the context of input data blocks, the “END” has a
name or label associated with it. An “END” used to terminate an array of
entries must not begin in column 1 as this instructs the SCALE driver to
terminate input to the sequence.h]h/XThe STARBUCS analytical sequence is initiated with “=STARBUCS” beginning
in column 1 of the input. This instructs the SCALE driver module to
execute the STARBUCS sequence. The input data are then entered in
free-format. The input is terminated with the word “END” starting in
column 1. An “END” is a special data item, which may be used to delimit
an input data block, end an array of input items, and terminate the
input for the case. In the context of input data blocks, the “END” has a
name or label associated with it. An “END” used to terminate an array of
entries must not begin in column 1 as this instructs the SCALE driver to
terminate input to the sequence.}(hjach j_chhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jNchhubeh}(h]sequence-specification-cardah]h]sequence specification cardah]h]uhh#h jYhhh!jIhMubh$)}(hhh](h))}(hOptional sequence parametersh]h/Optional sequence parameters}(hjzch jxchhh!NhNubah}(h]h]h]h]h]uhh(h juchhh!jIhMubh;)}(hTo check the input data, run STARBUCS and specify PARM=CHECK or PARM=CHK
after the analytical sequence specification as shown below.h]h/To check the input data, run STARBUCS and specify PARM=CHECK or PARM=CHK
after the analytical sequence specification as shown below.}(hjch jchhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh juchhubj)}(h=STARBUCS PARM=CHKh]h/=STARBUCS PARM=CHK}(hhh jcubah}(h]h]h]h]h]jjuhjh!jIhMh juchhubh;)}(hOther optional input for the PARM field to control multigroup resonance
self-shielding calculations are described in the XSProc section of this
manual.h]h/Other optional input for the PARM field to control multigroup resonance
self-shielding calculations are described in the XSProc section of this
manual.}(hjch jchhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh juchhubeh}(h]optional-sequence-parametersah]h]optional sequence parametersah]h]uhh#h jYhhh!jIhMubh$)}(hhh](h))}(hXSProch]h/XSProc}(hjch jchhh!NhNubah}(h]h]h]h]h]uhh(h jchhh!jIhMubh;)}(hXThe XSProc is used to read and process the standard composition
specification data that define the initial compositions of the fuel and
all structural materials in the problem, into mixing tables and unit
cell geometry information that are used by STARBUCS. All composition
data required for the problem are entered as standard composition
entries. A detailed description of this portion of the input can be
found in the section on XSProc (Chapter 7 (SECTIONREFERENCE)). Only one UO\ :sub:`2` fuel
type is permitted in STARBUCS. Therefore, a single fuel mixture defining
the fresh fuel composition and, for criticality safety calculations
employing multigroup cross sections, the geometry description of a
single fuel lattice cell are required in a STARBUCS input file. Only the
regular unit cells SQUAREPITCH, TRIANGPITCH, SPHSQUAREP, SPHTRIANGP, and
SYMMSLACELL may be specified for the LATTICECELL entry. Outside
diameters of the fuel, gap, and clad mixtures (i.e., not the radii) are
required.h](h/XThe XSProc is used to read and process the standard composition
specification data that define the initial compositions of the fuel and
all structural materials in the problem, into mixing tables and unit
cell geometry information that are used by STARBUCS. All composition
data required for the problem are entered as standard composition
entries. A detailed description of this portion of the input can be
found in the section on XSProc (Chapter 7 (SECTIONREFERENCE)). Only one UO }(hXThe XSProc is used to read and process the standard composition
specification data that define the initial compositions of the fuel and
all structural materials in the problem, into mixing tables and unit
cell geometry information that are used by STARBUCS. All composition
data required for the problem are entered as standard composition
entries. A detailed description of this portion of the input can be
found in the section on XSProc (Chapter 7 (SECTIONREFERENCE)). Only one UO\ h jchhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jcubah}(h]h]h]h]h]uhjh jcubh/X fuel
type is permitted in STARBUCS. Therefore, a single fuel mixture defining
the fresh fuel composition and, for criticality safety calculations
employing multigroup cross sections, the geometry description of a
single fuel lattice cell are required in a STARBUCS input file. Only the
regular unit cells SQUAREPITCH, TRIANGPITCH, SPHSQUAREP, SPHTRIANGP, and
SYMMSLACELL may be specified for the LATTICECELL entry. Outside
diameters of the fuel, gap, and clad mixtures (i.e., not the radii) are
required.}(hX fuel
type is permitted in STARBUCS. Therefore, a single fuel mixture defining
the fresh fuel composition and, for criticality safety calculations
employing multigroup cross sections, the geometry description of a
single fuel lattice cell are required in a STARBUCS input file. Only the
regular unit cells SQUAREPITCH, TRIANGPITCH, SPHSQUAREP, SPHTRIANGP, and
SYMMSLACELL may be specified for the LATTICECELL entry. Outside
diameters of the fuel, gap, and clad mixtures (i.e., not the radii) are
required.h jchhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jchhubeh}(h]xsprocah]h]xsprocah]h]uhh#h jYhhh!jIhMubh$)}(hhh](h))}(hControl parameter datah]h/Control parameter data}(hjch jchhh!NhNubah}(h]h]h]h]h]uhh(h jchhh!jIhMubh;)}(hXFThe control parameter data block allows the user to specify control
parameters and array data related to many of the burnup-credit analysis
parameters to be used in the problem. All input is by keyword entry. All
keywords are three-character identifiers that must be followed
immediately by an equals sign (“=”). The keywords may be in any order
within a data block. Input to the parameter data block is initiated with
the data block keywords **READ CONTROL** (only first four characters of
block name are required). The data block is terminated by the keywords
**END CONTROL**.h](h/XThe control parameter data block allows the user to specify control
parameters and array data related to many of the burnup-credit analysis
parameters to be used in the problem. All input is by keyword entry. All
keywords are three-character identifiers that must be followed
immediately by an equals sign (“=”). The keywords may be in any order
within a data block. Input to the parameter data block is initiated with
the data block keywords }(hXThe control parameter data block allows the user to specify control
parameters and array data related to many of the burnup-credit analysis
parameters to be used in the problem. All input is by keyword entry. All
keywords are three-character identifiers that must be followed
immediately by an equals sign (“=”). The keywords may be in any order
within a data block. Input to the parameter data block is initiated with
the data block keywords h jdhhh!NhNubhA)}(h**READ CONTROL**h]h/READ CONTROL}(hhh j
dubah}(h]h]h]h]h]uhh@h jdubh/g (only first four characters of
block name are required). The data block is terminated by the keywords
}(hg (only first four characters of
block name are required). The data block is terminated by the keywords
h jdhhh!NhNubhA)}(h**END CONTROL**h]h/END CONTROL}(hhh j dubah}(h]h]h]h]h]uhh@h jdubh/.}(hjh jdhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jchhubh;)}(hThe types of control parameter data that may be input are summarized in
Table 2.3.4. The individual keyword entries are described below.h]h/The types of control parameter data that may be input are summarized in
Table 2.3.4. The individual keyword entries are described below.}(hj:dh j8dhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jchhubj )}(hhh](j)}(hXARP= NAME OF THE ORIGEN LIBRARY TO BE USED. A character string with
the name of the ORIGEN library to be used in the depletion
calculation. This is a required entry. The library must be defined
in the SCALE text file ARPDATA.TXT that contains the cross section
library names and interpolation data used by ARP. A description of
an ARP input and the location of the ORIGEN cross section libraries
are provided in *ARP Input Description* located in the ORIGEN ARP
Module chapter. STARBUCS calculations are limited to UO\ :sub:`2`
spent fuels.
h]h;)}(hXARP= NAME OF THE ORIGEN LIBRARY TO BE USED. A character string with
the name of the ORIGEN library to be used in the depletion
calculation. This is a required entry. The library must be defined
in the SCALE text file ARPDATA.TXT that contains the cross section
library names and interpolation data used by ARP. A description of
an ARP input and the location of the ORIGEN cross section libraries
are provided in *ARP Input Description* located in the ORIGEN ARP
Module chapter. STARBUCS calculations are limited to UO\ :sub:`2`
spent fuels.h](h/XARP= NAME OF THE ORIGEN LIBRARY TO BE USED. A character string with
the name of the ORIGEN library to be used in the depletion
calculation. This is a required entry. The library must be defined
in the SCALE text file ARPDATA.TXT that contains the cross section
library names and interpolation data used by ARP. A description of
an ARP input and the location of the ORIGEN cross section libraries
are provided in }(hXARP= NAME OF THE ORIGEN LIBRARY TO BE USED. A character string with
the name of the ORIGEN library to be used in the depletion
calculation. This is a required entry. The library must be defined
in the SCALE text file ARPDATA.TXT that contains the cross section
library names and interpolation data used by ARP. A description of
an ARP input and the location of the ORIGEN cross section libraries
are provided in h jMdubh)}(h*ARP Input Description*h]h/ARP Input Description}(hhh jVdubah}(h]h]h]h]h]uhhh jMdubh/T located in the ORIGEN ARP
Module chapter. STARBUCS calculations are limited to UO }(hT located in the ORIGEN ARP
Module chapter. STARBUCS calculations are limited to UO\ h jMdubj)}(h:sub:`2`h]h/2}(hhh jidubah}(h]h]h]h]h]uhjh jMdubh/
spent fuels.}(h
spent fuels.h jMdubeh}(h]h]h]h]h]uhh:h!jIhMh jIdubah}(h]h]h]h]h]uhjh jFdhhh!jIhNubj)}(hXNAX= NUMBER OF AXIAL ZONES. This is the number of axial-burnup
subdivisions. For a user-input profile the value of NAX is
determined automatically by the code, and the NAX keyword is
optional, provided the AXP= array has been entered. The maximum
value of NAX must be chosen such that due product of NAX \* NHZ is
less than or equal to 100 (i.e., NAX:sub:`max` is 100, 50, 33, 25,
20, 16, or 14 when the number of horizontal zones is 1, 2, 3, 4, 5,
6, or 7, respectively). By default, the profile is automatically
normalized to unity by the code unless NPR=no. Built-in
burnup-dependent 18‑axial-zone profiles may be selected with an
entry of –18. These built-in profiles and the burnup range over
which they are applied, are listed in :numref:`tab2-3-5`. These profiles
have been proposed elsewhere (Ref. 2) as bounding axial profiles and
are included as options for convenience only. The default value of
NAX is –18 (use built-in profiles).
h]h;)}(hXNAX= NUMBER OF AXIAL ZONES. This is the number of axial-burnup
subdivisions. For a user-input profile the value of NAX is
determined automatically by the code, and the NAX keyword is
optional, provided the AXP= array has been entered. The maximum
value of NAX must be chosen such that due product of NAX \* NHZ is
less than or equal to 100 (i.e., NAX:sub:`max` is 100, 50, 33, 25,
20, 16, or 14 when the number of horizontal zones is 1, 2, 3, 4, 5,
6, or 7, respectively). By default, the profile is automatically
normalized to unity by the code unless NPR=no. Built-in
burnup-dependent 18‑axial-zone profiles may be selected with an
entry of –18. These built-in profiles and the burnup range over
which they are applied, are listed in :numref:`tab2-3-5`. These profiles
have been proposed elsewhere (Ref. 2) as bounding axial profiles and
are included as options for convenience only. The default value of
NAX is –18 (use built-in profiles).h](h/XeNAX= NUMBER OF AXIAL ZONES. This is the number of axial-burnup
subdivisions. For a user-input profile the value of NAX is
determined automatically by the code, and the NAX keyword is
optional, provided the AXP= array has been entered. The maximum
value of NAX must be chosen such that due product of NAX * NHZ is
less than or equal to 100 (i.e., NAX:sub:}(hXeNAX= NUMBER OF AXIAL ZONES. This is the number of axial-burnup
subdivisions. For a user-input profile the value of NAX is
determined automatically by the code, and the NAX keyword is
optional, provided the AXP= array has been entered. The maximum
value of NAX must be chosen such that due product of NAX \* NHZ is
less than or equal to 100 (i.e., NAX:sub:h jdubjV)}(h`max`h]h/max}(hhh jdubah}(h]h]h]h]h]uhjUh jdubh/X| is 100, 50, 33, 25,
20, 16, or 14 when the number of horizontal zones is 1, 2, 3, 4, 5,
6, or 7, respectively). By default, the profile is automatically
normalized to unity by the code unless NPR=no. Built-in
burnup-dependent 18‑axial-zone profiles may be selected with an
entry of –18. These built-in profiles and the burnup range over
which they are applied, are listed in }(hX| is 100, 50, 33, 25,
20, 16, or 14 when the number of horizontal zones is 1, 2, 3, 4, 5,
6, or 7, respectively). By default, the profile is automatically
normalized to unity by the code unless NPR=no. Built-in
burnup-dependent 18‑axial-zone profiles may be selected with an
entry of –18. These built-in profiles and the burnup range over
which they are applied, are listed in h jdubh_)}(h:numref:`tab2-3-5`h]j)}(hjdh]h/tab2-3-5}(hhh jdubah}(h]h](jstd
std-numrefeh]h]h]uhjh jdubah}(h]h]h]h]h]refdocj refdomainjdreftypenumrefrefexplicitrefwarnjtab2-3-5uhh^h!jIhMh jdubh/. These profiles
have been proposed elsewhere (Ref. 2) as bounding axial profiles and
are included as options for convenience only. The default value of
NAX is –18 (use built-in profiles).}(h. These profiles
have been proposed elsewhere (Ref. 2) as bounding axial profiles and
are included as options for convenience only. The default value of
NAX is –18 (use built-in profiles).h jdubeh}(h]h]h]h]h]uhh:h!jIhMh jdubah}(h]h]h]h]h]uhjh jFdhhh!jIhNubj)}(hXNHZ= NUMBER OF HORIZONTAL ZONES. This is the number of
horizontal-burnup subdivisions in the assembly. An optional entry if
no horizontal profile is requested. The maximum value is seven
zones. The exact limit is determined by the number of mixtures
defined in the lattice cell description. If a gap and second
moderator type are used the number of horizontal zones is limited to
five.
h]h;)}(hXNHZ= NUMBER OF HORIZONTAL ZONES. This is the number of
horizontal-burnup subdivisions in the assembly. An optional entry if
no horizontal profile is requested. The maximum value is seven
zones. The exact limit is determined by the number of mixtures
defined in the lattice cell description. If a gap and second
moderator type are used the number of horizontal zones is limited to
five.h]h/XNHZ= NUMBER OF HORIZONTAL ZONES. This is the number of
horizontal-burnup subdivisions in the assembly. An optional entry if
no horizontal profile is requested. The maximum value is seven
zones. The exact limit is determined by the number of mixtures
defined in the lattice cell description. If a gap and second
moderator type are used the number of horizontal zones is limited to
five.}(hjdh jdubah}(h]h]h]h]h]uhh:h!jIhMh jdubah}(h]h]h]h]h]uhjh jFdhhh!jIhNubj)}(hXNUC= BURNUP-CREDIT NUCLIDES used in the criticality calculation. A
list of actinides and/or fission products that are to be included in
the KENO criticality safety calculation. This is an array entry
keyword and is delimited by the keyword END. The nuclides are
entered using their standard composition alphanumeric names, as
listed in the Standard Composition Library chapter of the SCALE
manual. Isotopic correction factors may be entered, optionally,
immediately following the nuclide name. The isotopic correction
factors will be multiplied times the spent fuel nuclide
concentrations to account for isotopic composition bias.
The concentration of any nuclide that does not have a correction
factor is not adjusted. To select all available actinide and fission
product nuclides (with cross section data and atom densities greater
than 1.0E−29) for the criticality calculation, the user may select
NUC= ALL, without an END terminator. This is the only situation
where an array entry does not require an END. Note that the set of
nuclides tracked by ORIGEN in any decay or irradiation calculation,
documented in the ORIGEN Reaction Resource Contents chapter, is much
larger than the set of nuclides with available cross sections for
neutron transport calculations, documented in the SCALE Cross
Section Libraries chapter. Only nuclides with available cross
sections for neutron transport calculations are included in the
irradiated fuel compositions for criticality calculations.
h]h;)}(hXNUC= BURNUP-CREDIT NUCLIDES used in the criticality calculation. A
list of actinides and/or fission products that are to be included in
the KENO criticality safety calculation. This is an array entry
keyword and is delimited by the keyword END. The nuclides are
entered using their standard composition alphanumeric names, as
listed in the Standard Composition Library chapter of the SCALE
manual. Isotopic correction factors may be entered, optionally,
immediately following the nuclide name. The isotopic correction
factors will be multiplied times the spent fuel nuclide
concentrations to account for isotopic composition bias.
The concentration of any nuclide that does not have a correction
factor is not adjusted. To select all available actinide and fission
product nuclides (with cross section data and atom densities greater
than 1.0E−29) for the criticality calculation, the user may select
NUC= ALL, without an END terminator. This is the only situation
where an array entry does not require an END. Note that the set of
nuclides tracked by ORIGEN in any decay or irradiation calculation,
documented in the ORIGEN Reaction Resource Contents chapter, is much
larger than the set of nuclides with available cross sections for
neutron transport calculations, documented in the SCALE Cross
Section Libraries chapter. Only nuclides with available cross
sections for neutron transport calculations are included in the
irradiated fuel compositions for criticality calculations.h]h/XNUC= BURNUP-CREDIT NUCLIDES used in the criticality calculation. A
list of actinides and/or fission products that are to be included in
the KENO criticality safety calculation. This is an array entry
keyword and is delimited by the keyword END. The nuclides are
entered using their standard composition alphanumeric names, as
listed in the Standard Composition Library chapter of the SCALE
manual. Isotopic correction factors may be entered, optionally,
immediately following the nuclide name. The isotopic correction
factors will be multiplied times the spent fuel nuclide
concentrations to account for isotopic composition bias.
The concentration of any nuclide that does not have a correction
factor is not adjusted. To select all available actinide and fission
product nuclides (with cross section data and atom densities greater
than 1.0E−29) for the criticality calculation, the user may select
NUC= ALL, without an END terminator. This is the only situation
where an array entry does not require an END. Note that the set of
nuclides tracked by ORIGEN in any decay or irradiation calculation,
documented in the ORIGEN Reaction Resource Contents chapter, is much
larger than the set of nuclides with available cross sections for
neutron transport calculations, documented in the SCALE Cross
Section Libraries chapter. Only nuclides with available cross
sections for neutron transport calculations are included in the
irradiated fuel compositions for criticality calculations.}(hjdh jdubah}(h]h]h]h]h]uhh:h!jIhMh jdubah}(h]h]h]h]h]uhjh jFdhhh!jIhNubj)}(hXFLE= FUEL LIGHT ELEMENT NUCLIDES. A user-provided list of light
element nuclides that are to be included in the irradiated fuel
compositions for a CSAS5 or a CSAS6 calculation. This is an array
entry keyword and is delimited by the keyword END. The nuclides are
entered using their standard composition alphanumeric names, as
listed in Standard Composition Library chapter of the SCALE manual.
To select all available light element nuclides (with cross section
data and atom densities greater than 1.0E−29) for the criticality
calculation, the user may specify FLE= ALL, without an END
terminator. This is the only situation where an array entry does not
require an END. The use of the keyword FLE is not required if only
o-16 is to be included in the composition of irradiated uranium
oxide fuel pellets. For these material mixtures, o-16 will be
automatically included in irradiated fuel compositions due to its
significant concentration. Isotopic correction factors are not
allowed for light element nuclides. Note that the set of nuclides
tracked by ORIGEN in any decay or irradiation calculation,
documented in the ORIGEN Reaction Resource Contents chapter, is much
larger than the set of nuclides with available cross sections for
neutron transport calculations, documented in the SCALE Cross
Section Libraries chapter. Only nuclides with available cross
sections for neutron transport calculations are included in the
irradiated fuel compositions for criticality calculations.
h]h;)}(hXFLE= FUEL LIGHT ELEMENT NUCLIDES. A user-provided list of light
element nuclides that are to be included in the irradiated fuel
compositions for a CSAS5 or a CSAS6 calculation. This is an array
entry keyword and is delimited by the keyword END. The nuclides are
entered using their standard composition alphanumeric names, as
listed in Standard Composition Library chapter of the SCALE manual.
To select all available light element nuclides (with cross section
data and atom densities greater than 1.0E−29) for the criticality
calculation, the user may specify FLE= ALL, without an END
terminator. This is the only situation where an array entry does not
require an END. The use of the keyword FLE is not required if only
o-16 is to be included in the composition of irradiated uranium
oxide fuel pellets. For these material mixtures, o-16 will be
automatically included in irradiated fuel compositions due to its
significant concentration. Isotopic correction factors are not
allowed for light element nuclides. Note that the set of nuclides
tracked by ORIGEN in any decay or irradiation calculation,
documented in the ORIGEN Reaction Resource Contents chapter, is much
larger than the set of nuclides with available cross sections for
neutron transport calculations, documented in the SCALE Cross
Section Libraries chapter. Only nuclides with available cross
sections for neutron transport calculations are included in the
irradiated fuel compositions for criticality calculations.h]h/XFLE= FUEL LIGHT ELEMENT NUCLIDES. A user-provided list of light
element nuclides that are to be included in the irradiated fuel
compositions for a CSAS5 or a CSAS6 calculation. This is an array
entry keyword and is delimited by the keyword END. The nuclides are
entered using their standard composition alphanumeric names, as
listed in Standard Composition Library chapter of the SCALE manual.
To select all available light element nuclides (with cross section
data and atom densities greater than 1.0E−29) for the criticality
calculation, the user may specify FLE= ALL, without an END
terminator. This is the only situation where an array entry does not
require an END. The use of the keyword FLE is not required if only
o-16 is to be included in the composition of irradiated uranium
oxide fuel pellets. For these material mixtures, o-16 will be
automatically included in irradiated fuel compositions due to its
significant concentration. Isotopic correction factors are not
allowed for light element nuclides. Note that the set of nuclides
tracked by ORIGEN in any decay or irradiation calculation,
documented in the ORIGEN Reaction Resource Contents chapter, is much
larger than the set of nuclides with available cross sections for
neutron transport calculations, documented in the SCALE Cross
Section Libraries chapter. Only nuclides with available cross
sections for neutron transport calculations are included in the
irradiated fuel compositions for criticality calculations.}(hjeh j
eubah}(h]h]h]h]h]uhh:h!jIhMh j eubah}(h]h]h]h]h]uhjh jFdhhh!jIhNubj)}(hXKAXP= AXIAL-BURNUP PROFILE. The user-supplied axial-burnup profile of
the assembly to be used in the analysis. This entry is required
unless use of the built-in burnup-dependent axial profiles shown in
:numref:`tab2-3-5` is requested (NAX= −18). If NAX is set to anything other
than −18, the AXP array must contain NAX entries. Otherwise, the
value of NAX is determined automatically by the code. By default
(NPR=yes), the profile is automatically normalized by the code; this
may be disabled by setting NPR=no. If the burnup profile is
normalized, it is implicitly assumed that the height/volume of each
axial region is uniform when determining the average fuel burnup
(i.e., the burnup of each axial region is equally weighted). **The
user is cautioned that if fuel region subdivisions of unequal volume
are used, normalization should not be applied and the user must
ensure a correct correspondence between the axial-profile input and
the axial regions specified in the criticality calculation. AXP** is
an array entry and must be delimited by an END that must not start
in the first column.
h]h;)}(hXJAXP= AXIAL-BURNUP PROFILE. The user-supplied axial-burnup profile of
the assembly to be used in the analysis. This entry is required
unless use of the built-in burnup-dependent axial profiles shown in
:numref:`tab2-3-5` is requested (NAX= −18). If NAX is set to anything other
than −18, the AXP array must contain NAX entries. Otherwise, the
value of NAX is determined automatically by the code. By default
(NPR=yes), the profile is automatically normalized by the code; this
may be disabled by setting NPR=no. If the burnup profile is
normalized, it is implicitly assumed that the height/volume of each
axial region is uniform when determining the average fuel burnup
(i.e., the burnup of each axial region is equally weighted). **The
user is cautioned that if fuel region subdivisions of unequal volume
are used, normalization should not be applied and the user must
ensure a correct correspondence between the axial-profile input and
the axial regions specified in the criticality calculation. AXP** is
an array entry and must be delimited by an END that must not start
in the first column.h](h/AXP= AXIAL-BURNUP PROFILE. The user-supplied axial-burnup profile of
the assembly to be used in the analysis. This entry is required
unless use of the built-in burnup-dependent axial profiles shown in
}(hAXP= AXIAL-BURNUP PROFILE. The user-supplied axial-burnup profile of
the assembly to be used in the analysis. This entry is required
unless use of the built-in burnup-dependent axial profiles shown in
h j%eubh_)}(h:numref:`tab2-3-5`h]j)}(hj0eh]h/tab2-3-5}(hhh j2eubah}(h]h](jstd
std-numrefeh]h]h]uhjh j.eubah}(h]h]h]h]h]refdocj refdomainj 0. NAX
entries that
define the
axial-burnup
shape. The
profile is
automatically
normalized if
NPR=YES
(default).
Delimited by
END.h]h/Axial-burnup-pr
ofile
array. Required
if NAX > 0. NAX
entries that
define the
axial-burnup
shape. The
profile is
automatically
normalized if
NPR=YES
(default).
Delimited by
END.}(hjjh jjubah}(h]h]h]h]h]uhh:h!jIhMh jjubah}(h]h]h]h]h]uhj9h jiubeh}(h]h]h]h]h]uhj4h j]fubj5)}(hhh](j:)}(hhh]h;)}(hHZP=h]h/HZP=}(hj1jh j/jubah}(h]h]h]h]h]uhh:h!jIhMh j,jubah}(h]h]h]h]h]uhj9h j)jubj:)}(hhh]h;)}(hReal array\
:sup:`a`h](h/Real array
}(hReal array\
h jFjubj)}(h:sup:`a`h]h/a}(hhh jOjubah}(h]h]h]h]h]uhjh jFjubeh}(h]h]h]h]h]uhh:h!jIhMh jCjubah}(h]h]h]h]h]uhj9h j)jubj:)}(hhh]h;)}(hNoneh]h/None}(hjnjh jljubah}(h]h]h]h]h]uhh:h!jIhMh jijubah}(h]h]h]h]h]uhj9h j)jubj:)}(hhh]h;)}(hHorizontal-burn
up-profile
array. Required
if NHZ > 1.
Array containin
g
NHZ entries
that define the
horizontal,
or radial,
burnup profile
for the
analysis. Array
is
automatically
normalized by
the code.
Delimited by
END.h]h/Horizontal-burn
up-profile
array. Required
if NHZ > 1.
Array containin
g
NHZ entries
that define the
horizontal,
or radial,
burnup profile
for the
analysis. Array
is
automatically
normalized by
the code.
Delimited by
END.}(hjjh jjubah}(h]h]h]h]h]uhh:h!jIhMh jjubah}(h]h]h]h]h]uhj9h j)jubeh}(h]h]h]h]h]uhj4h j]fubj5)}(hhh](j:)}(hhh]h;)}(hMOD=h]h/MOD=}(hjjh jjubah}(h]h]h]h]h]uhh:h!jIhMh jjubah}(h]h]h]h]h]uhj9h jjubj:)}(hhh]h;)}(hReal array\
:sup:`a`h](h/Real array
}(hReal array\
h jjubj)}(h:sup:`a`h]h/a}(hhh jjubah}(h]h]h]h]h]uhjh jjubeh}(h]h]h]h]h]uhh:h!jIhMh jjubah}(h]h]h]h]h]uhj9h jjubj:)}(hhh]h;)}(hNoneh]h/None}(hjjh jjubah}(h]h]h]h]h]uhh:h!jIhMh jjubah}(h]h]h]h]h]uhj9h jjubj:)}(hhh]h;)}(hXOAxial-moderator
density,
applied in the
fuel depletion
analysis.
Note that MOD=
is required
only if the
ORIGEN library
contains
variable
moderator
density cross
sections.
NAX entries
ordered as AXP=
array.
Delimited by
END. Moderator
density default
values are not
available in
STARBUCS for
variable
moderator
density cross
sections.h]h/XOAxial-moderator
density,
applied in the
fuel depletion
analysis.
Note that MOD=
is required
only if the
ORIGEN library
contains
variable
moderator
density cross
sections.
NAX entries
ordered as AXP=
array.
Delimited by
END. Moderator
density default
values are not
available in
STARBUCS for
variable
moderator
density cross
sections.}(hjjh jjubah}(h]h]h]h]h]uhh:h!jIhMh jjubah}(h]h]h]h]h]uhj9h jjubeh}(h]h]h]h]h]uhj4h j]fubj5)}(hhh](j:)}(hhh]h;)}(hFIX=h]h/FIX=}(hjkh jkubah}(h]h]h]h]h]uhh:h!jIhMh jkubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(h Characterh]h/ Character}(hj0kh j.kubah}(h]h]h]h]h]uhh:h!jIhMh j+kubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(hNoh]h/No}(hjGkh jEkubah}(h]h]h]h]h]uhh:h!jIhMh jBkubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(hrOption to
select a
constant
specific power
level for all
axial and
horizontal
zones of the
assembly using
FIX=yes.h]h/rOption to
select a
constant
specific power
level for all
axial and
horizontal
zones of the
assembly using
FIX=yes.}(hj^kh j\kubah}(h]h]h]h]h]uhh:h!jIhMh jYkubah}(h]h]h]h]h]uhj9h jkubeh}(h]h]h]h]h]uhj4h j]fubj5)}(hhh](j:)}(hhh]h;)}(hNPR=h]h/NPR=}(hj~kh j|kubah}(h]h]h]h]h]uhh:h!jIhMh jykubah}(h]h]h]h]h]uhj9h jvkubj:)}(hhh]h;)}(h Characterh]h/ Character}(hjkh jkubah}(h]h]h]h]h]uhh:h!jIhMh jkubah}(h]h]h]h]h]uhj9h jvkubj:)}(hhh]h;)}(hYesh]h/Yes}(hjkh jkubah}(h]h]h]h]h]uhh:h!jIhMh jkubah}(h]h]h]h]h]uhj9h jvkubj:)}(hhh]h;)}(hvOption to
normalize
user-input
axial- and
horizontal-burn
up
profiles.
Default is to
automatically
normalize
profiles.h]h/vOption to
normalize
user-input
axial- and
horizontal-burn
up
profiles.
Default is to
automatically
normalize
profiles.}(hjkh jkubah}(h]h]h]h]h]uhh:h!jIhMh jkubah}(h]h]h]h]h]uhj9h jvkubeh}(h]h]h]h]h]uhj4h j]fubj5)}(hhh](j:)}(hhh]h;)}(hBUG=h]h/BUG=}(hjkh jkubah}(h]h]h]h]h]uhh:h!jIhMh jkubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(h Characterh]h/ Character}(hjkh jkubah}(h]h]h]h]h]uhh:h!jIhMh jkubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(hNoh]h/No}(hjlh jlubah}(h]h]h]h]h]uhh:h!jIhMh jlubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(h%Optional debug
printout with
BUG=yes.h]h/%Optional debug
printout with
BUG=yes.}(hj(lh j&lubah}(h]h]h]h]h]uhh:h!jIhMh j#lubah}(h]h]h]h]h]uhj9h jkubeh}(h]h]h]h]h]uhj4h j]fubj5)}(hhh](j:)}(hhh]h;)}(hEND CONTROLh]h/END CONTROL}(hjHlh jFlubah}(h]h]h]h]h]uhh:h!jIhMh jClubah}(h]h]h]h]h]uhj9h j@lubj:)}(hhh]h}(h]h]h]h]h]uhj9h j@lubj:)}(hhh]h;)}(h*End of the
control
parameter block
of datah]h/*End of the
control
parameter block
of data}(hjhlh jflubah}(h]h]h]h]h]uhh:h!jIhMh jclubah}(h]h]h]h]h]uhj9h j@lubj:)}(hhh]h}(h]h]h]h]h]uhj9h j@lubeh}(h]h]h]h]h]uhj4h j]fubj5)}(hhh](j:)}(hhh]h definition_list)}(hhh](h definition_list_item)}(hU:sup:`a` Termina\
te array data
entries with
end. Do not
place this end
in column 1.
h](h term)}(h:sup:`a` Termina\h](j)}(h:sup:`a`h]h/a}(hhh jlubah}(h]h]h]h]h]uhjh jlubh/ Termina}(h Termina\h jlubeh}(h]h]h]h]h]uhjlh!jIhM%h jlubh
definition)}(hhh]h;)}(hBte array data
entries with
end. Do not
place this end
in column 1.h]h/Bte array data
entries with
end. Do not
place this end
in column 1.}(hjlh jlubah}(h]h]h]h]h]uhh:h!jIhM!h jlubah}(h]h]h]h]h]uhjlh jlubeh}(h]h]h]h]h]uhjlh!jIhM%h jlubjl)}(hX:sup:`b` Note th\
at the set of
nuclides
tracked by
ORIGEN in any
decay or
irradiation
calculation,
documented in
the ORIGEN
Reaction
Resource
Contents
chapter, is
much larger
than the set of
nuclides with
available cross
sections for
neutron
transport
calculations,
documented in
the SCALE Cross
Section
Libraries
chapter. Only
nuclides with
available cross
sections for
neutron
transport
calculations
are included in
the irradiated
fuel
compositions
for criticality
calculations.h](jl)}(h:sup:`b` Note th\h](j)}(h:sup:`b`h]h/b}(hhh jlubah}(h]h]h]h]h]uhjh jlubh/ Note th}(h Note th\h jlubeh}(h]h]h]h]h]uhjlh!jIhMLh jlubjl)}(hhh]h;)}(hXat the set of
nuclides
tracked by
ORIGEN in any
decay or
irradiation
calculation,
documented in
the ORIGEN
Reaction
Resource
Contents
chapter, is
much larger
than the set of
nuclides with
available cross
sections for
neutron
transport
calculations,
documented in
the SCALE Cross
Section
Libraries
chapter. Only
nuclides with
available cross
sections for
neutron
transport
calculations
are included in
the irradiated
fuel
compositions
for criticality
calculations.h]h/Xat the set of
nuclides
tracked by
ORIGEN in any
decay or
irradiation
calculation,
documented in
the ORIGEN
Reaction
Resource
Contents
chapter, is
much larger
than the set of
nuclides with
available cross
sections for
neutron
transport
calculations,
documented in
the SCALE Cross
Section
Libraries
chapter. Only
nuclides with
available cross
sections for
neutron
transport
calculations
are included in
the irradiated
fuel
compositions
for criticality
calculations.}(hjlh jlubah}(h]h]h]h]h]uhh:h!jIhM(h jlubah}(h]h]h]h]h]uhjlh jlubeh}(h]h]h]h]h]uhjlh!jIhMLh jlubeh}(h]h]h]h]h]uhjlh jlubah}(h]h]h]h]h]uhj9h jlubj:)}(hhh]h}(h]h]h]h]h]uhj9h jlubj:)}(hhh]h}(h]h]h]h]h]uhj9h jlubj:)}(hhh]h}(h]h]h]h]h]uhj9h jlubeh}(h]h]h]h]h]uhj4h j]fubeh}(h]h]h]h]h]uhj/h j2fubeh}(h]h]h]h]h]colsKuhjh j!fubeh}(h](id91j feh]h]tab2-3-4ah]h]jcenteruhjh jchhh!jIhNj}jUmjfsj}j fjfsubh)}(h
.. _tab2-3-5:h]h}(h]h]h]h]h]htab2-3-5uhh
hM}!h jchhh!jIubj)}(hhh](h))}(h\Built-in burnup-dependent axial profiles, NAX= 18 from :cite:`lancaster_actinide-only_1998`)h](h/7Built-in burnup-dependent axial profiles, NAX= 18 from }(h7Built-in burnup-dependent axial profiles, NAX= 18 from h jimubh_)}(hlancaster_actinide-only_1998h]he)}(hjtmh]h/[lancaster_actinide-only_1998]}(hhh jvmubah}(h]h]h]h]h]uhhdh jrmubah}(h]jKah]hwah]h]h] refdomainh|reftypeh~ reftargetjtmrefwarnsupport_smartquotesuhh^h!jIhMQh jimubh/)}(hj=h jimubeh}(h]h]h]h]h]uhh(h!jIhMQh jfmubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthK
uhj#h jmubj$)}(hhh]h}(h]h]h]h]h]colwidthK
uhj#h jmubj$)}(hhh]h}(h]h]h]h]h]colwidthK
uhj#h jmubj$)}(hhh]h}(h]h]h]h]h]colwidthK
uhj#h jmubj$)}(hhh]h}(h]h]h]h]h]colwidthK
uhj#h jmubj0)}(hhh](j5)}(hhh](j:)}(hhh](h;)}(h **Axial**h]hA)}(hjmh]h/Axial}(hhh jmubah}(h]h]h]h]h]uhh@h jmubah}(h]h]h]h]h]uhh:h!jIhMUh jmubh;)}(h**zone
no.**h]hA)}(hjmh]h/zone
no.}(hhh jmubah}(h]h]h]h]h]uhh@h jmubah}(h]h]h]h]h]uhh:h!jIhMWh jmubeh}(h]h]h]h]h]uhj9h jmubj:)}(hhh](h;)}(h**Fraction
of**h]hA)}(hjnh]h/Fraction
of}(hhh jnubah}(h]h]h]h]h]uhh@h j
nubah}(h]h]h]h]h]uhh:h!jIhMUh j
nubh;)}(h**core
height**h]hA)}(hj&nh]h/core
height}(hhh j(nubah}(h]h]h]h]h]uhh@h j$nubah}(h]h]h]h]h]uhh:h!jIhMXh j
nubeh}(h]h]h]h]h]uhj9h jmubj:)}(hhh]h;)}(h**Burnup
< 18 GWd/MT
U**h]hA)}(hjFnh]h/Burnup
< 18 GWd/MT
U}(hhh jHnubah}(h]h]h]h]h]uhh@h jDnubah}(h]h]h]h]h]uhh:h!jIhMUh jAnubah}(h]h]h]h]h]uhj9h jmubj:)}(hhh]h;)}(h!**18 ≤
Burnup
< 30 GWd/MT
U**h]hA)}(hjfnh]h/18 ≤
Burnup
< 30 GWd/MT
U}(hhh jhnubah}(h]h]h]h]h]uhh@h jdnubah}(h]h]h]h]h]uhh:h!jIhMUh janubah}(h]h]h]h]h]uhj9h jmubj:)}(hhh]h;)}(h**Burnup
≥ 30 GWd/MT
U**h]hA)}(hjnh]h/Burnup
≥ 30 GWd/MT
U}(hhh jnubah}(h]h]h]h]h]uhh@h jnubah}(h]h]h]h]h]uhh:h!jIhMUh jnubah}(h]h]h]h]h]uhj9h jmubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jnubj:)}(hhh]h}(h]h]h]h]h]uhj9h jnubj:)}(hhh]h;)}(h**1**h]hA)}(hjnh]h/1}(hhh jnubah}(h]h]h]h]h]uhh@h jnubah}(h]h]h]h]h]uhh:h!jIhM[h jnubah}(h]h]h]h]h]uhj9h jnubj:)}(hhh]h;)}(h**2**h]hA)}(hjnh]h/2}(hhh jnubah}(h]h]h]h]h]uhh@h jnubah}(h]h]h]h]h]uhh:h!jIhM[h jnubah}(h]h]h]h]h]uhj9h jnubj:)}(hhh]h;)}(h**3**h]hA)}(hjoh]h/3}(hhh joubah}(h]h]h]h]h]uhh@h jnubah}(h]h]h]h]h]uhh:h!jIhM[h jnubah}(h]h]h]h]h]uhj9h jnubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(hjzh]h/1}(hjzh j(oubah}(h]h]h]h]h]uhh:h!jIhM]h j%oubah}(h]h]h]h]h]uhj9h j"oubj:)}(hhh]h;)}(h0.0278h]h/0.0278}(hj@oh j>oubah}(h]h]h]h]h]uhh:h!jIhM]h j;oubah}(h]h]h]h]h]uhj9h j"oubj:)}(hhh]h;)}(h0.649h]h/0.649}(hjWoh jUoubah}(h]h]h]h]h]uhh:h!jIhM]h jRoubah}(h]h]h]h]h]uhj9h j"oubj:)}(hhh]h;)}(h0.668h]h/0.668}(hjnoh jloubah}(h]h]h]h]h]uhh:h!jIhM]h jioubah}(h]h]h]h]h]uhj9h j"oubj:)}(hhh]h;)}(h0.652h]h/0.652}(hjoh joubah}(h]h]h]h]h]uhh:h!jIhM]h joubah}(h]h]h]h]h]uhj9h j"oubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(hj+h]h/2}(hj+h joubah}(h]h]h]h]h]uhh:h!jIhM_h joubah}(h]h]h]h]h]uhj9h joubj:)}(hhh]h;)}(h0.0833h]h/0.0833}(hjoh joubah}(h]h]h]h]h]uhh:h!jIhM_h joubah}(h]h]h]h]h]uhj9h joubj:)}(hhh]h;)}(h1.044h]h/1.044}(hjoh joubah}(h]h]h]h]h]uhh:h!jIhM_h joubah}(h]h]h]h]h]uhj9h joubj:)}(hhh]h;)}(h1.034h]h/1.034}(hjoh joubah}(h]h]h]h]h]uhh:h!jIhM_h joubah}(h]h]h]h]h]uhj9h joubj:)}(hhh]h;)}(h0.967h]h/0.967}(hjph joubah}(h]h]h]h]h]uhh:h!jIhM_h joubah}(h]h]h]h]h]uhj9h joubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(hjh]h/3}(hjh jpubah}(h]h]h]h]h]uhh:h!jIhMah jpubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h0.1389h]h/0.1389}(hj6ph j4pubah}(h]h]h]h]h]uhh:h!jIhMah j1pubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h1.208h]h/1.208}(hjMph jKpubah}(h]h]h]h]h]uhh:h!jIhMah jHpubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h1.150h]h/1.150}(hjdph jbpubah}(h]h]h]h]h]uhh:h!jIhMah j_pubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h1.074h]h/1.074}(hj{ph jypubah}(h]h]h]h]h]uhh:h!jIhMah jvpubah}(h]h]h]h]h]uhj9h jpubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(hjm,h]h/4}(hjm,h jpubah}(h]h]h]h]h]uhh:h!jIhMch jpubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h0.1944h]h/0.1944}(hjph jpubah}(h]h]h]h]h]uhh:h!jIhMch jpubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h1.215h]h/1.215}(hjph jpubah}(h]h]h]h]h]uhh:h!jIhMch jpubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h1.094h]h/1.094}(hjph jpubah}(h]h]h]h]h]uhh:h!jIhMch jpubah}(h]h]h]h]h]uhj9h jpubj:)}(hhh]h;)}(h1.103h]h/1.103}(hjph jpubah}(h]h]h]h]h]uhh:h!jIhMch jpubah}(h]h]h]h]h]uhj9h jpubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(hj6-h]h/5}(hj6-h jqubah}(h]h]h]h]h]uhh:h!jIhMeh jqubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h0.2500h]h/0.2500}(hj,qh j*qubah}(h]h]h]h]h]uhh:h!jIhMeh j'qubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h1.214h]h/1.214}(hjCqh jAqubah}(h]h]h]h]h]uhh:h!jIhMeh j>qubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h1.053h]h/1.053}(hjZqh jXqubah}(h]h]h]h]h]uhh:h!jIhMeh jUqubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h1.108h]h/1.108}(hjqqh joqubah}(h]h]h]h]h]uhh:h!jIhMeh jlqubah}(h]h]h]h]h]uhj9h jqubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(hj`h]h/6}(hj`h jqubah}(h]h]h]h]h]uhh:h!jIhMgh jqubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h0.3056h]h/0.3056}(hjqh jqubah}(h]h]h]h]h]uhh:h!jIhMgh jqubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h1.208h]h/1.208}(hjqh jqubah}(h]h]h]h]h]uhh:h!jIhMgh jqubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h1.048h]h/1.048}(hjqh jqubah}(h]h]h]h]h]uhh:h!jIhMgh jqubah}(h]h]h]h]h]uhj9h jqubj:)}(hhh]h;)}(h1.106h]h/1.106}(hjqh jqubah}(h]h]h]h]h]uhh:h!jIhMgh jqubah}(h]h]h]h]h]uhj9h jqubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h7h]h/7}(hjrh j
rubah}(h]h]h]h]h]uhh:h!jIhMih jrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h0.3611h]h/0.3611}(hj#rh j!rubah}(h]h]h]h]h]uhh:h!jIhMih jrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.197h]h/1.197}(hj:rh j8rubah}(h]h]h]h]h]uhh:h!jIhMih j5rubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.064h]h/1.064}(hjQrh jOrubah}(h]h]h]h]h]uhh:h!jIhMih jLrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.102h]h/1.102}(hjhrh jfrubah}(h]h]h]h]h]uhh:h!jIhMih jcrubah}(h]h]h]h]h]uhj9h jrubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h8h]h/8}(hjrh jrubah}(h]h]h]h]h]uhh:h!jIhMkh jrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h0.4167h]h/0.4167}(hjrh jrubah}(h]h]h]h]h]uhh:h!jIhMkh jrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.189h]h/1.189}(hjrh jrubah}(h]h]h]h]h]uhh:h!jIhMkh jrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.095h]h/1.095}(hjrh jrubah}(h]h]h]h]h]uhh:h!jIhMkh jrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.097h]h/1.097}(hjrh jrubah}(h]h]h]h]h]uhh:h!jIhMkh jrubah}(h]h]h]h]h]uhj9h jrubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(hjbh]h/9}(hjbh jsubah}(h]h]h]h]h]uhh:h!jIhMmh jrubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h0.4722h]h/0.4722}(hjsh jsubah}(h]h]h]h]h]uhh:h!jIhMmh jsubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.188h]h/1.188}(hj1sh j/subah}(h]h]h]h]h]uhh:h!jIhMmh j,subah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.121h]h/1.121}(hjHsh jFsubah}(h]h]h]h]h]uhh:h!jIhMmh jCsubah}(h]h]h]h]h]uhj9h jrubj:)}(hhh]h;)}(h1.094h]h/1.094}(hj_sh j]subah}(h]h]h]h]h]uhh:h!jIhMmh jZsubah}(h]h]h]h]h]uhj9h jrubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h10h]h/10}(hjsh j}subah}(h]h]h]h]h]uhh:h!jIhMoh jzsubah}(h]h]h]h]h]uhj9h jwsubj:)}(hhh]h;)}(h0.5278h]h/0.5278}(hjsh jsubah}(h]h]h]h]h]uhh:h!jIhMoh jsubah}(h]h]h]h]h]uhj9h jwsubj:)}(hhh]h;)}(h1.192h]h/1.192}(hjsh jsubah}(h]h]h]h]h]uhh:h!jIhMoh jsubah}(h]h]h]h]h]uhj9h jwsubj:)}(hhh]h;)}(h1.135h]h/1.135}(hjsh jsubah}(h]h]h]h]h]uhh:h!jIhMoh jsubah}(h]h]h]h]h]uhj9h jwsubj:)}(hhh]h;)}(h1.094h]h/1.094}(hjsh jsubah}(h]h]h]h]h]uhh:h!jIhMoh jsubah}(h]h]h]h]h]uhj9h jwsubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h11h]h/11}(hjsh jsubah}(h]h]h]h]h]uhh:h!jIhMqh jsubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h;)}(h0.5833h]h/0.5833}(hjth jtubah}(h]h]h]h]h]uhh:h!jIhMqh j
tubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h;)}(h1.195h]h/1.195}(hj)th j'tubah}(h]h]h]h]h]uhh:h!jIhMqh j$tubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h;)}(h1.140h]h/1.140}(hj@th j>tubah}(h]h]h]h]h]uhh:h!jIhMqh j;tubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h;)}(h1.095h]h/1.095}(hjWth jUtubah}(h]h]h]h]h]uhh:h!jIhMqh jRtubah}(h]h]h]h]h]uhj9h jsubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h12h]h/12}(hjwth jutubah}(h]h]h]h]h]uhh:h!jIhMsh jrtubah}(h]h]h]h]h]uhj9h jotubj:)}(hhh]h;)}(h0.6389h]h/0.6389}(hjth jtubah}(h]h]h]h]h]uhh:h!jIhMsh jtubah}(h]h]h]h]h]uhj9h jotubj:)}(hhh]h;)}(h1.190h]h/1.190}(hjth jtubah}(h]h]h]h]h]uhh:h!jIhMsh jtubah}(h]h]h]h]h]uhj9h jotubj:)}(hhh]h;)}(h1.138h]h/1.138}(hjth jtubah}(h]h]h]h]h]uhh:h!jIhMsh jtubah}(h]h]h]h]h]uhj9h jotubj:)}(hhh]h;)}(h1.096h]h/1.096}(hjth jtubah}(h]h]h]h]h]uhh:h!jIhMsh jtubah}(h]h]h]h]h]uhj9h jotubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h13h]h/13}(hjth jtubah}(h]h]h]h]h]uhh:h!jIhMuh jtubah}(h]h]h]h]h]uhj9h jtubj:)}(hhh]h;)}(h0.6944h]h/0.6944}(hj
uh juubah}(h]h]h]h]h]uhh:h!jIhMuh juubah}(h]h]h]h]h]uhj9h jtubj:)}(hhh]h;)}(h1.156h]h/1.156}(hj!uh juubah}(h]h]h]h]h]uhh:h!jIhMuh juubah}(h]h]h]h]h]uhj9h jtubj:)}(hhh]h;)}(h1.130h]h/1.130}(hj8uh j6uubah}(h]h]h]h]h]uhh:h!jIhMuh j3uubah}(h]h]h]h]h]uhj9h jtubj:)}(hhh]h;)}(h1.095h]h/1.095}(hjOuh jMuubah}(h]h]h]h]h]uhh:h!jIhMuh jJuubah}(h]h]h]h]h]uhj9h jtubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h14h]h/14}(hjouh jmuubah}(h]h]h]h]h]uhh:h!jIhMwh jjuubah}(h]h]h]h]h]uhj9h jguubj:)}(hhh]h;)}(h0.7500h]h/0.7500}(hjuh juubah}(h]h]h]h]h]uhh:h!jIhMwh juubah}(h]h]h]h]h]uhj9h jguubj:)}(hhh]h;)}(h1.022h]h/1.022}(hjuh juubah}(h]h]h]h]h]uhh:h!jIhMwh juubah}(h]h]h]h]h]uhj9h jguubj:)}(hhh]h;)}(h1.106h]h/1.106}(hjuh juubah}(h]h]h]h]h]uhh:h!jIhMwh juubah}(h]h]h]h]h]uhj9h jguubj:)}(hhh]h;)}(h1.086h]h/1.086}(hjuh juubah}(h]h]h]h]h]uhh:h!jIhMwh juubah}(h]h]h]h]h]uhj9h jguubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h15h]h/15}(hjuh juubah}(h]h]h]h]h]uhh:h!jIhMyh juubah}(h]h]h]h]h]uhj9h juubj:)}(hhh]h;)}(h0.8056h]h/0.8056}(hjvh jvubah}(h]h]h]h]h]uhh:h!jIhMyh juubah}(h]h]h]h]h]uhj9h juubj:)}(hhh]h;)}(h0.756h]h/0.756}(hjvh jvubah}(h]h]h]h]h]uhh:h!jIhMyh jvubah}(h]h]h]h]h]uhj9h juubj:)}(hhh]h;)}(h1.049h]h/1.049}(hj0vh j.vubah}(h]h]h]h]h]uhh:h!jIhMyh j+vubah}(h]h]h]h]h]uhj9h juubj:)}(hhh]h;)}(h1.059h]h/1.059}(hjGvh jEvubah}(h]h]h]h]h]uhh:h!jIhMyh jBvubah}(h]h]h]h]h]uhj9h juubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h16h]h/16}(hjgvh jevubah}(h]h]h]h]h]uhh:h!jIhM{h jbvubah}(h]h]h]h]h]uhj9h j_vubj:)}(hhh]h;)}(h0.8611h]h/0.8611}(hj~vh j|vubah}(h]h]h]h]h]uhh:h!jIhM{h jyvubah}(h]h]h]h]h]uhj9h j_vubj:)}(hhh]h;)}(h0.614h]h/0.614}(hjvh jvubah}(h]h]h]h]h]uhh:h!jIhM{h jvubah}(h]h]h]h]h]uhj9h j_vubj:)}(hhh]h;)}(h0.933h]h/0.933}(hjvh jvubah}(h]h]h]h]h]uhh:h!jIhM{h jvubah}(h]h]h]h]h]uhj9h j_vubj:)}(hhh]h;)}(h0.971h]h/0.971}(hjvh jvubah}(h]h]h]h]h]uhh:h!jIhM{h jvubah}(h]h]h]h]h]uhj9h j_vubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h17h]h/17}(hjvh jvubah}(h]h]h]h]h]uhh:h!jIhM}h jvubah}(h]h]h]h]h]uhj9h jvubj:)}(hhh]h;)}(h0.9167h]h/0.9167}(hjvh jvubah}(h]h]h]h]h]uhh:h!jIhM}h jvubah}(h]h]h]h]h]uhj9h jvubj:)}(hhh]h;)}(h0.481h]h/0.481}(hjwh jwubah}(h]h]h]h]h]uhh:h!jIhM}h jwubah}(h]h]h]h]h]uhj9h jvubj:)}(hhh]h;)}(h0.669h]h/0.669}(hj(wh j&wubah}(h]h]h]h]h]uhh:h!jIhM}h j#wubah}(h]h]h]h]h]uhj9h jvubj:)}(hhh]h;)}(h0.738h]h/0.738}(hj?wh j=wubah}(h]h]h]h]h]uhh:h!jIhM}h j:wubah}(h]h]h]h]h]uhj9h jvubeh}(h]h]h]h]h]uhj4h jmubj5)}(hhh](j:)}(hhh]h;)}(h18h]h/18}(hj_wh j]wubah}(h]h]h]h]h]uhh:h!jIhMh jZwubah}(h]h]h]h]h]uhj9h jWwubj:)}(hhh]h;)}(h0.9722h]h/0.9722}(hjvwh jtwubah}(h]h]h]h]h]uhh:h!jIhMh jqwubah}(h]h]h]h]h]uhj9h jWwubj:)}(hhh]h;)}(h0.284h]h/0.284}(hjwh jwubah}(h]h]h]h]h]uhh:h!jIhMh jwubah}(h]h]h]h]h]uhj9h jWwubj:)}(hhh]h;)}(h0.373h]h/0.373}(hjwh jwubah}(h]h]h]h]h]uhh:h!jIhMh jwubah}(h]h]h]h]h]uhj9h jWwubj:)}(hhh]h;)}(h0.462h]h/0.462}(hjwh jwubah}(h]h]h]h]h]uhh:h!jIhMh jwubah}(h]h]h]h]h]uhj9h jWwubeh}(h]h]h]h]h]uhj4h jmubeh}(h]h]h]h]h]uhj/h jmubeh}(h]h]h]h]h]colsKuhjh jfmubeh}(h](id92jemeh]h]tab2-3-5ah]h]jcenteruhjh jchhh!jIhNj}jwj[msj}jemj[msubh)}(h.. _burnup-history-data:h]h}(h]h]h]h]h]hburnup-history-datauhh
hM!h jchhh!jIubeh}(h]control-parameter-dataah]h]control parameter dataah]h]uhh#h jYhhh!jIhMubh$)}(hhh](h))}(hBurnup history datah]h/Burnup history data}(hjxh jxhhh!NhNubah}(h]h]h]h]h]uhh(h jwhhh!jIhMubh;)}(hXThe burnup history data block defines the irradiation history for the
assembly. These data are entered by keyword. The keywords are summarized
in :numref:`tab2-3-6`. Only the first four characters of the keywords are
required (i.e., any characters after the first four characters are
optional). A minimum of two entries are required for each cycle, (1) the
average assembly power (POWER=) and (2) the irradiation time (BURN=).
The decay time (DOWN=), if any, at the end of the cycle, and the number
of cross section libraries (NLIB=) are optional. The word END is
required to delimit the entries for each cycle. The entries within a
given cycle may be in any order.h](h/The burnup history data block defines the irradiation history for the
assembly. These data are entered by keyword. The keywords are summarized
in }(hThe burnup history data block defines the irradiation history for the
assembly. These data are entered by keyword. The keywords are summarized
in h jxhhh!NhNubh_)}(h:numref:`tab2-3-6`h]j)}(hjxh]h/tab2-3-6}(hhh jxubah}(h]h](jstd
std-numrefeh]h]h]uhjh jxubah}(h]h]h]h]h]refdocj refdomainj&xreftypenumrefrefexplicitrefwarnjtab2-3-6uhh^h!jIhMh jxubh/X. Only the first four characters of the keywords are
required (i.e., any characters after the first four characters are
optional). A minimum of two entries are required for each cycle, (1) the
average assembly power (POWER=) and (2) the irradiation time (BURN=).
The decay time (DOWN=), if any, at the end of the cycle, and the number
of cross section libraries (NLIB=) are optional. The word END is
required to delimit the entries for each cycle. The entries within a
given cycle may be in any order.}(hX. Only the first four characters of the keywords are
required (i.e., any characters after the first four characters are
optional). A minimum of two entries are required for each cycle, (1) the
average assembly power (POWER=) and (2) the irradiation time (BURN=).
The decay time (DOWN=), if any, at the end of the cycle, and the number
of cross section libraries (NLIB=) are optional. The word END is
required to delimit the entries for each cycle. The entries within a
given cycle may be in any order.h jxhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jwhhubh;)}(hThe burnup history data block reading is initiated with the keywords
READ HISTORY (or BURNDATA) and terminated by END HISTORY (or BURNDATA).h]h/The burnup history data block reading is initiated with the keywords
READ HISTORY (or BURNDATA) and terminated by END HISTORY (or BURNDATA).}(hjExh jCxhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jwhhubh;)}(hXPOWER= The average specific power of the assembly for this cycle.
The units of the specific power are in MW/MTU (W/g) of initial uranium.
The axial and horizontal profiles are multiplied by the specific power
to achieve the desired spatially-dependent burnup profiles for the
assembly when FIX=NO (default). If FIX=YES, the specific power input
using this keyword is assumed to be uniform over all fuel regions (axial
and horizontal) and the code will adjust the irradiation time to obtain
the desired burnup for each region.h]h/XPOWER= The average specific power of the assembly for this cycle.
The units of the specific power are in MW/MTU (W/g) of initial uranium.
The axial and horizontal profiles are multiplied by the specific power
to achieve the desired spatially-dependent burnup profiles for the
assembly when FIX=NO (default). If FIX=YES, the specific power input
using this keyword is assumed to be uniform over all fuel regions (axial
and horizontal) and the code will adjust the irradiation time to obtain
the desired burnup for each region.}(hjSxh jQxhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jwhhubh;)}(hNBURN= THE IRRADIATION TIME FOR THIS CYCLE. The cycle irradiation time in
days.h]h/NBURN= THE IRRADIATION TIME FOR THIS CYCLE. The cycle irradiation time in
days.}(hjaxh j_xhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jwhhubh;)}(hXDOWN= CYCLE DOWN TIME. An optional entry to specify the down time, in
days, at the end of an irradiation cycle. The down time is simulated as
an irradiation time step of effectively zero power after the irradiation
cycle. The down time for the last cycle is simulated as a separate
ORIGEN decay case with nine equally-spaced time steps. If a negative
down time is input, the time steps are spaced logarithmically.h]h/XDOWN= CYCLE DOWN TIME. An optional entry to specify the down time, in
days, at the end of an irradiation cycle. The down time is simulated as
an irradiation time step of effectively zero power after the irradiation
cycle. The down time for the last cycle is simulated as a separate
ORIGEN decay case with nine equally-spaced time steps. If a negative
down time is input, the time steps are spaced logarithmically.}(hjoxh jmxhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jwhhubh;)}(hX>NLIB= LIBRARIES PER CYCLE. An optional entry to request multiple cross
section libraries during a depletion cycle. If requested, the code
automatically subdivides the cycle in NLIB segments of uniform duration
and generates a separate library for the depletion analysis for each
segment using ARP. Generating multiple libraries provides a more
accurate representation of the time-dependent cross section variation
during the burnup analysis. Each segment of the cycle is assumed to have
the same specific power, and no down time is assumed between each
segment of the cycle.h]h/X>NLIB= LIBRARIES PER CYCLE. An optional entry to request multiple cross
section libraries during a depletion cycle. If requested, the code
automatically subdivides the cycle in NLIB segments of uniform duration
and generates a separate library for the depletion analysis for each
segment using ARP. Generating multiple libraries provides a more
accurate representation of the time-dependent cross section variation
during the burnup analysis. Each segment of the cycle is assumed to have
the same specific power, and no down time is assumed between each
segment of the cycle.}(hj}xh j{xhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jwhhubh;)}(hCEND The word END is required to terminate the input for each cycle.h]h/CEND The word END is required to terminate the input for each cycle.}(hjxh jxhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jwhhubh;)}(hVRepeat the above entries for each cycle to define the complete assembly
power history.h]h/VRepeat the above entries for each cycle to define the complete assembly
power history.}(hjxh jxhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jwhhubh)}(h
.. _tab2-3-6:h]h}(h]h]h]h]h]htab2-3-6uhh
hM!h jwhhh!jIubj)}(hhh](h))}(hTable of power history data.h]h/Table of power history data.}(hjxh jxubah}(h]h]h]h]h]uhh(h!jIhMh jxubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jxubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jxubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jxubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jxubj0)}(hhh](j5)}(hhh](j:)}(hhh](h;)}(h**Keyword**h]hA)}(hjxh]h/Keyword}(hhh jxubah}(h]h]h]h]h]uhh@h jxubah}(h]h]h]h]h]uhh:h!jIhMh jxubh;)}(h**name**h]hA)}(hjyh]h/name}(hhh jyubah}(h]h]h]h]h]uhh@h jyubah}(h]h]h]h]h]uhh:h!jIhMh jxubeh}(h]h]h]h]h]uhj9h jxubj:)}(hhh](h;)}(h**Data**h]hA)}(hj.yh]h/Data}(hhh j0yubah}(h]h]h]h]h]uhh@h j,yubah}(h]h]h]h]h]uhh:h!jIhMh j)yubh;)}(h**type**h]hA)}(hjEyh]h/type}(hhh jGyubah}(h]h]h]h]h]uhh@h jCyubah}(h]h]h]h]h]uhh:h!jIhMh j)yubeh}(h]h]h]h]h]uhj9h jxubj:)}(hhh](h;)}(h**Default**h]hA)}(hjeyh]h/Default}(hhh jgyubah}(h]h]h]h]h]uhh@h jcyubah}(h]h]h]h]h]uhh:h!jIhMh j`yubh;)}(h **value**h]hA)}(hj|yh]h/value}(hhh j~yubah}(h]h]h]h]h]uhh@h jzyubah}(h]h]h]h]h]uhh:h!jIhMh j`yubeh}(h]h]h]h]h]uhj9h jxubj:)}(hhh]h;)}(h**Comments**h]hA)}(hjyh]h/Comments}(hhh jyubah}(h]h]h]h]h]uhh@h jyubah}(h]h]h]h]h]uhh:h!jIhMh jyubah}(h]h]h]h]h]uhj9h jxubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(h$READ HISTORY
(or BURNDATA)\
:sup:`a`h](h/READ HISTORY
(or BURNDATA)
}(hREAD HISTORY
(or BURNDATA)\
h jyubj)}(h:sup:`a`h]h/a}(hhh jyubah}(h]h]h]h]h]uhjh jyubeh}(h]h]h]h]h]uhh:h!jIhMh jyubah}(h]h]h]h]h]uhj9h jyubj:)}(hhh]h}(h]h]h]h]h]uhj9h jyubj:)}(hhh]h}(h]h]h]h]h]uhj9h jyubj:)}(hhh]h;)}(h"Start of burnup
history data
blockh]h/"Start of burnup
history data
block}(hjyh jyubah}(h]h]h]h]h]uhh:h!jIhMh jyubah}(h]h]h]h]h]uhj9h jyubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(hPOWER=h]h/POWER=}(hjzh jzubah}(h]h]h]h]h]uhh:h!jIhMh jzubah}(h]h]h]h]h]uhj9h jzubj:)}(hhh]h;)}(h
Real variableh]h/
Real variable}(hj4zh j2zubah}(h]h]h]h]h]uhh:h!jIhMh j/zubah}(h]h]h]h]h]uhj9h jzubj:)}(hhh]h;)}(hNoneh]h/None}(hjKzh jIzubah}(h]h]h]h]h]uhh:h!jIhMh jFzubah}(h]h]h]h]h]uhj9h jzubj:)}(hhh]h;)}(h.Average
assembly power
for this cycle
(MW/MTU)h]h/.Average
assembly power
for this cycle
(MW/MTU)}(hjbzh j`zubah}(h]h]h]h]h]uhh:h!jIhMh j]zubah}(h]h]h]h]h]uhj9h jzubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(hBURN=h]h/BURN=}(hjzh jzubah}(h]h]h]h]h]uhh:h!jIhMh j}zubah}(h]h]h]h]h]uhj9h jzzubj:)}(hhh]h;)}(h
Real variableh]h/
Real variable}(hjzh jzubah}(h]h]h]h]h]uhh:h!jIhMh jzubah}(h]h]h]h]h]uhj9h jzzubj:)}(hhh]h;)}(hNoneh]h/None}(hjzh jzubah}(h]h]h]h]h]uhh:h!jIhMh jzubah}(h]h]h]h]h]uhj9h jzzubj:)}(hhh]h;)}(hCycle
irradiation
time (days)h]h/Cycle
irradiation
time (days)}(hjzh jzubah}(h]h]h]h]h]uhh:h!jIhMh jzubah}(h]h]h]h]h]uhj9h jzzubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(hDOWN=h]h/DOWN=}(hjzh jzubah}(h]h]h]h]h]uhh:h!jIhMh jzubah}(h]h]h]h]h]uhj9h jzubj:)}(hhh]h;)}(h
Real variableh]h/
Real variable}(hjzh jzubah}(h]h]h]h]h]uhh:h!jIhMh jzubah}(h]h]h]h]h]uhj9h jzubj:)}(hhh]h;)}(hjh]h/0}(hjh j{ubah}(h]h]h]h]h]uhh:h!jIhMh j{ubah}(h]h]h]h]h]uhj9h jzubj:)}(hhh]h;)}(hEnd-of-cycle
decay time
(days).
Optional. A
negative down
time may be
used to select
logarithmic
decay time
intervals for
the last decay
case.h]h/End-of-cycle
decay time
(days).
Optional. A
negative down
time may be
used to select
logarithmic
decay time
intervals for
the last decay
case.}(hj+{h j){ubah}(h]h]h]h]h]uhh:h!jIhMh j&{ubah}(h]h]h]h]h]uhj9h jzubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(hNLIB/CYCLE=h]h/NLIB/CYCLE=}(hjK{h jI{ubah}(h]h]h]h]h]uhh:h!jIhMh jF{ubah}(h]h]h]h]h]uhj9h jC{ubj:)}(hhh]h;)}(hInteger
variableh]h/Integer
variable}(hjb{h j`{ubah}(h]h]h]h]h]uhh:h!jIhMh j]{ubah}(h]h]h]h]h]uhj9h jC{ubj:)}(hhh]h;)}(hjzh]h/1}(hjzh jw{ubah}(h]h]h]h]h]uhh:h!jIhMh jt{ubah}(h]h]h]h]h]uhj9h jC{ubj:)}(hhh]h;)}(hXNumber of
libraries to be
applied in this
cycle.
Optional.
If multiple
libraries are
requested for
this cycle, the
cycle is
subdivided into
equal time
segments, and
an updated
library is
generated for
each segment.
No down time is
simulated
between
segments.h]h/XNumber of
libraries to be
applied in this
cycle.
Optional.
If multiple
libraries are
requested for
this cycle, the
cycle is
subdivided into
equal time
segments, and
an updated
library is
generated for
each segment.
No down time is
simulated
between
segments.}(hj{h j{ubah}(h]h]h]h]h]uhh:h!jIhMh j{ubah}(h]h]h]h]h]uhj9h jC{ubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(hENDh]h/END}(hj{h j{ubah}(h]h]h]h]h]uhh:h!jIhMh j{ubah}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h;)}(hRequired.
Defines the end
of the data for
the current
cycle. Repeat
the above
entries for
each cycle in
the irradiation
history. An
END, not to
begin in
column 1, must
terminate each
cycle
definition.h]h/Required.
Defines the end
of the data for
the current
cycle. Repeat
the above
entries for
each cycle in
the irradiation
history. An
END, not to
begin in
column 1, must
terminate each
cycle
definition.}(hj{h j{ubah}(h]h]h]h]h]uhh:h!jIhMh j{ubah}(h]h]h]h]h]uhj9h j{ubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(hEND HISTORY (or
BURNDATA)\ *a*h](h/END HISTORY (or
BURNDATA) }(hEND HISTORY (or
BURNDATA)\ h j{ubh)}(h*a*h]h/a}(hhh j{ubah}(h]h]h]h]h]uhhh j{ubeh}(h]h]h]h]h]uhh:h!jIhMh j{ubah}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h;)}(h End blockh]h/ End block}(hj0|h j.|ubah}(h]h]h]h]h]uhh:h!jIhMh j+|ubah}(h]h]h]h]h]uhj9h j{ubeh}(h]h]h]h]h]uhj4h jxubj5)}(hhh](j:)}(hhh]h;)}(hK:sup:`a` Only
the first four
characters are
required, i.e.,
HIST (or BURN).h](j)}(h:sup:`a`h]h/a}(hhh jR|ubah}(h]h]h]h]h]uhjh jN|ubh/C Only
the first four
characters are
required, i.e.,
HIST (or BURN).}(hC Only
the first four
characters are
required, i.e.,
HIST (or BURN).h jN|ubeh}(h]h]h]h]h]uhh:h!jIhMh jK|ubah}(h]h]h]h]h]uhj9h jH|ubj:)}(hhh]h}(h]h]h]h]h]uhj9h jH|ubj:)}(hhh]h}(h]h]h]h]h]uhj9h jH|ubj:)}(hhh]h}(h]h]h]h]h]uhj9h jH|ubeh}(h]h]h]h]h]uhj4h jxubeh}(h]h]h]h]h]uhj/h jxubeh}(h]h]h]h]h]colsKuhjh jxubeh}(h](id93jxeh]h]tab2-3-6ah]h]jcenteruhjh jwhhh!jIhNj}j|jxsj}jxjxsubeh}(h](jwid40eh]h](burnup history databurnup-history-dataeh]h]uhh#h jYhhh!jIhMj}j|jwsj}jwjwsubh$)}(hhh](h))}(hSearch parameter datah]h/Search parameter data}(hj|h j|hhh!NhNubah}(h]h]h]h]h]uhh(h j|hhh!jIhMubh;)}(hXThe search parameter data block defines input data for burnup loading
curve analyses for commercial UO\ :sub:`2` spent fuels. Burnup history
input data are not allowed in an input file that supplies search
parameters. A burnup history data block is generated in STARBUCS for
subsequent iterative calculations using the initial user-supplied search
parameter data. STARBUCS sample problem *starbucs1.input* contains a
search data block to request burnup loading curve analyses for spent
fuel at various burnups. The search data block reading is initiated with
the keywords READ SEARCH and terminated by END SEARCH. The keywords are
summarized in :numref:`tab2-3-7`. These keywords may be in any order.h](h/hThe search parameter data block defines input data for burnup loading
curve analyses for commercial UO }(hhThe search parameter data block defines input data for burnup loading
curve analyses for commercial UO\ h j|hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j|ubah}(h]h]h]h]h]uhjh j|ubh/X spent fuels. Burnup history
input data are not allowed in an input file that supplies search
parameters. A burnup history data block is generated in STARBUCS for
subsequent iterative calculations using the initial user-supplied search
parameter data. STARBUCS sample problem }(hX spent fuels. Burnup history
input data are not allowed in an input file that supplies search
parameters. A burnup history data block is generated in STARBUCS for
subsequent iterative calculations using the initial user-supplied search
parameter data. STARBUCS sample problem h j|hhh!NhNubh)}(h*starbucs1.input*h]h/starbucs1.input}(hhh j|ubah}(h]h]h]h]h]uhhh j|ubh/ contains a
search data block to request burnup loading curve analyses for spent
fuel at various burnups. The search data block reading is initiated with
the keywords READ SEARCH and terminated by END SEARCH. The keywords are
summarized in }(h contains a
search data block to request burnup loading curve analyses for spent
fuel at various burnups. The search data block reading is initiated with
the keywords READ SEARCH and terminated by END SEARCH. The keywords are
summarized in h j|hhh!NhNubh_)}(h:numref:`tab2-3-7`h]j)}(hj|h]h/tab2-3-7}(hhh j|ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j|ubah}(h]h]h]h]h]refdocj refdomainj}reftypenumrefrefexplicitrefwarnjtab2-3-7uhh^h!jIhMh j|ubh/&. These keywords may be in any order.}(h&. These keywords may be in any order.h j|hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh j|hhubh;)}(h4USL= THE UPPER SUBCRITICAL LIMIT FOR BURNUP LOADING.h]h/4USL= THE UPPER SUBCRITICAL LIMIT FOR BURNUP LOADING.}(hj"}h j }hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh j|hhubh;)}(hX(EPS= TOLERANCE ON CONVERGENCE. The convergence criterion used in the
search for initial fuel enrichment so that user-specified *k*\ :sub:`eff` value
is within USL ± EPS. The tolerance value must be greater that the
standard deviation of the calculated k\ :sub:`eff` for the solution to
converge.h](h/EPS= TOLERANCE ON CONVERGENCE. The convergence criterion used in the
search for initial fuel enrichment so that user-specified }(hEPS= TOLERANCE ON CONVERGENCE. The convergence criterion used in the
search for initial fuel enrichment so that user-specified h j.}hhh!NhNubh)}(h*k*h]h/k}(hhh j7}ubah}(h]h]h]h]h]uhhh j.}ubh/ }(h\ h j.}hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jJ}ubah}(h]h]h]h]h]uhjh j.}ubh/r value
is within USL ± EPS. The tolerance value must be greater that the
standard deviation of the calculated k }(hr value
is within USL ± EPS. The tolerance value must be greater that the
standard deviation of the calculated k\ h j.}hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j]}ubah}(h]h]h]h]h]uhjh j.}ubh/ for the solution to
converge.}(h for the solution to
converge.h j.}hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh j|hhubh;)}(hITMAX= MAXIMUM ITERATIONS ALLOWED FOR EACH ENRICHMENT SEARCH. The search
for initial fuel enrichment stops when the number of iterations exceeds
this parameter and a warning message is provided to the user.h]h/ITMAX= MAXIMUM ITERATIONS ALLOWED FOR EACH ENRICHMENT SEARCH. The search
for initial fuel enrichment stops when the number of iterations exceeds
this parameter and a warning message is provided to the user.}(hjx}h jv}hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhM!h j|hhubh;)}(hECL= LOWER ENRICHMENT CONSTRAINT. The unit for this parameter is wt%
:sup:`235`\ U. The lower enrichment constraint must be within the
enrichment interval used in the ORIGEN library specified in READ CONTROL
data block.h](h/EECL= LOWER ENRICHMENT CONSTRAINT. The unit for this parameter is wt%
}(hEECL= LOWER ENRICHMENT CONSTRAINT. The unit for this parameter is wt%
h j}hhh!NhNubj)}(h
:sup:`235`h]h/235}(hhh j}ubah}(h]h]h]h]h]uhjh j}ubh/ U. The lower enrichment constraint must be within the
enrichment interval used in the ORIGEN library specified in READ CONTROL
data block.}(h\ U. The lower enrichment constraint must be within the
enrichment interval used in the ORIGEN library specified in READ CONTROL
data block.h j}hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhM%h j|hhubh;)}(hECH= UPPER ENRICHMENT CONSTRAINT. The unit for this parameter is wt%
:sup:`235`\ U. The upper enrichment constraint must be within the
enrichment interval used in the ORIGEN library specified in READ CONTROL
data block.h](h/EECH= UPPER ENRICHMENT CONSTRAINT. The unit for this parameter is wt%
}(hEECH= UPPER ENRICHMENT CONSTRAINT. The unit for this parameter is wt%
h j}hhh!NhNubj)}(h
:sup:`235`h]h/235}(hhh j}ubah}(h]h]h]h]h]uhjh j}ubh/ U. The upper enrichment constraint must be within the
enrichment interval used in the ORIGEN library specified in READ CONTROL
data block.}(h\ U. The upper enrichment constraint must be within the
enrichment interval used in the ORIGEN library specified in READ CONTROL
data block.h j}hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhM*h j|hhubh;)}(hXBU= ARRAY OF REQUESTED BURNUP VALUES (GWd/MTU). The word END is required
to terminate this array. The user inputs a series of discharge burnup
values for which the initial fuel enrichments that result in a desired
*k*\ :sub:`eff` value (USL ± EPS) are to be determined.h](h/BU= ARRAY OF REQUESTED BURNUP VALUES (GWd/MTU). The word END is required
to terminate this array. The user inputs a series of discharge burnup
values for which the initial fuel enrichments that result in a desired
}(hBU= ARRAY OF REQUESTED BURNUP VALUES (GWd/MTU). The word END is required
to terminate this array. The user inputs a series of discharge burnup
values for which the initial fuel enrichments that result in a desired
h j}hhh!NhNubh)}(h*k*h]h/k}(hhh j}ubah}(h]h]h]h]h]uhhh j}ubh/ }(h\ h j}hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j}ubah}(h]h]h]h]h]uhjh j}ubh/) value (USL ± EPS) are to be determined.}(h) value (USL ± EPS) are to be determined.h j}hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhM/h j|hhubh;)}(hAVGBU= AVERAGE BURNUP PER CYCLE (GWd/MTU). An optional entry used to
determine the number of irradiation cycles as the ratio of a burnup
value in the BU array to AVGBU.h]h/AVGBU= AVERAGE BURNUP PER CYCLE (GWd/MTU). An optional entry used to
determine the number of irradiation cycles as the ratio of a burnup
value in the BU array to AVGBU.}(hj}h j}hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhM4h j|hhubh;)}(hXvPOWER= The average specific power of the assembly. The units of the
specific power are in MW/MTU (W/g) of initial uranium. This entry has
the same function as the entry for POWER= keyword in the HISTORY data
block (see :ref:`burnup-history-data`). It is also used to determine cycle
irradiation time as the ratio of a burnup value in the BU array to
average assembly power.h](h/POWER= The average specific power of the assembly. The units of the
specific power are in MW/MTU (W/g) of initial uranium. This entry has
the same function as the entry for POWER= keyword in the HISTORY data
block (see }(hPOWER= The average specific power of the assembly. The units of the
specific power are in MW/MTU (W/g) of initial uranium. This entry has
the same function as the entry for POWER= keyword in the HISTORY data
block (see h j~hhh!NhNubh_)}(h:ref:`burnup-history-data`h]he)}(hj~h]h/burnup-history-data}(hhh j~ubah}(h]h](jstdstd-refeh]h]h]uhhdh j~ubah}(h]h]h]h]h]refdocj refdomainj"~reftyperefrefexplicitrefwarnjburnup-history-datauhh^h!jIhM8h j~ubh/). It is also used to determine cycle
irradiation time as the ratio of a burnup value in the BU array to
average assembly power.}(h). It is also used to determine cycle
irradiation time as the ratio of a burnup value in the BU array to
average assembly power.h j~hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhM8h j|hhubh;)}(hXFDT= FRACTIONAL DOWNTIME. An optional entry used to determine down time
between irradiation cycles (the entry for DOWN= keyword in the HISTORY
data block) if fuel irradiation requires two or more cycles. For
example, for a cycle with 365 days of irradiation followed by a 30-day
downtime, FDT = 30 / 395 = 0.07595. STARBUCS uses the user-provided FDT
to compute cycle downtime as the irradiation time per cycle multiplied
by FDT and divided by (1-FDT).h]h/XFDT= FRACTIONAL DOWNTIME. An optional entry used to determine down time
between irradiation cycles (the entry for DOWN= keyword in the HISTORY
data block) if fuel irradiation requires two or more cycles. For
example, for a cycle with 365 days of irradiation followed by a 30-day
downtime, FDT = 30 / 395 = 0.07595. STARBUCS uses the user-provided FDT
to compute cycle downtime as the irradiation time per cycle multiplied
by FDT and divided by (1-FDT).}(hjA~h j?~hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhM?h j|hhubh;)}(hDEC= DECAY TIME AFTER IRRADIATION. An optional entry to specify the
decay time, in days, after fuel discharge. A negative value may be used
to select logarithmic decay time intervals.h]h/DEC= DECAY TIME AFTER IRRADIATION. An optional entry to specify the
decay time, in days, after fuel discharge. A negative value may be used
to select logarithmic decay time intervals.}(hjO~h jM~hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMGh j|hhubh;)}(hXRNLIB= NUMBER OF LIBRARIES PER CYCLE. An optional entry to request
multiple cross section libraries during a depletion cycle. Generating
multiple libraries provides a more accurate representation of the
time-dependent cross section variation during the burnup analysis. Each
segment of the cycle is assumed to have the same specific power.h]h/XRNLIB= NUMBER OF LIBRARIES PER CYCLE. An optional entry to request
multiple cross section libraries during a depletion cycle. Generating
multiple libraries provides a more accurate representation of the
time-dependent cross section variation during the burnup analysis. Each
segment of the cycle is assumed to have the same specific power.}(hj]~h j[~hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMKh j|hhubh;)}(hXFFE= FRESH FUEL ENRICHMENT. The purpose of this option is to help in
reducing the total number of iterations needed to achieve convergence.
There are two options implemented in STARBUCS for the fresh fuel
enrichment value to be used in the first inner iterations over fuel
enrichment, FFE=SEARCH (default) and FFE=INPUT. With the default option
(FFE=SEARCH), the lower enrichment bound and the starting fresh fuel
enrichment at the beginning of a search are adjusted based on the
results of the previous outer iteration over burnup. The procedure
includes the following steps. First, the user requested burnup values
are sorted in ascending order so that STARBUCS outer iterations over
burnup proceed from the lowest to the highest burnup value. Then, the
initial fresh fuel for the lowest burnup is changed to the mid-value of
the enrichment interval, (ECL+ECU)/2, and the search for the fresh fuel
enrichment corresponding to the lowest burnup is initiated and
completed. Suppose that a solution for this burnup step exists. This
solution becomes the lower enrichment constraint (ECL) in the search
passes for the next burnup value and the initial fresh fuel enrichment
is chosen as the middle point of the enrichment interval. The procedure
is applied for the entire set of the requested burnups. The average
number of iterations for each burnup step with this option is
approximately 4. The alternate option (FFE=INPUT) starts a search for
fuel enrichment with the user supplied fresh fuel enrichment.h]h/XFFE= FRESH FUEL ENRICHMENT. The purpose of this option is to help in
reducing the total number of iterations needed to achieve convergence.
There are two options implemented in STARBUCS for the fresh fuel
enrichment value to be used in the first inner iterations over fuel
enrichment, FFE=SEARCH (default) and FFE=INPUT. With the default option
(FFE=SEARCH), the lower enrichment bound and the starting fresh fuel
enrichment at the beginning of a search are adjusted based on the
results of the previous outer iteration over burnup. The procedure
includes the following steps. First, the user requested burnup values
are sorted in ascending order so that STARBUCS outer iterations over
burnup proceed from the lowest to the highest burnup value. Then, the
initial fresh fuel for the lowest burnup is changed to the mid-value of
the enrichment interval, (ECL+ECU)/2, and the search for the fresh fuel
enrichment corresponding to the lowest burnup is initiated and
completed. Suppose that a solution for this burnup step exists. This
solution becomes the lower enrichment constraint (ECL) in the search
passes for the next burnup value and the initial fresh fuel enrichment
is chosen as the middle point of the enrichment interval. The procedure
is applied for the entire set of the requested burnups. The average
number of iterations for each burnup step with this option is
approximately 4. The alternate option (FFE=INPUT) starts a search for
fuel enrichment with the user supplied fresh fuel enrichment.}(hjk~h ji~hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMQh j|hhubh)}(h
.. _tab2-3-7:h]h}(h]h]h]h]h]htab2-3-7uhh
hM"h j|hhh!jIubj)}(hhh](h))}(hTable of search data.h]h/Table of search data.}(hj~h j~ubah}(h]h]h]h]h]uhh(h!jIhMih j~ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j~ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j~ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j~ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j~ubj0)}(hhh](j5)}(hhh](j:)}(hhh](h;)}(h**Keyword**h]hA)}(hj~h]h/Keyword}(hhh j~ubah}(h]h]h]h]h]uhh@h j~ubah}(h]h]h]h]h]uhh:h!jIhMmh j~ubh;)}(h**Name**h]hA)}(hj~h]h/Name}(hhh j~ubah}(h]h]h]h]h]uhh@h j~ubah}(h]h]h]h]h]uhh:h!jIhMoh j~ubeh}(h]h]h]h]h]uhj9h j~ubj:)}(hhh](h;)}(h**Data**h]hA)}(hjh]h/Data}(hhh jubah}(h]h]h]h]h]uhh@h j~ubah}(h]h]h]h]h]uhh:h!jIhMmh j~ubh;)}(h**type**h]hA)}(hjh]h/type}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!jIhMoh j~ubeh}(h]h]h]h]h]uhj9h j~ubj:)}(hhh](h;)}(h**Default**h]hA)}(hj7h]h/Default}(hhh j9ubah}(h]h]h]h]h]uhh@h j5ubah}(h]h]h]h]h]uhh:h!jIhMmh j2ubh;)}(h **value**h]hA)}(hjNh]h/value}(hhh jPubah}(h]h]h]h]h]uhh@h jLubah}(h]h]h]h]h]uhh:h!jIhMoh j2ubeh}(h]h]h]h]h]uhj9h j~ubj:)}(hhh]h;)}(h**Comments**h]hA)}(hjnh]h/Comments}(hhh jpubah}(h]h]h]h]h]uhh@h jlubah}(h]h]h]h]h]uhh:h!jIhMmh jiubah}(h]h]h]h]h]uhj9h j~ubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hREAD SEARCH\
:sup:`a`h](h/
READ SEARCH
}(h
READ SEARCH\
h jubj)}(h:sup:`a`h]h/a}(hhh jubah}(h]h]h]h]h]uhjh jubeh}(h]h]h]h]h]uhh:h!jIhMqh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h*Initiate
reading the
search block of
data.h]h/*Initiate
reading the
search block of
data.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMqh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hUSL=h]h/USL=}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMyh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hRealh]h/Real}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMyh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h1.0h]h/1.0}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMyh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hUpper
subcritical
limit.h]h/Upper
subcritical
limit.}(hj4h j2ubah}(h]h]h]h]h]uhh:h!jIhMyh j/ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hEPS=h]h/EPS=}(hjTh jRubah}(h]h]h]h]h]uhh:h!jIhM}h jOubah}(h]h]h]h]h]uhj9h jLubj:)}(hhh]h;)}(hRealh]h/Real}(hjkh jiubah}(h]h]h]h]h]uhh:h!jIhM}h jfubah}(h]h]h]h]h]uhj9h jLubj:)}(hhh]h;)}(h0.005h]h/0.005}(hjh jubah}(h]h]h]h]h]uhh:h!jIhM}h j}ubah}(h]h]h]h]h]uhj9h jLubj:)}(hhh]h;)}(hTolerance on
convergence.h]h/Tolerance on
convergence.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhM}h jubah}(h]h]h]h]h]uhj9h jLubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hITMAX=h]h/ITMAX=}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hIntegerh]h/Integer}(hjЀh jubah}(h]h]h]h]h]uhh:h!jIhMh jˀubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h10h]h/10}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hIteration
limit.h]h/Iteration
limit.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hECL=h]h/ECL=}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hRealh]h/Real}(hj5h j3ubah}(h]h]h]h]h]uhh:h!jIhMh j0ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h1.5h]h/1.5}(hjLh jJubah}(h]h]h]h]h]uhh:h!jIhMh jGubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h5Lower initial
fuel enrichment
constraint
(U-235 wt%).h]h/5Lower initial
fuel enrichment
constraint
(U-235 wt%).}(hjch jaubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hECH=h]h/ECH=}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh j~ubah}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h;)}(hRealh]h/Real}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h;)}(h5.0h]h/5.0}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h j{ubj:)}(hhh]h;)}(h5Upper initial
fuel enrichment
constraint
(U-235 wt%).h]h/5Upper initial
fuel enrichment
constraint
(U-235 wt%).}(hjȁh jƁubah}(h]h]h]h]h]uhh:h!jIhMh jÁubah}(h]h]h]h]h]uhj9h j{ubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hBUh]h/BU}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hReal\ :sup:`b`h](h/Real }(hReal\ h jubj)}(h:sup:`b`h]h/b}(hhh jubah}(h]h]h]h]h]uhjh jubeh}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hNoneh]h/None}(hj%h j#ubah}(h]h]h]h]h]uhh:h!jIhMh j ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h;Array entry of
requested
burnup values
(GWd/MTU).\
:sup:`c`h](h/3Array entry of
requested
burnup values
(GWd/MTU).
}(h3Array entry of
requested
burnup values
(GWd/MTU).\
h j:ubj)}(h:sup:`c`h]h/c}(hhh jCubah}(h]h]h]h]h]uhjh j:ubeh}(h]h]h]h]h]uhh:h!jIhMh j7ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hAVGBU=h]h/AVGBU=}(hjkh jiubah}(h]h]h]h]h]uhh:h!jIhMh jfubah}(h]h]h]h]h]uhj9h jcubj:)}(hhh]h;)}(hRealh]h/Real}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh j}ubah}(h]h]h]h]h]uhj9h jcubj:)}(hhh]h;)}(h20.0h]h/20.0}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jcubj:)}(hhh]h;)}(hAverage burnup
per cycle.h]h/Average burnup
per cycle.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jcubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hPOWER=h]h/POWER=}(hjЂh jubah}(h]h]h]h]h]uhh:h!jIhMh j˂ubah}(h]h]h]h]h]uhj9h jȂubj:)}(hhh]h;)}(hRealh]h/Real}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jȂubj:)}(hhh]h;)}(h25.0h]h/25.0}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jȂubj:)}(hhh]h;)}(hAverage
specific power
(W/g).h]h/Average
specific power
(W/g).}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jȂubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hFDT=h]h/FDT=}(hj5h j3ubah}(h]h]h]h]h]uhh:h!jIhMh j0ubah}(h]h]h]h]h]uhj9h j-ubj:)}(hhh]h;)}(hRealh]h/Real}(hjLh jJubah}(h]h]h]h]h]uhh:h!jIhMh jGubah}(h]h]h]h]h]uhj9h j-ubj:)}(hhh]h;)}(h0.2h]h/0.2}(hjch jaubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j-ubj:)}(hhh]h;)}(hFractional
downtime.h]h/Fractional
downtime.}(hjzh jxubah}(h]h]h]h]h]uhh:h!jIhMh juubah}(h]h]h]h]h]uhj9h j-ubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hDEC=h]h/DEC=}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hRealh]h/Real}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h1825.0h]h/1825.0}(hjȃh jƃubah}(h]h]h]h]h]uhh:h!jIhMh jÃubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hDecay time
(days).h]h/Decay time
(days).}(hj߃h j݃ubah}(h]h]h]h]h]uhh:h!jIhMh jڃubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hNLIB=h]h/NLIB=}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hIntegerh]h/Integer}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hj+h]h/2}(hj+h j+ubah}(h]h]h]h]h]uhh:h!jIhMh j(ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hLibraries per
cycle.h]h/Libraries per
cycle.}(hjCh jAubah}(h]h]h]h]h]uhh:h!jIhMh j>ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(hFFE=h]h/FFE=}(hjch jaubah}(h]h]h]h]h]uhh:h!jIhMh j^ubah}(h]h]h]h]h]uhj9h j[ubj:)}(hhh]h;)}(h Characterh]h/ Character}(hjzh jxubah}(h]h]h]h]h]uhh:h!jIhMh juubah}(h]h]h]h]h]uhj9h j[ubj:)}(hhh]h;)}(hSEARCHh]h/SEARCH}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h j[ubj:)}(hhh]h;)}(hFresh fuel
option.
FFE=INPUT
starts the
outer
iterations over
the burnup
values with
user supplied
fresh fuel
composition.
FFE=SEARCH
helps in
reducing the
number of
search passes
(approximately
4 in average).h]h/Fresh fuel
option.
FFE=INPUT
starts the
outer
iterations over
the burnup
values with
user supplied
fresh fuel
composition.
FFE=SEARCH
helps in
reducing the
number of
search passes
(approximately
4 in average).}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h j[ubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh]h;)}(h
END SEARCHh]h/
END SEARCH}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnd of the
search datah]h/End of the
search data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h j~ubj5)}(hhh](j:)}(hhh](h;)}(h6:sup:`a` \Only
the first four
characters are
required.h](j)}(h:sup:`a`h]h/a}(hhh j@ubah}(h]h]h]h]h]uhjh j<ubh/. Only
the first four
characters are
required.}(h. \Only
the first four
characters are
required.h j<ubeh}(h]h]h]h]h]uhh:h!jIhMh j9ubh;)}(hT:sup:`b` Termin\
ate array data
entries with
end. Do not
place this end
in column 1.h](j)}(h:sup:`b`h]h/b}(hhh j]ubah}(h]h]h]h]h]uhjh jYubh/L Termin
ate array data
entries with
end. Do not
place this end
in column 1.}(hL Termin\
ate array data
entries with
end. Do not
place this end
in column 1.h jYubeh}(h]h]h]h]h]uhh:h!jIhMh j9ubh;)}(h:sup:`c` There
are no restrain\
ts on the maxim\
um number of the
burnup values
requested in
burnup loading
curve
calculations. A
user may
consider
computer time
and resources
in assessing
the maximum
number of
burnup values
in this array.h](j)}(h:sup:`c`h]h/c}(hhh jzubah}(h]h]h]h]h]uhjh jvubh/ There
are no restrain
ts on the maxim
um number of the
burnup values
requested in
burnup loading
curve
calculations. A
user may
consider
computer time
and resources
in assessing
the maximum
number of
burnup values
in this array.}(h There
are no restrain\
ts on the maxim\
um number of the
burnup values
requested in
burnup loading
curve
calculations. A
user may
consider
computer time
and resources
in assessing
the maximum
number of
burnup values
in this array.h jvubeh}(h]h]h]h]h]uhh:h!jIhMh j9ubeh}(h]h]h]h]h]uhj9h j6ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j6ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j6ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j6ubeh}(h]h]h]h]h]uhj4h j~ubeh}(h]h]h]h]h]uhj/h j~ubeh}(h]h]h]h]h]colsKuhjh j~ubeh}(h](id94j~eh]h]tab2-3-7ah]h]jcenteruhjh j|hhh!jIhNj}j̅jw~sj}j~jw~subeh}(h]search-parameter-dataah]h]search parameter dataah]h]uhh#h jYhhh!jIhMubh$)}(hhh](h))}(hKENO input datah]h/KENO input data}(hj߅h j݅hhh!NhNubah}(h]h]h]h]h]uhh(h jڅhhh!jIhMubh;)}(hX=The KENO input for the problem is specified in the KENO data block.
Input to the data block is initiated with the data block keywords **READ
KENO or READ KENOVA** and is terminated by the keywords **END** **KENO**
or **END** **KENOVA** for criticality calculations using **KENO V.a**.
Input to the data block is initiated with the data block keywords **READ
KENOVI or READ KENO6** and is terminated by the keywords **END**
**KENOVI** or **END** **KENO6** for criticality calculations using
**KENO VI**. STARBUCS performs no error checking of the KENO input. The
data within the data block delimiters is copied, without change, to the
CSAS input file and executed. The user is therefore advised to ensure
that the KENO input is free of errors by first running the case within
CSAS5 or CSAS6 before applying the input in STARBUCS.h](h/The KENO input for the problem is specified in the KENO data block.
Input to the data block is initiated with the data block keywords }(hThe KENO input for the problem is specified in the KENO data block.
Input to the data block is initiated with the data block keywords h jhhh!NhNubhA)}(h**READ
KENO or READ KENOVA**h]h/READ
KENO or READ KENOVA}(hhh jubah}(h]h]h]h]h]uhh@h jubh/# and is terminated by the keywords }(h# and is terminated by the keywords h jhhh!NhNubhA)}(h**END**h]h/END}(hhh jubah}(h]h]h]h]h]uhh@h jubh/ }(hjTh jhhh!NhNubhA)}(h**KENO**h]h/KENO}(hhh jubah}(h]h]h]h]h]uhh@h jubh/
or }(h
or h jhhh!NhNubhA)}(h**END**h]h/END}(hhh j,ubah}(h]h]h]h]h]uhh@h jubh/ }(hjTh jubhA)}(h
**KENOVA**h]h/KENOVA}(hhh j>ubah}(h]h]h]h]h]uhh@h jubh/$ for criticality calculations using }(h$ for criticality calculations using h jhhh!NhNubhA)}(h**KENO V.a**h]h/KENO V.a}(hhh jQubah}(h]h]h]h]h]uhh@h jubh/D.
Input to the data block is initiated with the data block keywords }(hD.
Input to the data block is initiated with the data block keywords h jhhh!NhNubhA)}(h**READ
KENOVI or READ KENO6**h]h/READ
KENOVI or READ KENO6}(hhh jdubah}(h]h]h]h]h]uhh@h jubh/# and is terminated by the keywords }(hjh jubhA)}(h**END**h]h/END}(hhh jvubah}(h]h]h]h]h]uhh@h jubh/
}(h
h jhhh!NhNubhA)}(h
**KENOVI**h]h/KENOVI}(hhh jubah}(h]h]h]h]h]uhh@h jubh/ or }(h or h jhhh!NhNubhA)}(h**END**h]h/END}(hhh jubah}(h]h]h]h]h]uhh@h jubh/ }(hjTh jubhA)}(h **KENO6**h]h/KENO6}(hhh jubah}(h]h]h]h]h]uhh@h jubh/$ for criticality calculations using
}(h$ for criticality calculations using
h jhhh!NhNubhA)}(h**KENO VI**h]h/KENO VI}(hhh jubah}(h]h]h]h]h]uhh@h jubh/XH. STARBUCS performs no error checking of the KENO input. The
data within the data block delimiters is copied, without change, to the
CSAS input file and executed. The user is therefore advised to ensure
that the KENO input is free of errors by first running the case within
CSAS5 or CSAS6 before applying the input in STARBUCS.}(hXH. STARBUCS performs no error checking of the KENO input. The
data within the data block delimiters is copied, without change, to the
CSAS input file and executed. The user is therefore advised to ensure
that the KENO input is free of errors by first running the case within
CSAS5 or CSAS6 before applying the input in STARBUCS.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jڅhhubh;)}(hX.The input requirements for KENO V.a and KENO-VI are not described in
this section, but are described in detail in the KENO chapter of this
manual. This section describes only the input requirements as related to
the execution of KENO within STARBUCS and the conventions used for
module compatibility.h]h/X.The input requirements for KENO V.a and KENO-VI are not described in
this section, but are described in detail in the KENO chapter of this
manual. This section describes only the input requirements as related to
the execution of KENO within STARBUCS and the conventions used for
module compatibility.}(hj܆h jچhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jڅhhubh;)}(hXAThe mixture numbers for each of the non-fuel materials applied to the
material regions of the KENO model are defined as the mixture numbers
(MX) specified in the standard composition input. STARBUCS automatically
defines the *MIXTURE ID* for each of the fuel regions according to the
axial and/or horizontal zones defined by the NAX and NHZ entries in the
burnup-profile arrays. The first axial-zone mixture is assigned MX=101,
and is incremented by one for each additional axial zone. Therefore, in
a problem that defines 18 axial zones, spent fuel mixtures will be
generated with identifiers that range from 101 to 118. The
correspondence of these mixtures to the assembly locations is determined
by the ordering of the AXP= input array that defines the axial-burnup
profile for the assembly. If the AXP= array orders the burnup profile
from the bottom of the assembly to the top of the assembly, the
resulting MX=101 will correspond to the bottom axial-zone segment, and
MX=118 would correspond to the top axial zone. If multiple horizontal
zones are defined, then the numbering sequence of the second horizontal
zone will start at MX=201 and, in the example given here, would range up
to MX=218. Refer to :ref:`cap-and-lim` for limitations in the mixture-numbering
scheme. The mixture-numbering scheme is illustrated in :numref:`fig2-3-3`.h](h/The mixture numbers for each of the non-fuel materials applied to the
material regions of the KENO model are defined as the mixture numbers
(MX) specified in the standard composition input. STARBUCS automatically
defines the }(hThe mixture numbers for each of the non-fuel materials applied to the
material regions of the KENO model are defined as the mixture numbers
(MX) specified in the standard composition input. STARBUCS automatically
defines the h jhhh!NhNubh)}(h*MIXTURE ID*h]h/
MIXTURE ID}(hhh jubah}(h]h]h]h]h]uhhh jubh/X for each of the fuel regions according to the
axial and/or horizontal zones defined by the NAX and NHZ entries in the
burnup-profile arrays. The first axial-zone mixture is assigned MX=101,
and is incremented by one for each additional axial zone. Therefore, in
a problem that defines 18 axial zones, spent fuel mixtures will be
generated with identifiers that range from 101 to 118. The
correspondence of these mixtures to the assembly locations is determined
by the ordering of the AXP= input array that defines the axial-burnup
profile for the assembly. If the AXP= array orders the burnup profile
from the bottom of the assembly to the top of the assembly, the
resulting MX=101 will correspond to the bottom axial-zone segment, and
MX=118 would correspond to the top axial zone. If multiple horizontal
zones are defined, then the numbering sequence of the second horizontal
zone will start at MX=201 and, in the example given here, would range up
to MX=218. Refer to }(hX for each of the fuel regions according to the
axial and/or horizontal zones defined by the NAX and NHZ entries in the
burnup-profile arrays. The first axial-zone mixture is assigned MX=101,
and is incremented by one for each additional axial zone. Therefore, in
a problem that defines 18 axial zones, spent fuel mixtures will be
generated with identifiers that range from 101 to 118. The
correspondence of these mixtures to the assembly locations is determined
by the ordering of the AXP= input array that defines the axial-burnup
profile for the assembly. If the AXP= array orders the burnup profile
from the bottom of the assembly to the top of the assembly, the
resulting MX=101 will correspond to the bottom axial-zone segment, and
MX=118 would correspond to the top axial zone. If multiple horizontal
zones are defined, then the numbering sequence of the second horizontal
zone will start at MX=201 and, in the example given here, would range up
to MX=218. Refer to h jhhh!NhNubh_)}(h:ref:`cap-and-lim`h]he)}(hjh]h/cap-and-lim}(hhh jubah}(h]h](jstdstd-refeh]h]h]uhhdh jubah}(h]h]h]h]h]refdocj refdomainjreftyperefrefexplicitrefwarnjcap-and-limuhh^h!jIhMh jubh/a for limitations in the mixture-numbering
scheme. The mixture-numbering scheme is illustrated in }(ha for limitations in the mixture-numbering
scheme. The mixture-numbering scheme is illustrated in h jhhh!NhNubh_)}(h:numref:`fig2-3-3`h]j)}(hj+h]h/fig2-3-3}(hhh j-ubah}(h]h](jstd
std-numrefeh]h]h]uhjh j)ubah}(h]h]h]h]h]refdocj refdomainj7reftypenumrefrefexplicitrefwarnjfig2-3-3uhh^h!jIhMh jubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jڅhhubeh}(h]keno-input-dataah]h]keno input dataah]h]uhh#h jYhhh!jIhMubeh}(h]input-descriptionah]h]input descriptionah]h]uhh#h jRhhh!jIhMubjuLeh}(h](]starbucs-a-scale-control-module-for-automated-criticality-safety-analyses-using-burnup-creditstarbucseh]h](^starbucs: a scale control module for automated criticality safety analyses using burnup creditstarbucseh]h]uhh#h h%hhh!jIhKj}jjh)}(h
.. _STARBUCS:h]h}(h]h]h]h]h]hjfuhh
hM.h h$)}(hhh](h))}(h*Run KENO-VI containing multiple unit cellsh]h/*Run KENO-VI containing multiple unit cells}(hj}h j{hhh!NhNubah}(h]h]h]h]h]uhh(h jxhhh!CSAS6App.rsthKubh;)}(hXCSAS6 can create a microscopic working format library and a mixing table
that contains more than one unit cell. Each unit cell is explicitly
defined in the CELLDATA section of the standard composition data.
Materials may appear in only one unit cell. All materials in the
standard composition that are not contained in a unit cell are processed
assuming infinite homogeneous media. CSAS6 passes the created working
library to KENO-VI which calculates *k*\ :sub:`eff` for the problem.h](h/XCSAS6 can create a microscopic working format library and a mixing table
that contains more than one unit cell. Each unit cell is explicitly
defined in the CELLDATA section of the standard composition data.
Materials may appear in only one unit cell. All materials in the
standard composition that are not contained in a unit cell are processed
assuming infinite homogeneous media. CSAS6 passes the created working
library to KENO-VI which calculates }(hXCSAS6 can create a microscopic working format library and a mixing table
that contains more than one unit cell. Each unit cell is explicitly
defined in the CELLDATA section of the standard composition data.
Materials may appear in only one unit cell. All materials in the
standard composition that are not contained in a unit cell are processed
assuming infinite homogeneous media. CSAS6 passes the created working
library to KENO-VI which calculates h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/ for the problem.}(h for the problem.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jxhhubh;)}(h`EXAMPLE 1. CSAS6 – Calculate the *k*\ :sub:`eff` of a system using two unit
cell descriptions.h](h/#EXAMPLE 1. CSAS6 – Calculate the }(h#EXAMPLE 1. CSAS6 – Calculate the h jhhh!NhNubh)}(h*k*h]h/k}(hhh jȇubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jۇubah}(h]h]h]h]h]uhjh jubh/. of a system using two unit
cell descriptions.}(h. of a system using two unit
cell descriptions.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jxhhubh;)}(hXConsider an infinite XY-array composed of two types of fuel assemblies
in a checkerboard pattern moderated by water. Each assembly consists of
a 17 × 17 × 1 array of zirconium-clad, enriched UO\ :sub:`2` fuel pins
in a square pitched array. In one array the uranium is 3.5%-enriched and
in the other array the uranium is 2.9%-enriched. The UO\ :sub:`2` has a
density of 9.21 g/cm\ :sup:`3`. The pin diameter is 0.8 cm and is 366 cm
long. The clad is 0.07 cm thick, and the pitch is 1.3 cm. Each fuel
bundle is contained in a 0.65-cm-thick Boral sheath. The bundles are
separated by an edge-to-edge spacing of 1.0 cm. The water and zirconium
is input in the standard composition data once for every unit cell in
which it appears because a material may appear in only one unit cell.
Determine the *k*\ :sub:`eff` of the infinite array. Note that periodic
boundary conditions are required to obtain an infinite checkerboard
array. Input data for this problem follow.h](h/Consider an infinite XY-array composed of two types of fuel assemblies
in a checkerboard pattern moderated by water. Each assembly consists of
a 17 × 17 × 1 array of zirconium-clad, enriched UO }(hConsider an infinite XY-array composed of two types of fuel assemblies
in a checkerboard pattern moderated by water. Each assembly consists of
a 17 × 17 × 1 array of zirconium-clad, enriched UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ fuel pins
in a square pitched array. In one array the uranium is 3.5%-enriched and
in the other array the uranium is 2.9%-enriched. The UO }(h fuel pins
in a square pitched array. In one array the uranium is 3.5%-enriched and
in the other array the uranium is 2.9%-enriched. The UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ has a
density of 9.21 g/cm }(h has a
density of 9.21 g/cm\ h jhhh!NhNubj)}(h:sup:`3`h]h/3}(hhh j#ubah}(h]h]h]h]h]uhjh jubh/X. The pin diameter is 0.8 cm and is 366 cm
long. The clad is 0.07 cm thick, and the pitch is 1.3 cm. Each fuel
bundle is contained in a 0.65-cm-thick Boral sheath. The bundles are
separated by an edge-to-edge spacing of 1.0 cm. The water and zirconium
is input in the standard composition data once for every unit cell in
which it appears because a material may appear in only one unit cell.
Determine the }(hX. The pin diameter is 0.8 cm and is 366 cm
long. The clad is 0.07 cm thick, and the pitch is 1.3 cm. Each fuel
bundle is contained in a 0.65-cm-thick Boral sheath. The bundles are
separated by an edge-to-edge spacing of 1.0 cm. The water and zirconium
is input in the standard composition data once for every unit cell in
which it appears because a material may appear in only one unit cell.
Determine the h jhhh!NhNubh)}(h*k*h]h/k}(hhh j6ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jIubah}(h]h]h]h]h]uhjh jubh/ of the infinite array. Note that periodic
boundary conditions are required to obtain an infinite checkerboard
array. Input data for this problem follow.}(h of the infinite array. Note that periodic
boundary conditions are required to obtain an infinite checkerboard
array. Input data for this problem follow.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jxhhubj)}(hXn=CSAS6
2 SQUARE FUEL ASSEMBLIES EXAMPLE IN AN INFINITE LATTICE OF ASSEMBLIES
V7-238
READ COMP
UO2 1 DEN=9.21 1.0 293. 92235 3.5 92238 96.5 END
ZR 2 1 END
H2O 3 1 END
UO2 4 DEN=9.21 1.0 293. 92235 2.9 92238 97.1 END
ZR 5 1 END
H2O 6 1 END
B4C 7 0.367 END
AL 7 0.636 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.3 3 FUELD=0.8 1 CLADD=0.94 2 END
LATTICECELL SQUAREPITCH PITCH=1.3 6 FUELD=0.8 4 CLADD=0.94 5 END
END CELLDATA
READ PARAM FAR=YES GEN=253 END PARAM
READ GEOM
UNIT 1
COM='3.5 W% FUEL PIN'
CYLINDER 10 0.4 2P183.0
CYLINDER 20 0.47 2P183.07
CUBOID 30 4P0.65 2P183.07
MEDIA 1 1 10
MEDIA 2 1 20 -10
MEDIA 3 1 30 -20 -10
BOUNDARY 30
UNIT 2
COM='3.5 W% FUEL ASSEMBLY'
CUBOID 10 4P11.05 2P183.07
CUBOID 20 4P11.7 2P183.72
CUBOID 30 4P12.2 2P184.22
ARRAY 1 10 PLACE 9 9 1 3*0.0
MEDIA 7 1 20 -10
MEDIA 3 1 20 -20 -20
BOUNDARY 30
UNIT 3
COM='2.9 W% FUEL PIN'
CYLINDER 10 0.4 2P183.0
CYLINDER 20 0.47 2P183.07
CUBOID 30 4P0.65 2P183.07
MEDIA 4 1 10
MEDIA 5 1 20 -10
MEDIA 6 1 30 -20 -10
BOUNDARY 30
UNIT 4
COM='2.9 W% FUEL ASSEMBLY'
CUBOID 10 4P11.05 2P183.07
CUBOID 20 4P11.7 2P183.72
CUBOID 30 4P12.2 2P184.22
ARRAY 2 10 PLACE 9 9 1 3*0.0
MEDIA 7 1 20 -10
MEDIA 6 1 20 -20 -20
BOUNDARY 30
GLOBAL UNIT 5
COM='FUEL CASK CONTAINING 4X4 ARRAY OF ASSEMBLIES'
CUBOID 10 4P24.4 2P184.22
ARRAY 3 10 PLACE 1 1 1 -12.2 -12.2 0.0
BOUNDARY 10
END GEOM
READ ARRAY
ARA=1 NUX=17 NUY=17 NUZ=1 FILL F1 END FILL
ARA=2 NUX=17 NUY=17 NUZ=1 FILL F3 END FILL
GBL=3 ARA=3 NUX=2 NUY=2 NUZ=1 FILL 2 4 4 2 END FILL
END ARRAY
READ BOUNDS XYF=PERIODIC END BOUNDS
END DATA
ENDh]h/Xn=CSAS6
2 SQUARE FUEL ASSEMBLIES EXAMPLE IN AN INFINITE LATTICE OF ASSEMBLIES
V7-238
READ COMP
UO2 1 DEN=9.21 1.0 293. 92235 3.5 92238 96.5 END
ZR 2 1 END
H2O 3 1 END
UO2 4 DEN=9.21 1.0 293. 92235 2.9 92238 97.1 END
ZR 5 1 END
H2O 6 1 END
B4C 7 0.367 END
AL 7 0.636 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.3 3 FUELD=0.8 1 CLADD=0.94 2 END
LATTICECELL SQUAREPITCH PITCH=1.3 6 FUELD=0.8 4 CLADD=0.94 5 END
END CELLDATA
READ PARAM FAR=YES GEN=253 END PARAM
READ GEOM
UNIT 1
COM='3.5 W% FUEL PIN'
CYLINDER 10 0.4 2P183.0
CYLINDER 20 0.47 2P183.07
CUBOID 30 4P0.65 2P183.07
MEDIA 1 1 10
MEDIA 2 1 20 -10
MEDIA 3 1 30 -20 -10
BOUNDARY 30
UNIT 2
COM='3.5 W% FUEL ASSEMBLY'
CUBOID 10 4P11.05 2P183.07
CUBOID 20 4P11.7 2P183.72
CUBOID 30 4P12.2 2P184.22
ARRAY 1 10 PLACE 9 9 1 3*0.0
MEDIA 7 1 20 -10
MEDIA 3 1 20 -20 -20
BOUNDARY 30
UNIT 3
COM='2.9 W% FUEL PIN'
CYLINDER 10 0.4 2P183.0
CYLINDER 20 0.47 2P183.07
CUBOID 30 4P0.65 2P183.07
MEDIA 4 1 10
MEDIA 5 1 20 -10
MEDIA 6 1 30 -20 -10
BOUNDARY 30
UNIT 4
COM='2.9 W% FUEL ASSEMBLY'
CUBOID 10 4P11.05 2P183.07
CUBOID 20 4P11.7 2P183.72
CUBOID 30 4P12.2 2P184.22
ARRAY 2 10 PLACE 9 9 1 3*0.0
MEDIA 7 1 20 -10
MEDIA 6 1 20 -20 -20
BOUNDARY 30
GLOBAL UNIT 5
COM='FUEL CASK CONTAINING 4X4 ARRAY OF ASSEMBLIES'
CUBOID 10 4P24.4 2P184.22
ARRAY 3 10 PLACE 1 1 1 -12.2 -12.2 0.0
BOUNDARY 10
END GEOM
READ ARRAY
ARA=1 NUX=17 NUY=17 NUZ=1 FILL F1 END FILL
ARA=2 NUX=17 NUY=17 NUZ=1 FILL F3 END FILL
GBL=3 ARA=3 NUX=2 NUY=2 NUZ=1 FILL 2 4 4 2 END FILL
END ARRAY
READ BOUNDS XYF=PERIODIC END BOUNDS
END DATA
END}(hhh jbubah}(h]h]h]h]h]jjuhjh!jhKh jxhhubh;)}(h{EXAMPLE 2. CSAS6 – Calculate the *k*\ :sub:`eff` of a system using two unit
cell descriptions and cell-weighted mixtures.h](h/#EXAMPLE 2. CSAS6 – Calculate the }(h#EXAMPLE 2. CSAS6 – Calculate the h jphhh!NhNubh)}(h*k*h]h/k}(hhh jyubah}(h]h]h]h]h]uhhh jpubh/ }(h\ h jphhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jpubh/I of a system using two unit
cell descriptions and cell-weighted mixtures.}(hI of a system using two unit
cell descriptions and cell-weighted mixtures.h jphhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMCh jxhhubh;)}(hXConsider a problem in which a stainless steel cylinder with an inner
diameter of 56 cm and an inside height of 91 cm is filled with pellets
of UO\ :sub:`2` in borated water. The steel is 0.125 cm thick. The
spherical 2.57%-enriched UO\ :sub:`2` pellets have a diameter of 1.07 cm
and are arranged in a triangular pitch array with a pitch of 1.13 cm.
The spherical 2.96%-enriched UO\ :sub:`2` pellets have a diameter of
1.07 cm and are arranged in a triangular pitch array with a pitch of
1.12 cm. The cylindrical tank is filled half full of the 2.96% pellets
in borated water, and the remainder is filled with the 2.57%-enriched
pellets in borated water.h](h/Consider a problem in which a stainless steel cylinder with an inner
diameter of 56 cm and an inside height of 91 cm is filled with pellets
of UO }(hConsider a problem in which a stainless steel cylinder with an inner
diameter of 56 cm and an inside height of 91 cm is filled with pellets
of UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/R in borated water. The steel is 0.125 cm thick. The
spherical 2.57%-enriched UO }(hR in borated water. The steel is 0.125 cm thick. The
spherical 2.57%-enriched UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ pellets have a diameter of 1.07 cm
and are arranged in a triangular pitch array with a pitch of 1.13 cm.
The spherical 2.96%-enriched UO }(h pellets have a diameter of 1.07 cm
and are arranged in a triangular pitch array with a pitch of 1.13 cm.
The spherical 2.96%-enriched UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jԈubah}(h]h]h]h]h]uhjh jubh/X pellets have a diameter of
1.07 cm and are arranged in a triangular pitch array with a pitch of
1.12 cm. The cylindrical tank is filled half full of the 2.96% pellets
in borated water, and the remainder is filled with the 2.57%-enriched
pellets in borated water.}(hX pellets have a diameter of
1.07 cm and are arranged in a triangular pitch array with a pitch of
1.12 cm. The cylindrical tank is filled half full of the 2.96% pellets
in borated water, and the remainder is filled with the 2.57%-enriched
pellets in borated water.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMFh jxhhubh;)}(hXMixture 100 is the cell-weighted mixture containing the 2.57%-enriched
uranium pellets and mixture 200 is the cell-weighted mixture containing
the 2.96%-enriched uranium pellets. Determine the *k*\ :sub:`eff` of this
system. Input data for this problem follow.h](h/Mixture 100 is the cell-weighted mixture containing the 2.57%-enriched
uranium pellets and mixture 200 is the cell-weighted mixture containing
the 2.96%-enriched uranium pellets. Determine the }(hMixture 100 is the cell-weighted mixture containing the 2.57%-enriched
uranium pellets and mixture 200 is the cell-weighted mixture containing
the 2.96%-enriched uranium pellets. Determine the h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j ubah}(h]h]h]h]h]uhjh jubh/4 of this
system. Input data for this problem follow.}(h4 of this
system. Input data for this problem follow.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhMQh jxhhubj)}(hX=CSAS6
2.57% AND 2.96% ENR UO2 PELLETS IN 3500 PPM BORATED WATER
V7-238
READ COMP
UO2 1 0.925 283 92235 2.57 92238 97.43 END
H2O 2 1.0 283 END
ATOMBACID 2 2.0017-2 3 5000 1 1001 3 8016 3 1.0 283 END
UO2 3 0.925 283 92235 2.96 92238 97.04 END
H2O 4 1.0 283 END
ATOMBACID 4 2.0017-2 3 5000 1 1001 3 8016 3 1.0 283 END
SS304 5 1.0 283 END
END COMP
READ CELLDATA
LATTICECELL CELLMIX=100 SPHTRIANGP PITCH=1.13 2 FUELD=1.07 1 END
LATTICECELL CELLMIX=200 SPHTRIANGP PITCH=1.13 4 FUELD=1.07 3 END
END CELLDATA
READ PARAM FLX=YES END PARAM
READ GEOM
GLOBAL UNIT 1
CYLINDER 10 38.0 45.5 0.0
CYLINDER 20 38.0 91.0 0.0
CYLINDER 30 38.125 91.0 -0.125
MEDIA 100 1 10
MEDIA 200 1 20 -10
MEDIA 5 1 30 -20
BOUNDARY 30
END GEOM
END DATA
ENDh]h/X=CSAS6
2.57% AND 2.96% ENR UO2 PELLETS IN 3500 PPM BORATED WATER
V7-238
READ COMP
UO2 1 0.925 283 92235 2.57 92238 97.43 END
H2O 2 1.0 283 END
ATOMBACID 2 2.0017-2 3 5000 1 1001 3 8016 3 1.0 283 END
UO2 3 0.925 283 92235 2.96 92238 97.04 END
H2O 4 1.0 283 END
ATOMBACID 4 2.0017-2 3 5000 1 1001 3 8016 3 1.0 283 END
SS304 5 1.0 283 END
END COMP
READ CELLDATA
LATTICECELL CELLMIX=100 SPHTRIANGP PITCH=1.13 2 FUELD=1.07 1 END
LATTICECELL CELLMIX=200 SPHTRIANGP PITCH=1.13 4 FUELD=1.07 3 END
END CELLDATA
READ PARAM FLX=YES END PARAM
READ GEOM
GLOBAL UNIT 1
CYLINDER 10 38.0 45.5 0.0
CYLINDER 20 38.0 91.0 0.0
CYLINDER 30 38.125 91.0 -0.125
MEDIA 100 1 10
MEDIA 200 1 20 -10
MEDIA 5 1 30 -20
BOUNDARY 30
END GEOM
END DATA
END}(hhh j"ubah}(h]h]h]h]h]jjuhjh!jhMYh jxhhubjneh}(h]*run-keno-vi-containing-multiple-unit-cellsah]h]*run keno-vi containing multiple unit cellsah]h]uhh#h h$)}(hhh](h))}(hLCSAS6: Control Module for Enhanced Criticality Safety Analysis with KENO-VIh]h/LCSAS6: Control Module for Enhanced Criticality Safety Analysis with KENO-VI}(hj=h j;hhh!NhNubah}(h]h]h]h]h]uhh(h j8hhh! CSAS6.rsthKubh;)}(hP*L. M. Petrie, K. B. Bekar, D. F. Hollenbach,*\ :sup:`1` *S. Goluoglu*\ :sup:`1`h](h)}(h.*L. M. Petrie, K. B. Bekar, D. F. Hollenbach,*h]h/,L. M. Petrie, K. B. Bekar, D. F. Hollenbach,}(hhh jNubah}(h]h]h]h]h]uhhh jJubh/ }(h\ h jJhhh!NhNubj)}(h:sup:`1`h]h/1}(hhh jaubah}(h]h]h]h]h]uhjh jJubh/ }(hjTh jJhhh!NhNubh)}(h
*S. Goluoglu*h]h/S. Goluoglu}(hhh jsubah}(h]h]h]h]h]uhhh jJubh/ }(hj`h jJubj)}(h:sup:`1`h]h/1}(hhh jubah}(h]h]h]h]h]uhjh jJubeh}(h]h]h]h]h]uhh:h!jIhKh j8hhubh;)}(hXlThe **C**\ riticality **S**\ afety **A**\ nalysis **S**\ equence with
KENO-VI (CSAS6) provides reliable and efficient means of performing
*k\ eff* calculations for systems that are routinely encountered in
engineering practice. In the multigroup calculation mode, CSAS6 uses
XSProc to process the cross sections for temperature corrections and
problem-dependent resonance self-shielding and calculates the *k\ eff*
of three-dimensional (3-D) system models. If the continuous energy
calculation mode is selected no resonance processing is needed and the
continuous energy cross sections are used directly in KENO-VI, with
temperature corrections provided as the cross sections are loaded. The
geometric modeling capabilities available in KENO-VI coupled with the
automated cross-section processing within the control sequences allow
complex, 3-D systems to be easily analyzed.h](h/The }(hThe h jhhh!NhNubhA)}(h**C**h]h/C}(hhh jubah}(h]h]h]h]h]uhh@h jubh/
riticality }(h
\ riticality h jhhh!NhNubhA)}(h**S**h]h/S}(hhh jubah}(h]h]h]h]h]uhh@h jubh/ afety }(h\ afety h jhhh!NhNubhA)}(h**A**h]h/A}(hhh jȉubah}(h]h]h]h]h]uhh@h jubh/
nalysis }(h
\ nalysis h jhhh!NhNubhA)}(h**S**h]h/S}(hhh jۉubah}(h]h]h]h]h]uhh@h jubh/S equence with
KENO-VI (CSAS6) provides reliable and efficient means of performing
}(hS\ equence with
KENO-VI (CSAS6) provides reliable and efficient means of performing
h jhhh!NhNubh)}(h*k\ eff*h]h/k eff}(hhh jubah}(h]h]h]h]h]uhhh jubh/X calculations for systems that are routinely encountered in
engineering practice. In the multigroup calculation mode, CSAS6 uses
XSProc to process the cross sections for temperature corrections and
problem-dependent resonance self-shielding and calculates the }(hX calculations for systems that are routinely encountered in
engineering practice. In the multigroup calculation mode, CSAS6 uses
XSProc to process the cross sections for temperature corrections and
problem-dependent resonance self-shielding and calculates the h jhhh!NhNubh)}(h*k\ eff*h]h/k eff}(hhh jubah}(h]h]h]h]h]uhhh jubh/X
of three-dimensional (3-D) system models. If the continuous energy
calculation mode is selected no resonance processing is needed and the
continuous energy cross sections are used directly in KENO-VI, with
temperature corrections provided as the cross sections are loaded. The
geometric modeling capabilities available in KENO-VI coupled with the
automated cross-section processing within the control sequences allow
complex, 3-D systems to be easily analyzed.}(hX
of three-dimensional (3-D) system models. If the continuous energy
calculation mode is selected no resonance processing is needed and the
continuous energy cross sections are used directly in KENO-VI, with
temperature corrections provided as the cross sections are loaded. The
geometric modeling capabilities available in KENO-VI coupled with the
automated cross-section processing within the control sequences allow
complex, 3-D systems to be easily analyzed.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhK h j8hhubh;)}(h5:sup:`1`\ Formerly with Oak Ridge National Laboratoryh](j)}(h:sup:`1`h]h/1}(hhh jubah}(h]h]h]h]h]uhjh jubh/- Formerly with Oak Ridge National Laboratory}(h-\ Formerly with Oak Ridge National Laboratoryh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKh j8hhubh;)}(hACKNOWLEDGMENTSh]h/ACKNOWLEDGMENTS}(hj9h j7hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh j8hhubh;)}(hX_The CSAS6 Criticality Safety Analysis Sequence is based on the CSAS
control module, and the KENO‑VI functional module, described in their
respective chapters. G. E. Whitesides is acknowledged for his
contributions through early versions of KENO. Appreciation is expressed
to C. V. Parks and S. M. Bowman for their guidance in developing CSAS6.h]h/X_The CSAS6 Criticality Safety Analysis Sequence is based on the CSAS
control module, and the KENO‑VI functional module, described in their
respective chapters. G. E. Whitesides is acknowledged for his
contributions through early versions of KENO. Appreciation is expressed
to C. V. Parks and S. M. Bowman for their guidance in developing CSAS6.}(hjGh jEhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh j8hhubh$)}(hhh](h))}(hIntroductionh]h/Introduction}(hjXh jVhhh!NhNubah}(h]h]h]h]h]uhh(h jShhh!jIhK#ubh;)}(hXCriticality Safety Analysis Sequence with KENO-VI (CSAS6) provides
reliable and efficient means of performing *k\ eff* calculations for
systems that are routinely encountered in engineering practice,
especially in the calculation of *k\ eff* of three-dimensional (3-D)
system models. CSAS6 implements XSProc to process material input and
provide a temperature and resonance-corrected cross-section library
based on the physical characteristics of the problem being analyzed. If
a continuous energy cross-section library is specified, no resonance
processing is needed and the continuous energy cross sections are used
directly in KENO-VI, with temperature corrections provided as the cross
sections are loaded.h](h/nCriticality Safety Analysis Sequence with KENO-VI (CSAS6) provides
reliable and efficient means of performing }(hnCriticality Safety Analysis Sequence with KENO-VI (CSAS6) provides
reliable and efficient means of performing h jdhhh!NhNubh)}(h*k\ eff*h]h/k eff}(hhh jmubah}(h]h]h]h]h]uhhh jdubh/s calculations for
systems that are routinely encountered in engineering practice,
especially in the calculation of }(hs calculations for
systems that are routinely encountered in engineering practice,
especially in the calculation of h jdhhh!NhNubh)}(h*k\ eff*h]h/k eff}(hhh jubah}(h]h]h]h]h]uhhh jdubh/X of three-dimensional (3-D)
system models. CSAS6 implements XSProc to process material input and
provide a temperature and resonance-corrected cross-section library
based on the physical characteristics of the problem being analyzed. If
a continuous energy cross-section library is specified, no resonance
processing is needed and the continuous energy cross sections are used
directly in KENO-VI, with temperature corrections provided as the cross
sections are loaded.}(hX of three-dimensional (3-D)
system models. CSAS6 implements XSProc to process material input and
provide a temperature and resonance-corrected cross-section library
based on the physical characteristics of the problem being analyzed. If
a continuous energy cross-section library is specified, no resonance
processing is needed and the continuous energy cross sections are used
directly in KENO-VI, with temperature corrections provided as the cross
sections are loaded.h jdhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhK%h jShhubeh}(h]id28ah]h]h]introductionah]uhh#h j8hhh!jIhK#jmKubh$)}(hhh](h))}(hSequence Capabilitiesh]h/Sequence Capabilities}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhK2ubh;)}(hXfCSAS6 is designed to prepare a resonance-corrected cross-section library
for subsequent use in KENO‑VI. In order to minimize human error, the
SCALE data handling is automated as much as possible. CSAS6 and many
other SCALE sequences apply a standardized procedure to provide
appropriate number densities and cross sections for the calculation.
XSProc is responsible for reading the standard composition data and
other engineering-type specifications, including volume fraction or
percent theoretical density, temperature, and isotopic distribution as
well as the unit cell data. XSProc then generates number densities and
related information, prepares geometry data for resonance self-shielding
and flux-weighting cell calculations, if needed, and (if needed)
provides problem-dependent multigroup cross-section processing. CSAS6
invokes a KENO-VI Data Processor to read and check the KENO-VI data.
When the data checking has been completed, the control sequence executes
XSProc to prepare a resonance-corrected microscopic cross-section
library in the AMPX working library format if a multigroup library has
been selected.h]h/XfCSAS6 is designed to prepare a resonance-corrected cross-section library
for subsequent use in KENO‑VI. In order to minimize human error, the
SCALE data handling is automated as much as possible. CSAS6 and many
other SCALE sequences apply a standardized procedure to provide
appropriate number densities and cross sections for the calculation.
XSProc is responsible for reading the standard composition data and
other engineering-type specifications, including volume fraction or
percent theoretical density, temperature, and isotopic distribution as
well as the unit cell data. XSProc then generates number densities and
related information, prepares geometry data for resonance self-shielding
and flux-weighting cell calculations, if needed, and (if needed)
provides problem-dependent multigroup cross-section processing. CSAS6
invokes a KENO-VI Data Processor to read and check the KENO-VI data.
When the data checking has been completed, the control sequence executes
XSProc to prepare a resonance-corrected microscopic cross-section
library in the AMPX working library format if a multigroup library has
been selected.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhK4h jhhubh;)}(hX=For each unit cell specified as being cell-weighted, XSProc performs the
necessary calculations and produces a cell-weighted microscopic
cross-section library. KENO-VI may be executed to calculate the *k\ eff*
or neutron multiplication factor using the cross-section library that
was prepared by the control sequence.h](h/For each unit cell specified as being cell-weighted, XSProc performs the
necessary calculations and produces a cell-weighted microscopic
cross-section library. KENO-VI may be executed to calculate the }(hFor each unit cell specified as being cell-weighted, XSProc performs the
necessary calculations and produces a cell-weighted microscopic
cross-section library. KENO-VI may be executed to calculate the h jhhh!NhNubh)}(h*k\ eff*h]h/k eff}(hhh jɊubah}(h]h]h]h]h]uhhh jubh/l
or neutron multiplication factor using the cross-section library that
was prepared by the control sequence.}(hl
or neutron multiplication factor using the cross-section library that
was prepared by the control sequence.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKFh jhhubeh}(h]id29ah]h]h]sequence capabilitiesah]uhh#h j8hhh!jIhK2jmKubh$)}(hhh](h))}(hMultigroup CSAS6 limitationsh]h/Multigroup CSAS6 limitations}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhKMubh;)}(hXyThe CSAS6 control module was developed to use simple input data and
prepare problem-dependent cross sections for use in calculating the
effective neutron multiplication factor of a 3-D system using KENO-VI
and possibly XSDRNPM. An attempt was made to make the system as general
as possible within the constraints of the standardized methods chosen to
be used in SCALE. Standardized methods of data input were adopted to
allow easy data entry and for quality assurance purposes. Some of the
limitations of the CSAS6 sequence are a result of using preprocessed
multigroup cross sections. Inherent limitations in CSAS6 are as follows:h]h/XyThe CSAS6 control module was developed to use simple input data and
prepare problem-dependent cross sections for use in calculating the
effective neutron multiplication factor of a 3-D system using KENO-VI
and possibly XSDRNPM. An attempt was made to make the system as general
as possible within the constraints of the standardized methods chosen to
be used in SCALE. Standardized methods of data input were adopted to
allow easy data entry and for quality assurance purposes. Some of the
limitations of the CSAS6 sequence are a result of using preprocessed
multigroup cross sections. Inherent limitations in CSAS6 are as follows:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKOh jhhubh block_quote)}(hhh]h;)}(hX1. Two-dimensional (2-D) effects such as fuel rods in assemblies
where some positions are filled with control rod guide tubes,
burnable poison rods and/or fuel rods of different enrichments. The
cross sections are processed as if the rods are in an infinite
lattice of rods. If the user inputs a Dancoff factor for the cell
(such as one computed by MCDancoff), XSProc can produce an infinite
lattice cell, which reproduces that Dancoff. This can mitigate some
two dimensional lattice effects.h]h/X1. Two-dimensional (2-D) effects such as fuel rods in assemblies
where some positions are filled with control rod guide tubes,
burnable poison rods and/or fuel rods of different enrichments. The
cross sections are processed as if the rods are in an infinite
lattice of rods. If the user inputs a Dancoff factor for the cell
(such as one computed by MCDancoff), XSProc can produce an infinite
lattice cell, which reproduces that Dancoff. This can mitigate some
two dimensional lattice effects.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKYh jubah}(h]h]h]h]h]uhj h jhhh!jIhNubh;)}(hIt is strongly recommended that the user perform CSAS6 calculations of
benchmark experiments similar to the problem of interest to demonstrate
the validity of the cross-section data and processing for that type of
problem.h]h/It is strongly recommended that the user perform CSAS6 calculations of
benchmark experiments similar to the problem of interest to demonstrate
the validity of the cross-section data and processing for that type of
problem.}(hj$h j"hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKbh jhhubh$)}(hhh](h))}(h#Continuous energy CSAS6 limitationsh]h/#Continuous energy CSAS6 limitations}(hj5h j3hhh!NhNubah}(h]h]h]h]h]uhh(h j0hhh!jIhKhubh;)}(hXWhen continuous energy KENO calculations are desired, none of the
resonance processing modules are applicable or needed. Moreover, the MG
limitations noted in the previous section are eliminated. The continuous
energy cross sections are directly used in KENO. An existing multigroup
input file can easily be converted to a continuous energy input file by
simply specifying the continuous energy library. In this case, all cell
data is ignored. However, the following limitations exist:h]h/XWhen continuous energy KENO calculations are desired, none of the
resonance processing modules are applicable or needed. Moreover, the MG
limitations noted in the previous section are eliminated. The continuous
energy cross sections are directly used in KENO. An existing multigroup
input file can easily be converted to a continuous energy input file by
simply specifying the continuous energy library. In this case, all cell
data is ignored. However, the following limitations exist:}(hjCh jAhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKjh j0hhubj )}(hhh](j)}(hIf CELLMIX is defined in the cell data, the problem will not run in
the continuous energy mode. CELLMIX implies new mixture cross
sections are generated using XSDRNPM-calculated cell fluxes and
therefore is not applicable in the continuous energy mode.
h]h;)}(hIf CELLMIX is defined in the cell data, the problem will not run in
the continuous energy mode. CELLMIX implies new mixture cross
sections are generated using XSDRNPM-calculated cell fluxes and
therefore is not applicable in the continuous energy mode.h]h/If CELLMIX is defined in the cell data, the problem will not run in
the continuous energy mode. CELLMIX implies new mixture cross
sections are generated using XSDRNPM-calculated cell fluxes and
therefore is not applicable in the continuous energy mode.}(hjXh jVubah}(h]h]h]h]h]uhh:h!jIhKrh jRubah}(h]h]h]h]h]uhjh jOhhh!jIhNubj)}(hOnly VACUUM, MIRROR, PERIODIC, and WHITE boundary conditions are
allowed. Other albedos, e.g., WATER, CARBON, POLY, etc. are for
multigroup only.
h]h;)}(hOnly VACUUM, MIRROR, PERIODIC, and WHITE boundary conditions are
allowed. Other albedos, e.g., WATER, CARBON, POLY, etc. are for
multigroup only.h]h/Only VACUUM, MIRROR, PERIODIC, and WHITE boundary conditions are
allowed. Other albedos, e.g., WATER, CARBON, POLY, etc. are for
multigroup only.}(hjph jnubah}(h]h]h]h]h]uhh:h!jIhKwh jjubah}(h]h]h]h]h]uhjh jOhhh!jIhNubj)}(h^Problems with DOUBLEHET cell data are not allowed as they inherently
utilize CELLMIX feature.
h]h;)}(h]Problems with DOUBLEHET cell data are not allowed as they inherently
utilize CELLMIX feature.h]h/]Problems with DOUBLEHET cell data are not allowed as they inherently
utilize CELLMIX feature.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhK{h jubah}(h]h]h]h]h]uhjh jOhhh!jIhNubeh}(h]h]h]h]h]j j j hj juhj h j0hhh!jIhKrubeh}(h]#continuous-energy-csas6-limitationsah]h]#continuous energy csas6 limitationsah]h]uhh#h jhhh!jIhKhubeh}(h]multigroup-csas6-limitationsah]h]multigroup csas6 limitationsah]h]uhh#h j8hhh!jIhKMubh$)}(hhh](h))}(hInput Data Guideh]h/Input Data Guide}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhKubh;)}(hXDThe input data for CSAS6 are composed of two broad categories of data.
The first is XSProc, including Standard Composition Specification Data
and Unit Cell Geometry Specification. This first category specifies the
cross-section library and defines the composition of each mixture and
optionally the unit cell geometry that may be used to process the
cross sections. The second category of data, the KENO-VI input data, is
used to specify the geometric and boundary conditions that represent the
physical 3-D configuration of the problem. Both data blocks are
necessary for CSAS6.h]h/XDThe input data for CSAS6 are composed of two broad categories of data.
The first is XSProc, including Standard Composition Specification Data
and Unit Cell Geometry Specification. This first category specifies the
cross-section library and defines the composition of each mixture and
optionally the unit cell geometry that may be used to process the
cross sections. The second category of data, the KENO-VI input data, is
used to specify the geometric and boundary conditions that represent the
physical 3-D configuration of the problem. Both data blocks are
necessary for CSAS6.}(hjËh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubh;)}(hXAll data are entered in free form, allowing alphanumeric data,
floating-point data, and integer data to be entered in an unstructured
manner. Up to 252 columns of data entry per line are allowed. Data can
usually start or end in any column with a few exceptions. As an example,
the word END beginning in column 1 and followed by two blank spaces or a
new line will end the problem and any data following will be ignored.
Each data entry must be followed by one or more blanks to terminate the
data entry. For numeric data, either a comma or a blank can be used to
terminate each data entry. Integers may be entered for floating values.
For example, 10 will be interpreted as 10.0. Imbedded blanks are not
allowed within a data entry unless an E precedes a single blank as in an
unsigned exponent in a floating-point number. For example, 1.0E 4 would
be correctly interpreted as 1.0 × 10\ :sup:`4`.h](h/X~All data are entered in free form, allowing alphanumeric data,
floating-point data, and integer data to be entered in an unstructured
manner. Up to 252 columns of data entry per line are allowed. Data can
usually start or end in any column with a few exceptions. As an example,
the word END beginning in column 1 and followed by two blank spaces or a
new line will end the problem and any data following will be ignored.
Each data entry must be followed by one or more blanks to terminate the
data entry. For numeric data, either a comma or a blank can be used to
terminate each data entry. Integers may be entered for floating values.
For example, 10 will be interpreted as 10.0. Imbedded blanks are not
allowed within a data entry unless an E precedes a single blank as in an
unsigned exponent in a floating-point number. For example, 1.0E 4 would
be correctly interpreted as 1.0 × 10 }(hX~All data are entered in free form, allowing alphanumeric data,
floating-point data, and integer data to be entered in an unstructured
manner. Up to 252 columns of data entry per line are allowed. Data can
usually start or end in any column with a few exceptions. As an example,
the word END beginning in column 1 and followed by two blank spaces or a
new line will end the problem and any data following will be ignored.
Each data entry must be followed by one or more blanks to terminate the
data entry. For numeric data, either a comma or a blank can be used to
terminate each data entry. Integers may be entered for floating values.
For example, 10 will be interpreted as 10.0. Imbedded blanks are not
allowed within a data entry unless an E precedes a single blank as in an
unsigned exponent in a floating-point number. For example, 1.0E 4 would
be correctly interpreted as 1.0 × 10\ h jϋhhh!NhNubj)}(h:sup:`4`h]h/4}(hhh j؋ubah}(h]h]h]h]h]uhjh jϋubh/.}(hjh jϋhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKh jhhubh;)}(hX The word “END” is a special data item. An “END” may have a name or label
associated with it. The name or label associated with an “END” is
separated from the “END” by a single blank and is a maximum of
12 characters long. *At least two blanks or a new line MUST follow every
labeled and unlabeled “END.” It is the user’s responsibility to ensure
compliance with this restriction. Failure to observe this restriction
can result in the use of incorrect or incomplete data without the
benefit of warning or error messages.*h](h/The word “END” is a special data item. An “END” may have a name or label
associated with it. The name or label associated with an “END” is
separated from the “END” by a single blank and is a maximum of
12 characters long. }(hThe word “END” is a special data item. An “END” may have a name or label
associated with it. The name or label associated with an “END” is
separated from the “END” by a single blank and is a maximum of
12 characters long. h jhhh!NhNubh)}(hX1*At least two blanks or a new line MUST follow every
labeled and unlabeled “END.” It is the user’s responsibility to ensure
compliance with this restriction. Failure to observe this restriction
can result in the use of incorrect or incomplete data without the
benefit of warning or error messages.*h]h/X/At least two blanks or a new line MUST follow every
labeled and unlabeled “END.” It is the user’s responsibility to ensure
compliance with this restriction. Failure to observe this restriction
can result in the use of incorrect or incomplete data without the
benefit of warning or error messages.}(hhh jubah}(h]h]h]h]h]uhhh jubeh}(h]h]h]h]h]uhh:h!jIhKh jhhubh;)}(hXMultiple entries of the same data value can be achieved by specifying
the number of times the data value is to be entered, followed by either
R, \*, or $, followed by the data value to be repeated. Imbedded blanks
are not allowed between the number of repeats and the repeat flag. For
example, 5R12, 5*12, 5$12, or 5R 12, etc., will enter five successive
12s in the input data. Multiple zeros can be specified as nZ where n is
the number of zeroes to be entered.h]h/XMultiple entries of the same data value can be achieved by specifying
the number of times the data value is to be entered, followed by either
R, *, or $, followed by the data value to be repeated. Imbedded blanks
are not allowed between the number of repeats and the repeat flag. For
example, 5R12, 5*12, 5$12, or 5R 12, etc., will enter five successive
12s in the input data. Multiple zeros can be specified as nZ where n is
the number of zeroes to be entered.}(hXMultiple entries of the same data value can be achieved by specifying
the number of times the data value is to be entered, followed by either
R, \*, or $, followed by the data value to be repeated. Imbedded blanks
are not allowed between the number of repeats and the repeat flag. For
example, 5R12, 5*12, 5$12, or 5R 12, etc., will enter five successive
12s in the input data. Multiple zeros can be specified as nZ where n is
the number of zeroes to be entered.h j
hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubh;)}(hThe purpose of this section is to define the input data in discrete
subsections relating to a particular type of data. Tables of the input
data are included in each subsection, and the entries are described in
more detail in the appropriate sections.h]h/The purpose of this section is to define the input data in discrete
subsections relating to a particular type of data. Tables of the input
data are included in each subsection, and the entries are described in
more detail in the appropriate sections.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubh;)}(hXResonance-corrected cross sections are generated using the appropriate
boundary conditions for the unit cell description (i.e., void for the
outer surface of a single unit, white for the outer surface of an
infinite array of cylinders, spheres, or planes). As many unit cells as
needed may be specified in a problem. A unit cell is cell‑weighted by
using the keyword CELLMIX= followed by a unique user specified mixture
number in the unit cell data.h]h/XResonance-corrected cross sections are generated using the appropriate
boundary conditions for the unit cell description (i.e., void for the
outer surface of a single unit, white for the outer surface of an
infinite array of cylinders, spheres, or planes). As many unit cells as
needed may be specified in a problem. A unit cell is cell‑weighted by
using the keyword CELLMIX= followed by a unique user specified mixture
number in the unit cell data.}(hj,h j*hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubh;)}(hTo check the input data without actually processing the cross sections,
the words “PARM=CHECK” or “PARM=CHK” should be entered, as shown below.h]h/To check the input data without actually processing the cross sections,
the words “PARM=CHECK” or “PARM=CHK” should be entered, as shown below.}(hj:h j8hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubj
)}(hhh]h;)}(h=CSAS6 PARM=CHKh]h/=CSAS6 PARM=CHK}(hjKh jIubah}(h]h]h]h]h]uhh:h!jIhKh jFubah}(h]h]h]h]h]uhj h jhhh!jIhNubh;)}(horh]h/or}(hj_h j]hhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubj
)}(hhh]h;)}(h#CSAS6 PARM=CHKh]h/#CSAS6 PARM=CHK}(hjph jnubah}(h]h]h]h]h]uhh:h!jIhKh jkubah}(h]h]h]h]h]uhj h jhhh!jIhNubh;)}(hXThis will cause the input data for CSAS6 to be checked and appropriate
error messages to be printed. If plots are specified in the data, they
will be printed. This feature allows the user to debug and verify the
input data while using a minimum amount of computer time.h]h/XThis will cause the input data for CSAS6 to be checked and appropriate
error messages to be printed. If plots are specified in the data, they
will be printed. This feature allows the user to debug and verify the
input data while using a minimum amount of computer time.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubh$)}(hhh](h))}(hXSProc datah]h/XSProc data}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhKubh;)}(hXGThe XSProc reads the standard composition specification data and the
unit cell geometry specifications. It then produces the mixing table and
unit cell information necessary for processing the cross sections if
needed. The XSProc section of this manual provides a detailed
description of the input data and processing options.h]h/XGThe XSProc reads the standard composition specification data and the
unit cell geometry specifications. It then produces the mixing table and
unit cell information necessary for processing the cross sections if
needed. The XSProc section of this manual provides a detailed
description of the input data and processing options.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhKh jhhubeh}(h]id31ah]h]h]xsproc dataah]uhh#h jhhh!jIhKjmKubh$)}(hhh](h))}(hKENO-VI datah]h/KENO-VI data}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhKubh;)}(hXp:numref:`tab2-2-1` contains the outline for the KENO-VI input. The KENO-VI
input is divided into 13 data blocks. A brief outline of commonly used
data blocks is shown in :numref:`tab2-2-1`. Note that parameter data must
precede all other KENO data blocks. Information on all KENO-VI input is
provided in the KENO chapter of this document and will not be repeated
here.h](h_)}(h:numref:`tab2-2-1`h]j)}(hjΌh]h/tab2-2-1}(hhh jЌubah}(h]h](jstd
std-numrefeh]h]h]uhjh ǰubah}(h]h]h]h]h]refdocj refdomainjڌreftypenumrefrefexplicitrefwarnjtab2-2-1uhh^h!jIhKh jȌubh/ contains the outline for the KENO-VI input. The KENO-VI
input is divided into 13 data blocks. A brief outline of commonly used
data blocks is shown in }(h contains the outline for the KENO-VI input. The KENO-VI
input is divided into 13 data blocks. A brief outline of commonly used
data blocks is shown in h jȌhhh!NhNubh_)}(h:numref:`tab2-2-1`h]j)}(hjh]h/tab2-2-1}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-2-1uhh^h!jIhKh jȌubh/. Note that parameter data must
precede all other KENO data blocks. Information on all KENO-VI input is
provided in the KENO chapter of this document and will not be repeated
here.}(h. Note that parameter data must
precede all other KENO data blocks. Information on all KENO-VI input is
provided in the KENO chapter of this document and will not be repeated
here.h jȌhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhKh jhhubh)}(h
.. _tab2-2-1:h]h}(h]h]h]h]h]htab2-2-1uhh
hM}h jhhh!jIubj)}(hhh](h))}(hOutline of KENO datah]h/Outline of KENO data}(hj,h j*ubah}(h]h]h]h]h]uhh(h!jIhKh j'ubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j8ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j8ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j8ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j8ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(h**Type of
data**h]hA)}(hjnh]h/Type of
data}(hhh jpubah}(h]h]h]h]h]uhh@h jlubah}(h]h]h]h]h]uhh:h!jIhKh jiubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h;)}(h**Starting
flag**h]hA)}(hjh]h/
Starting
flag}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h;)}(h**Comments**h]hA)}(hjh]h/Comments}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h;)}(h**Termination
flag**h]hA)}(hjh]h/Termination
flag}(hhh jЍubah}(h]h]h]h]h]uhh@h j̍ubah}(h]h]h]h]h]uhh:h!jIhKh jɍubah}(h]h]h]h]h]uhj9h jfubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hParameters\*h]h/Parameters*}(hParameters\*h jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hREAD PARAMETERh]h/READ PARAMETER}(hjh j
ubah}(h]h]h]h]h]uhh:h!jIhKh j
ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnter
desired
parameter
datah]h/Enter
desired
parameter
data}(hj&h j$ubah}(h]h]h]h]h]uhh:h!jIhKh j!ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
END PARAMETERh]h/
END PARAMETER}(hj=h j;ubah}(h]h]h]h]h]uhh:h!jIhKh j8ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hGeometryh]h/Geometry}(hj]h j[ubah}(h]h]h]h]h]uhh:h!jIhKh jXubah}(h]h]h]h]h]uhj9h jUubj:)}(hhh]h;)}(h
READ GEOMETRYh]h/
READ GEOMETRY}(hjth jrubah}(h]h]h]h]h]uhh:h!jIhKh joubah}(h]h]h]h]h]uhj9h jUubj:)}(hhh]h;)}(hEnter
desired
geometry
datah]h/Enter
desired
geometry
data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jUubj:)}(hhh]h;)}(hEND GEOMETRYh]h/END GEOMETRY}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jUubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(h
Array datah]h/
Array data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
READ ARRAYh]h/
READ ARRAY}(hjَh jubah}(h]h]h]h]h]uhh:h!jIhKh jԎubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnter
desired
array datah]h/Enter
desired
array data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h END ARRAYh]h/ END ARRAY}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hBoundary
conditionsh]h/Boundary
conditions}(hj'h j%ubah}(h]h]h]h]h]uhh:h!jIhKh j"ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hREAD BOUNDSh]h/READ BOUNDS}(hj>h j<ubah}(h]h]h]h]h]uhh:h!jIhKh j9ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h!Enter
desired
boundary
conditionsh]h/!Enter
desired
boundary
conditions}(hjUh jSubah}(h]h]h]h]h]uhh:h!jIhKh jPubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
END BOUNDSh]h/
END BOUNDS}(hjlh jjubah}(h]h]h]h]h]uhh:h!jIhKh jgubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hEnergy group
boundariesh]h/Energy group
boundaries}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hREAD ENERGYh]h/READ ENERGY}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h-Enter
desired
neutron
energy group
boundariesh]h/-Enter
desired
neutron
energy group
boundaries}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
END ENERGYh]h/
END ENERGY}(hjяh jϏubah}(h]h]h]h]h]uhh:h!jIhKh j̏ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hStart data
or initial
sourceh]h/Start data
or initial
source}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
READ STARTh]h/
READ START}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnter
desired
start datah]h/Enter
desired
start data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h END STARTh]h/ END START}(hj6h j4ubah}(h]h]h]h]h]uhh:h!jIhKh j1ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(h Plot datah]h/ Plot data}(hjVh jTubah}(h]h]h]h]h]uhh:h!jIhKh jQubah}(h]h]h]h]h]uhj9h jNubj:)}(hhh]h;)}(h READ PLOTh]h/ READ PLOT}(hjmh jkubah}(h]h]h]h]h]uhh:h!jIhKh jhubah}(h]h]h]h]h]uhj9h jNubj:)}(hhh]h;)}(hEnter
desired plot
datah]h/Enter
desired plot
data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jNubj:)}(hhh]h;)}(hEND PLOTh]h/END PLOT}(hjh jubah}(h]h]h]h]h]uhh:h!jIhKh jubah}(h]h]h]h]h]uhj9h jNubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hGrid
geometry
datah]h/Grid
geometry
data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h READ GRIDh]h/ READ GRID}(hjҐh jАubah}(h]h]h]h]h]uhh:h!jIhMh j͐ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnter
desired mesh
datah]h/Enter
desired mesh
data}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEND GRIDh]h/END GRID}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hReactionh]h/Reaction}(hj h jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
READ REACTIONh]h/
READ REACTION}(hj7h j5ubah}(h]h]h]h]h]uhh:h!jIhMh j2ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h,Enter desire
reaction
tallies (CE
mode only)h]h/,Enter desire
reaction
tallies (CE
mode only)}(hjNh jLubah}(h]h]h]h]h]uhh:h!jIhMh jIubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEND REACTIONh]h/END REACTION}(hjeh jcubah}(h]h]h]h]h]uhh:h!jIhMh j`ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(hKENO-VI data
terminush]h/KENO-VI data
terminus}(hjh jubah}(h]h]h]h]h]uhh:h!jIhM h jubah}(h]h]h]h]h]uhj9h j}ubj:)}(hhh]h;)}(hEND DATAh]h/END DATA}(hjh jubah}(h]h]h]h]h]uhh:h!jIhM h jubah}(h]h]h]h]h]uhj9h j}ubj:)}(hhh]h
line_block)}(hhh](h h)}(hEnter to
signal the
end of allh]h/Enter to
signal the
end of all}(hjh jubah}(h]h]h]h]h]uhhindentKh jh!jIhKubj)}(hKENO-VI
datah]h/KENO-VI
data}(hjȑh jƑubah}(h]h]h]h]h]uhhjőKh jh!jIhKubeh}(h]h]h]h]h]uhjh jubah}(h]h]h]h]h]uhj9h j}ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j}ubeh}(h]h]h]h]h]uhj4h jcubj5)}(hhh](j:)}(hhh]h;)}(h3\*Must precede
all other data
blocks in this
table.h]h/3*Must precede
all other data
blocks in this
table.}(h3\*Must precede
all other data
blocks in this
table.h jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jcubeh}(h]h]h]h]h]uhj/h j8ubeh}(h]h]h]h]h]colsKuhjh j'ubeh}(h](id78j&eh]h]tab2-2-1ah]h]jjuhjh jhhh!jIhNj}j=jsj}j&jsubeh}(h]keno-vi-dataah]h]keno-vi dataah]h]uhh#h jhhh!jIhKubeh}(h]id30ah]h]h]input data guideah]uhh#h j8hhh!jIhKjmKubh$)}(hhh](h))}(hSample Problemsh]h/Sample Problems}(hjWh jUhhh!NhNubah}(h]h]h]h]h]uhh(h jRhhh!jIhMubh;)}(hXThis section contains sample problems to demonstrate some of the options
available in CSAS6. A brief problem description and the associated input
data for multigroup mode of calculation are included for each problem.
The same sample problems may be executed in the continuous energy mode
by changing the library name to an continuous-energy library. See
Appendix A (SECTIONREFERENCE) for additional examples.h]h/XThis section contains sample problems to demonstrate some of the options
available in CSAS6. A brief problem description and the associated input
data for multigroup mode of calculation are included for each problem.
The same sample problems may be executed in the continuous energy mode
by changing the library name to an continuous-energy library. See
Appendix A (SECTIONREFERENCE) for additional examples.}(hjeh jchhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jRhhubh$)}(hhh](h))}(hsample-problem-4-sphere-models-using-chords-and-mirror-albedosah]h]?sample problem 4: sphere models using chords and mirror albedosah]h]uhh#h jRhhh!jIhMubh$)}(hhh](h))}(h?Sample Problem 5: Sphere Models Using Chords and Mirror Albedosh]h/?Sample Problem 5: Sphere Models Using Chords and Mirror Albedos}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhMubh;)}(hThis problem models an assembly consisting of a 93.2% enriched bare
uranium sphere, 8.741 cm in radius, having a density of
18.76 gm/cm\ :sup:`3`. The problem models the assembly as a quarter
sphere with mirror reflection on the two flat surfaces.h](h/This problem models an assembly consisting of a 93.2% enriched bare
uranium sphere, 8.741 cm in radius, having a density of
18.76 gm/cm }(hThis problem models an assembly consisting of a 93.2% enriched bare
uranium sphere, 8.741 cm in radius, having a density of
18.76 gm/cm\ h j)hhh!NhNubj)}(h:sup:`3`h]h/3}(hhh j2ubah}(h]h]h]h]h]uhjh j)ubh/f. The problem models the assembly as a quarter
sphere with mirror reflection on the two flat surfaces.}(hf. The problem models the assembly as a quarter
sphere with mirror reflection on the two flat surfaces.h j)hhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jhhubj)}(hX=csas6
sample problem 5 bare 93.2% U sphere, quarter sphere w/ mirror albedo
v7-238
read comp
uranium 1 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
end comp
read geometry
global unit 1
sphere 10 8.741 chord +x=0.0 chord +y=0.0
cuboid 20 8.741 0.0 8.741 0.0 8.741 -8.741
media 1 1 10 vol=2797.5121
media 0 1 20 -10 vol=2545.3424
boundary 20
end geometry
read bounds
-xy=mirror
end bounds
end data
endh]h/X=csas6
sample problem 5 bare 93.2% U sphere, quarter sphere w/ mirror albedo
v7-238
read comp
uranium 1 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
end comp
read geometry
global unit 1
sphere 10 8.741 chord +x=0.0 chord +y=0.0
cuboid 20 8.741 0.0 8.741 0.0 8.741 -8.741
media 1 1 10 vol=2797.5121
media 0 1 20 -10 vol=2545.3424
boundary 20
end geometry
read bounds
-xy=mirror
end bounds
end data
end}(hhh jKubah}(h]h]h]h]h]jjuhjh!jIhM"h jhhubeh}(h]>sample-problem-5-sphere-models-using-chords-and-mirror-albedosah]h]?sample problem 5: sphere models using chords and mirror albedosah]h]uhh#h jRhhh!jIhMubh$)}(hhh](h))}(hOSample Problem 6: Sphere Models Using Chords and Mirror Albedos (Eighth Sphere)h]h/OSample Problem 6: Sphere Models Using Chords and Mirror Albedos (Eighth Sphere)}(hjfh jdhhh!NhNubah}(h]h]h]h]h]uhh(h jahhh!jIhM7ubh;)}(hThis problem models an assembly consisting of a 93.2% enriched bare
uranium sphere, 8.741 cm in radius, having a density of
18.76 gm/cm\ :sup:`3`. The problem models the assembly as an eighth
sphere with mirror reflection on the three flat surfaces.h](h/This problem models an assembly consisting of a 93.2% enriched bare
uranium sphere, 8.741 cm in radius, having a density of
18.76 gm/cm }(hThis problem models an assembly consisting of a 93.2% enriched bare
uranium sphere, 8.741 cm in radius, having a density of
18.76 gm/cm\ h jrhhh!NhNubj)}(h:sup:`3`h]h/3}(hhh j{ubah}(h]h]h]h]h]uhjh jrubh/h. The problem models the assembly as an eighth
sphere with mirror reflection on the three flat surfaces.}(hh. The problem models the assembly as an eighth
sphere with mirror reflection on the three flat surfaces.h jrhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhM9h jahhubj)}(hX=csas6
sample problem 6 bare 93.2% U sphere, eighth sphere w/ mirror albedo
v7-238
read comp
uranium 1 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
end comp
read geometry
global unit 1
sphere 10 8.741 chord +x=0.0 chord +y=0.0 chord +z=0.0
cuboid 20 8.741 0.0 8.741 0.0 8.741 0.0
media 1 1 10 vol=2797.5121
media 0 1 20 -10 vol=2545.3424
boundary 20
end geometry
read bounds
-fc=mirror
end bounds
end data
endh]h/X=csas6
sample problem 6 bare 93.2% U sphere, eighth sphere w/ mirror albedo
v7-238
read comp
uranium 1 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
end comp
read geometry
global unit 1
sphere 10 8.741 chord +x=0.0 chord +y=0.0 chord +z=0.0
cuboid 20 8.741 0.0 8.741 0.0 8.741 0.0
media 1 1 10 vol=2797.5121
media 0 1 20 -10 vol=2545.3424
boundary 20
end geometry
read bounds
-fc=mirror
end bounds
end data
end}(hhh jubah}(h]h]h]h]h]jjuhjh!jIhM@h jahhubeh}(h]Lsample-problem-6-sphere-models-using-chords-and-mirror-albedos-eighth-sphereah]h]Osample problem 6: sphere models using chords and mirror albedos (eighth sphere)ah]h]uhh#h jRhhh!jIhM7ubh$)}(hhh](h))}(h1Sample Problem 7: Grotesque without the Diaphragmh]h/1Sample Problem 7: Grotesque without the Diaphragm}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhMUubh;)}(hXThe purpose of this problem is to calculate the *k*\ :sub:`eff` of a system
composed of eight enriched uranium units placed on a diaphragm, with an
irregularly shaped centerpiece positioned in the center hole of the
diaphragm :cite:`mihalczo_brief_1999` The assembly and centerpiece are shown in :numref:`fig2-2-3`,
which is Fig. 4 from Ref. 1. The eight units consist of an approximate
parallelepiped with an irregular top, a parallelepiped, and
six cylinders of various sizes. The centerpiece, which penetrates the
hole in the diaphragm, consists of a cylinder topped by a parallelepiped
topped by a hemisphere. The diaphragm is not modeled in this example.h](h/0The purpose of this problem is to calculate the }(h0The purpose of this problem is to calculate the h jhhh!NhNubh)}(h*k*h]h/k}(hhh jĕubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jוubah}(h]h]h]h]h]uhjh jubh/ of a system
composed of eight enriched uranium units placed on a diaphragm, with an
irregularly shaped centerpiece positioned in the center hole of the
diaphragm }(h of a system
composed of eight enriched uranium units placed on a diaphragm, with an
irregularly shaped centerpiece positioned in the center hole of the
diaphragm h jhhh!NhNubh_)}(hmihalczo_brief_1999h]he)}(hjh]h/[mihalczo_brief_1999]}(hhh jubah}(h]h]h]h]h]uhhdh jubah}(h]id32ah]hwah]h]h] refdomainh|reftypeh~ reftargetjrefwarnsupport_smartquotesuhh^h!jIhMWh jhhubh/+ The assembly and centerpiece are shown in }(h+ The assembly and centerpiece are shown in h jhhh!NhNubh_)}(h:numref:`fig2-2-3`h]j)}(hjh]h/fig2-2-3}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjfig2-2-3uhh^h!jIhMWh jubh/XZ,
which is Fig. 4 from Ref. 1. The eight units consist of an approximate
parallelepiped with an irregular top, a parallelepiped, and
six cylinders of various sizes. The centerpiece, which penetrates the
hole in the diaphragm, consists of a cylinder topped by a parallelepiped
topped by a hemisphere. The diaphragm is not modeled in this example.}(hXZ,
which is Fig. 4 from Ref. 1. The eight units consist of an approximate
parallelepiped with an irregular top, a parallelepiped, and
six cylinders of various sizes. The centerpiece, which penetrates the
hole in the diaphragm, consists of a cylinder topped by a parallelepiped
topped by a hemisphere. The diaphragm is not modeled in this example.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMWh jhhubh)}(h
.. _fig2-2-3:h]h}(h]h]h]h]h]hfig2-2-3uhh
hMh jhhh!jIubj)}(hhh](j)}(h`.. figure:: figs/CSAS6/fig3.png
:align: center
:width: 400
Grotesque experimental setup.
h]h}(h]h]h]h]h]width400urifigs/CSAS6/fig3.pngj}jjRsuhjh jBh!jIhMfubj)}(hGrotesque experimental setup.h]h/Grotesque experimental setup.}(hjVh jTubah}(h]h]h]h]h]uhjh!jIhMfh jBubeh}(h](id81jAeh]h]fig2-2-3ah]h]jcenteruhjhMfh jhhh!jIj}jgj7sj}jAj7subj)}(hX=csas6
sample problem 7 keno-vi grotesque w/o diaphragm, ornl/csd/tm-220
v7-238
read comp
uranium 1 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 2 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 3 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 4 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 5 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 6 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 7 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 8 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 9 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 10 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 11 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 12 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 13 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 14 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
end comp
read param
pgm=yes plt=yes
end param
read geom
global unit 1
'*** one through three is item 1 in drawing 84-10649 ornl/csd/tm-220 ***
'one top piece of item 1
cuboid 10 2p6.3515 1.2685 -3.8115 13.377 13.058 origin y=-17.464 z=0.15 rotate a2=-1.35
'two middle piece of item 1
cuboid 20 2p6.3515 6.3515 -3.8115 13.058 11.155 origin y=-17.464 z=0.15 rotate a2=-1.35
'three bottom piece of item 1
cuboid 30 4p6.3515 11.155 0. origin y=-17.464 z=0.15 rotate a2=-1.35
'*** four is item 2 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 40 4.555 12.918 0. origin x=-12.176 y=-9.343 z=0.111 rotate a1=-52.5 a2=-1.400
'*** five is item 3 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 50 5.761 13.475 0. origin x=-16.333 y=1.681 z=0.174 rotate a1=83.5 a2=+1.173
'*** six is item 4 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 60 4.5525 12.969 0. origin x=-9.539 y=11.168 z=0.156 rotate a1=40.5 a2=+1.970
'*** seven and eight are item 5 in drawing 84-10649 ornl/csd/tm-220 ***
'seven
cuboid 70 2p3.81 8.13 -4.573 8.91 0. origin y=15.698 z=0.290 rotate a2=+2.58
'eight
cylinder 80 4.573 13.229 8.91 origin y=15.698 z=0.290 rotate a2=+2.58
'*** nine is item 6 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 90 4.5545 12.974 0. origin x=9.854 y=10.964 z=0.134 rotate a1=-42.0 a2=+1.680
'*** ten is item 7 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 100 5.7495 13.475 0. origin x=16.388 y=1.434 z=0.140 rotate a1=-86.0 a2=+1.400
'*** eleven is item 8 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 110 4.5565 12.954 0. origin x=12.029 y=-9.398 z=0.087 rotate a1=38.0 a2=-1.100
'*12 through 14 is the centerpiece in drawing 84-10649 ornl/csd/tm-220
'twelve
cylinder 120 5.757 2.690 0. origin x=-0.593 y=-0.593 z=-1.753
'thirteen
cuboid 130 4p6.35 5.718 0. origin z=0.937
'fourteen
sphere 140 6.082 chord +z=0. origin x=-0.268 y=0.268 z=6.655
'*** fifteen is the system boundary ***
'fifteen
cuboid 150 4p25.0 15.0 -2.0
media 1 1 +10 vol=20.58546556
media 2 1 +20 -10 vol=245.678420867
media 3 1 +30 -20 vol=1800.040061395
media 4 1 +40 vol=842.019046637
media 5 1 +50 vol=1404.99376489
media 6 1 +60 vol=844.415646269
media 7 1 +70 vol=862.4600226
media 8 1 +80 -70 vol=283.749744681
media 9 1 +90 vol=845.483582679
media 10 1 +100 vol=1399.390119093
media 11 1 +110 vol=844.921798001
media 12 1 +120 -130 vol=280.088070346
media 13 1 +130 vol=922.25622
media 14 1 +140 -130 vol=471.191948666
media 0 1 150 -10 -20 -30 -40 -50 -60 -70 -80 -90 -100
-110 -120 -130 -140 vol=31432.726088316
boundary 150
end geom
read plot
scr=yes lpi=10
clr= 1 255 0 0
2 0 0 205
3 0 229 238
4 0 238 0
5 205 205 0
6 255 121 121
7 145 44 238
8 150 150 150
9 240 200 220
10 0 191 255
11 224 255 255
12 0 128 64
13 255 202 149
14 255 0 128
end color
ttl='grotesque x-y slice at z=0.5'
xul=-25.5 yul= 25.5 zul=0.5
xlr= 25.5 ylr=-25.5 zlr=.5
uax=1 vdn=-1 nax=800 end
ttl='grotesque x-y slice at z=2.0'
xul=-25.5 yul= 25.5 zul=2
xlr= 25.5 ylr=-25.5 zlr=2 end
ttl='grotesque x-y slice at z=9.5'
xul=-25.5 yul= 25.5 zul=9.5
xlr= 25.5 ylr=-25.5 zlr=9.5 end
ttl='grotesque y-z slice at x=-0.593'
xul=-.593 yul=-25.5 zul=15.5
xlr=-.593 ylr= 25.5 zlr=-3.5
uax=0 vax=1
vdn=0 wdn=-1 nax=800 end
ttl='grotesque x-z slice at y=0.0'
xul=-25.5 yul=0.0 zul=15.5
xlr= 25.5 ylr=0.0 zlr=-3.5
uax=1 vax=0 wax=0
udn=0 vdn=0 wdn=-1 nax=800 end
ttl='grotesque x-z slice at y=12.125'
xul=-25.5 yul=12.125 zul=15.5
xlr= 25.5 ylr=12.125 zlr=-3.5
uax=1 vax=0 wax=0
udn=0 vdn=0 wdn=-1 nax=800 end
ttl='grotesque x-z slice at y=-12.000'
xul=-25.5 yul=-12.000 zul=15.5
xlr= 25.5 ylr=-12.000 zlr=-3.5
uax=1 vax=0 wax=0
udn=0 vdn=0 wdn=-1 nax=800 end
end plot
end data
endh]h/X=csas6
sample problem 7 keno-vi grotesque w/o diaphragm, ornl/csd/tm-220
v7-238
read comp
uranium 1 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 2 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 3 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 4 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 5 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 6 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 7 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 8 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 9 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 10 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 11 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 12 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 13 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
uranium 14 den=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 end
end comp
read param
pgm=yes plt=yes
end param
read geom
global unit 1
'*** one through three is item 1 in drawing 84-10649 ornl/csd/tm-220 ***
'one top piece of item 1
cuboid 10 2p6.3515 1.2685 -3.8115 13.377 13.058 origin y=-17.464 z=0.15 rotate a2=-1.35
'two middle piece of item 1
cuboid 20 2p6.3515 6.3515 -3.8115 13.058 11.155 origin y=-17.464 z=0.15 rotate a2=-1.35
'three bottom piece of item 1
cuboid 30 4p6.3515 11.155 0. origin y=-17.464 z=0.15 rotate a2=-1.35
'*** four is item 2 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 40 4.555 12.918 0. origin x=-12.176 y=-9.343 z=0.111 rotate a1=-52.5 a2=-1.400
'*** five is item 3 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 50 5.761 13.475 0. origin x=-16.333 y=1.681 z=0.174 rotate a1=83.5 a2=+1.173
'*** six is item 4 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 60 4.5525 12.969 0. origin x=-9.539 y=11.168 z=0.156 rotate a1=40.5 a2=+1.970
'*** seven and eight are item 5 in drawing 84-10649 ornl/csd/tm-220 ***
'seven
cuboid 70 2p3.81 8.13 -4.573 8.91 0. origin y=15.698 z=0.290 rotate a2=+2.58
'eight
cylinder 80 4.573 13.229 8.91 origin y=15.698 z=0.290 rotate a2=+2.58
'*** nine is item 6 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 90 4.5545 12.974 0. origin x=9.854 y=10.964 z=0.134 rotate a1=-42.0 a2=+1.680
'*** ten is item 7 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 100 5.7495 13.475 0. origin x=16.388 y=1.434 z=0.140 rotate a1=-86.0 a2=+1.400
'*** eleven is item 8 in drawing 84-10649 ornl/csd/tm-220 ***
cylinder 110 4.5565 12.954 0. origin x=12.029 y=-9.398 z=0.087 rotate a1=38.0 a2=-1.100
'*12 through 14 is the centerpiece in drawing 84-10649 ornl/csd/tm-220
'twelve
cylinder 120 5.757 2.690 0. origin x=-0.593 y=-0.593 z=-1.753
'thirteen
cuboid 130 4p6.35 5.718 0. origin z=0.937
'fourteen
sphere 140 6.082 chord +z=0. origin x=-0.268 y=0.268 z=6.655
'*** fifteen is the system boundary ***
'fifteen
cuboid 150 4p25.0 15.0 -2.0
media 1 1 +10 vol=20.58546556
media 2 1 +20 -10 vol=245.678420867
media 3 1 +30 -20 vol=1800.040061395
media 4 1 +40 vol=842.019046637
media 5 1 +50 vol=1404.99376489
media 6 1 +60 vol=844.415646269
media 7 1 +70 vol=862.4600226
media 8 1 +80 -70 vol=283.749744681
media 9 1 +90 vol=845.483582679
media 10 1 +100 vol=1399.390119093
media 11 1 +110 vol=844.921798001
media 12 1 +120 -130 vol=280.088070346
media 13 1 +130 vol=922.25622
media 14 1 +140 -130 vol=471.191948666
media 0 1 150 -10 -20 -30 -40 -50 -60 -70 -80 -90 -100
-110 -120 -130 -140 vol=31432.726088316
boundary 150
end geom
read plot
scr=yes lpi=10
clr= 1 255 0 0
2 0 0 205
3 0 229 238
4 0 238 0
5 205 205 0
6 255 121 121
7 145 44 238
8 150 150 150
9 240 200 220
10 0 191 255
11 224 255 255
12 0 128 64
13 255 202 149
14 255 0 128
end color
ttl='grotesque x-y slice at z=0.5'
xul=-25.5 yul= 25.5 zul=0.5
xlr= 25.5 ylr=-25.5 zlr=.5
uax=1 vdn=-1 nax=800 end
ttl='grotesque x-y slice at z=2.0'
xul=-25.5 yul= 25.5 zul=2
xlr= 25.5 ylr=-25.5 zlr=2 end
ttl='grotesque x-y slice at z=9.5'
xul=-25.5 yul= 25.5 zul=9.5
xlr= 25.5 ylr=-25.5 zlr=9.5 end
ttl='grotesque y-z slice at x=-0.593'
xul=-.593 yul=-25.5 zul=15.5
xlr=-.593 ylr= 25.5 zlr=-3.5
uax=0 vax=1
vdn=0 wdn=-1 nax=800 end
ttl='grotesque x-z slice at y=0.0'
xul=-25.5 yul=0.0 zul=15.5
xlr= 25.5 ylr=0.0 zlr=-3.5
uax=1 vax=0 wax=0
udn=0 vdn=0 wdn=-1 nax=800 end
ttl='grotesque x-z slice at y=12.125'
xul=-25.5 yul=12.125 zul=15.5
xlr= 25.5 ylr=12.125 zlr=-3.5
uax=1 vax=0 wax=0
udn=0 vdn=0 wdn=-1 nax=800 end
ttl='grotesque x-z slice at y=-12.000'
xul=-25.5 yul=-12.000 zul=15.5
xlr= 25.5 ylr=-12.000 zlr=-3.5
uax=1 vax=0 wax=0
udn=0 vdn=0 wdn=-1 nax=800 end
end plot
end data
end}(hhh jmubah}(h]h]h]h]h]jjuhjh!jIhMjh jhhubeh}(h]0sample-problem-7-grotesque-without-the-diaphragmah]h]1sample problem 7: grotesque without the diaphragmah]h]uhh#h jRhhh!jIhMUubh$)}(hhh](h))}(h9Sample Problem 8 Infinite Array of MOX and UO2 Assembliesh]h/9Sample Problem 8 Infinite Array of MOX and UO2 Assemblies}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jIhMubh;)}(hXcThe purpose of this problem is to calculate the *k\ eff* of a system
composed of an infinite array of MOX assemblies interspersed between
UO\ :sub:`2` assemblies. Both assembly types contain 331 pins in a
hexagonal lattice with a pin pitch of 1.275 cm and an assembly pitch
of 23.60 cm as shown in
:numref:`fig2-2-4`. The moderator is borated water at 306°C having a density
of 0.71533 gm/cc and composed of 99.94 wt % H\ :sub:`2`\ O and
0.06 wt % natural boron. Each fuel rod is 355 cm in length, has a
radius of 0.3860 cm, 0.722-cm-thick Zr cladding with no gap, and is at
a temperature of 754°C.h](h/0The purpose of this problem is to calculate the }(h0The purpose of this problem is to calculate the h jhhh!NhNubh)}(h*k\ eff*h]h/k eff}(hhh jubah}(h]h]h]h]h]uhhh jubh/W of a system
composed of an infinite array of MOX assemblies interspersed between
UO }(hW of a system
composed of an infinite array of MOX assemblies interspersed between
UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ assemblies. Both assembly types contain 331 pins in a
hexagonal lattice with a pin pitch of 1.275 cm and an assembly pitch
of 23.60 cm as shown in
}(h assemblies. Both assembly types contain 331 pins in a
hexagonal lattice with a pin pitch of 1.275 cm and an assembly pitch
of 23.60 cm as shown in
h jhhh!NhNubh_)}(h:numref:`fig2-2-4`h]j)}(hjŖh]h/fig2-2-4}(hhh jǖubah}(h]h](jstd
std-numrefeh]h]h]uhjh jÖubah}(h]h]h]h]h]refdocj refdomainjіreftypenumrefrefexplicitrefwarnjfig2-2-4uhh^h!jIhMh jubh/n. The moderator is borated water at 306°C having a density
of 0.71533 gm/cc and composed of 99.94 wt % H }(hn. The moderator is borated water at 306°C having a density
of 0.71533 gm/cc and composed of 99.94 wt % H\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ O and
0.06 wt % natural boron. Each fuel rod is 355 cm in length, has a
radius of 0.3860 cm, 0.722-cm-thick Zr cladding with no gap, and is at
a temperature of 754°C.}(h\ O and
0.06 wt % natural boron. Each fuel rod is 355 cm in length, has a
radius of 0.3860 cm, 0.722-cm-thick Zr cladding with no gap, and is at
a temperature of 754°C.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jhhubh;)}(hThe UO\ :sub:`2` fuel consists of 4.4 wt % :sup:`235`\ U and 95.6 wt %
:sup:`238`\ U at a density of 8.7922 gm/cc. The UO\ :sub:`2` fuel also
contains 9.4581E–9 atoms/b-cm of :sup:`135`\ Xe and 7.3667E–8 atoms/b-cm
of :sup:`149`\ Sm.h](h/The UO }(hThe UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j
ubah}(h]h]h]h]h]uhjh jubh/ fuel consists of 4.4 wt % }(h fuel consists of 4.4 wt % h jhhh!NhNubj)}(h
:sup:`235`h]h/235}(hhh jubah}(h]h]h]h]h]uhjh jubh/ U and 95.6 wt %
}(h\ U and 95.6 wt %
h jhhh!NhNubj)}(h
:sup:`238`h]h/238}(hhh j0ubah}(h]h]h]h]h]uhjh jubh/+ U at a density of 8.7922 gm/cc. The UO }(h+\ U at a density of 8.7922 gm/cc. The UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jCubah}(h]h]h]h]h]uhjh jubh/. fuel also
contains 9.4581E–9 atoms/b-cm of }(h. fuel also
contains 9.4581E–9 atoms/b-cm of h jhhh!NhNubj)}(h
:sup:`135`h]h/135}(hhh jVubah}(h]h]h]h]h]uhjh jubh/# Xe and 7.3667E–8 atoms/b-cm
of }(h#\ Xe and 7.3667E–8 atoms/b-cm
of h jhhh!NhNubj)}(h
:sup:`149`h]h/149}(hhh jiubah}(h]h]h]h]h]uhjh jubh/ Sm.}(h\ Sm.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jhhubh;)}(hXThe MOX fuel consists of 96.38 wt % UO\ :sub:`2` and
3.62 wt % PuO\ :sub:`2` at a density of 8.8182 gm/cc. The UO\ :sub:`2`
fuel is composed of 2.0 wt % \ :sup:`235`\ U and
98.0 wt % \ :sup:`238`\ U. The PuO\ :sub:`2` fuel is composed of
93.0 wt % :sup:`239`\ Pu, 6.0 wt % \ :sup:`240`\ Pu- and
1.0 wt % \ :sup:`241`\ Pu. The MOX fuel also contains 9.4581E–9
atoms/b-cm of :sup:`135`\ Xe and 7.3667E–8 atoms/b-cm of :sup:`149`\ Sm.h](h/+The MOX fuel consists of 96.38 wt % UO }(h+The MOX fuel consists of 96.38 wt % UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ and
3.62 wt % PuO }(h and
3.62 wt % PuO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/( at a density of 8.8182 gm/cc. The UO }(h( at a density of 8.8182 gm/cc. The UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/#
fuel is composed of 2.0 wt % }(h#
fuel is composed of 2.0 wt % \ h jhhh!NhNubj)}(h
:sup:`235`h]h/235}(hhh jėubah}(h]h]h]h]h]uhjh jubh/ U and
98.0 wt % }(h\ U and
98.0 wt % \ h jhhh!NhNubj)}(h
:sup:`238`h]h/238}(hhh jחubah}(h]h]h]h]h]uhjh jubh/ U. The PuO }(h\ U. The PuO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/! fuel is composed of
93.0 wt % }(h! fuel is composed of
93.0 wt % h jhhh!NhNubj)}(h
:sup:`239`h]h/239}(hhh jubah}(h]h]h]h]h]uhjh jubh/ Pu, 6.0 wt % }(h\ Pu, 6.0 wt % \ h jhhh!NhNubj)}(h
:sup:`240`h]h/240}(hhh jubah}(h]h]h]h]h]uhjh jubh/ Pu- and
1.0 wt % }(h\ Pu- and
1.0 wt % \ h jhhh!NhNubj)}(h
:sup:`241`h]h/241}(hhh j#ubah}(h]h]h]h]h]uhjh jubh/; Pu. The MOX fuel also contains 9.4581E–9
atoms/b-cm of }(h;\ Pu. The MOX fuel also contains 9.4581E–9
atoms/b-cm of h jhhh!NhNubj)}(h
:sup:`135`h]h/135}(hhh j6ubah}(h]h]h]h]h]uhjh jubh/$ Xe and 7.3667E–8 atoms/b-cm of }(h$\ Xe and 7.3667E–8 atoms/b-cm of h jhhh!NhNubj)}(h
:sup:`149`h]h/149}(hhh jIubah}(h]h]h]h]h]uhjh jubh/ Sm.}(h\ Sm.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jhhubh;)}(hXThese two assemblies are placed so they represent an infinite array in
the X and Y dimensions as shown in :numref:`fig2-2-5`. There is 20 cm of water
above and below fuel assemblies. This problem uses CENTRM/PMC as the
resolved resonance processor cross section. Since an infinite array
cannot be explicitly modeled, a section of the array is modeled and the
X and Y sides have mirror reflection.h](h/kThese two assemblies are placed so they represent an infinite array in
the X and Y dimensions as shown in }(hkThese two assemblies are placed so they represent an infinite array in
the X and Y dimensions as shown in h jbhhh!NhNubh_)}(h:numref:`fig2-2-5`h]j)}(hjmh]h/fig2-2-5}(hhh joubah}(h]h](jstd
std-numrefeh]h]h]uhjh jkubah}(h]h]h]h]h]refdocj refdomainjyreftypenumrefrefexplicitrefwarnjfig2-2-5uhh^h!jIhMh jbubh/X. There is 20 cm of water
above and below fuel assemblies. This problem uses CENTRM/PMC as the
resolved resonance processor cross section. Since an infinite array
cannot be explicitly modeled, a section of the array is modeled and the
X and Y sides have mirror reflection.}(hX. There is 20 cm of water
above and below fuel assemblies. This problem uses CENTRM/PMC as the
resolved resonance processor cross section. Since an infinite array
cannot be explicitly modeled, a section of the array is modeled and the
X and Y sides have mirror reflection.h jbhhh!NhNubeh}(h]h]h]h]h]uhh:h!jIhMh jhhubj)}(hX=csas6 parm=(centrm)
sample problem 8 - VVER inf. array - MOX & UO2 Assemblies
v7-238
read comp
' UO2 Fuel
uo2 1 den=8.7922 1.0 1027 92235 4.4 92238 95.6 end
xe-135 1 0 9.4581E-09 1027 end
sm-149 1 0 7.3667E-08 1027 end
' MOX Fuel
uo2 2 den=8.8182 0.9638 1027 92235 2.0 92238 98.0 end
puo2 2 den=8.8182 0.0362 1027 94239 93.0 94240 6.0 94241 1.0 end
xe-135 2 0 9.4581E-09 1027 end
sm-149 2 0 7.3667E-08 1027 end
' Cladding for UO2 fuel
zr 3 den=6.4073 1.0 579 end
' Moderator for UO2 fuel
h2o 4 den=0.71533 0.9994 579 end
boron 4 den=0.71533 0.0006 579 end
' Cladding for MOX fuel
zr 5 den=6.4073 1.0 579 end
' Moderator for MOX fuel
h2o 6 den=0.71533 0.9994 579 end
boron 6 den=0.71533 0.0006 579 end
' Moderator for vacant units
h2o 7 den=0.71533 0.9994 579 end
boron 7 den=0.71533 0.0006 579 end
end comp
read celldata
latticecell triangpitch pitch=1.2750 4 fueld=0.7720 1 cladd=0.9164 3 end
latticecell triangpitch pitch=1.2750 6 fueld=0.7720 2 cladd=0.9164 5 end
' more data dab=500 end more
end celldata
read param
gen=203 npg=1000
end param
read bounds
all=mirror zfc=void
end bounds
read geom
unit 1
com='UO2 Fuel Rod'
cylinder 10 0.3860 355.0 0.0
cylinder 20 0.4582 355.0 0.0
hexprism 30 0.6375 355.0 0.0
media 1 1 10
media 3 1 20 -10
media 4 1 30 -20
boundary 30
unit 2
com='Vacant(water filled) hex'
hexprism 10 0.6375 355.0 0.0
media 7 1 10
boundary 10
unit 3
com='Vacant(water filled) hex'
hexprism 10 0.6375 355.0 0.0
media 7 1 10
boundary 10
unit 4
com='MOX Fuel Rod'
cylinder 10 0.3860 355.0 0.0
cylinder 20 0.4582 355.0 0.0
hexprism 30 0.6375 355.0 0.0
media 2 1 10
media 5 1 20 -10
media 6 1 30 -20
boundary 30
global unit 5
rhexprism 10 11.800 355.0 0.0
rhexprism 20 11.800 355.0 0.0 origin y=23.6
rhexprism 30 11.800 355.0 0.0 origin x=20.4382 y=11.8
rhexprism 40 11.800 355.0 0.0 origin x=20.4382 y=35.4
cuboid 50 20.4382 0.0 35.4 0.0 375.0 -20.0
array 1 10 -20 -30 -40 place 12 12 1 0.0 0.0 0.0
array 2 20 -10 -30 -40 place 12 12 1 0.0 23.6 0.0
array 2 30 -10 -20 -40 place 12 12 1 20.4382 11.8 0.0
array 1 40 -10 -20 -30 place 12 12 1 20.4382 35.4 0.0
media 4 1 50 -10 -20 -30 -40
boundary 50
end geom
read array
ara=1 typ=shexagonal nux=23 nuy=23 nuz=1
fill
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3
3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
end fill
ara=2 typ=shexagonal nux=23 nuy=23 nuz=1
fill
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2
2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
end fill
end array
read plot
lpi=10 scr=yes
ttl='VVER assembly x-y x-section'
xul=-0.1 yul=35.5 zul=10
xlr=20.6 ylr=-0.1 zlr=10
uax=1 vdn=-1.0
nax=640 pic=mat end plt1
end plot
read volume
type=random batches=1000
end volume
end data
endh]h/X=csas6 parm=(centrm)
sample problem 8 - VVER inf. array - MOX & UO2 Assemblies
v7-238
read comp
' UO2 Fuel
uo2 1 den=8.7922 1.0 1027 92235 4.4 92238 95.6 end
xe-135 1 0 9.4581E-09 1027 end
sm-149 1 0 7.3667E-08 1027 end
' MOX Fuel
uo2 2 den=8.8182 0.9638 1027 92235 2.0 92238 98.0 end
puo2 2 den=8.8182 0.0362 1027 94239 93.0 94240 6.0 94241 1.0 end
xe-135 2 0 9.4581E-09 1027 end
sm-149 2 0 7.3667E-08 1027 end
' Cladding for UO2 fuel
zr 3 den=6.4073 1.0 579 end
' Moderator for UO2 fuel
h2o 4 den=0.71533 0.9994 579 end
boron 4 den=0.71533 0.0006 579 end
' Cladding for MOX fuel
zr 5 den=6.4073 1.0 579 end
' Moderator for MOX fuel
h2o 6 den=0.71533 0.9994 579 end
boron 6 den=0.71533 0.0006 579 end
' Moderator for vacant units
h2o 7 den=0.71533 0.9994 579 end
boron 7 den=0.71533 0.0006 579 end
end comp
read celldata
latticecell triangpitch pitch=1.2750 4 fueld=0.7720 1 cladd=0.9164 3 end
latticecell triangpitch pitch=1.2750 6 fueld=0.7720 2 cladd=0.9164 5 end
' more data dab=500 end more
end celldata
read param
gen=203 npg=1000
end param
read bounds
all=mirror zfc=void
end bounds
read geom
unit 1
com='UO2 Fuel Rod'
cylinder 10 0.3860 355.0 0.0
cylinder 20 0.4582 355.0 0.0
hexprism 30 0.6375 355.0 0.0
media 1 1 10
media 3 1 20 -10
media 4 1 30 -20
boundary 30
unit 2
com='Vacant(water filled) hex'
hexprism 10 0.6375 355.0 0.0
media 7 1 10
boundary 10
unit 3
com='Vacant(water filled) hex'
hexprism 10 0.6375 355.0 0.0
media 7 1 10
boundary 10
unit 4
com='MOX Fuel Rod'
cylinder 10 0.3860 355.0 0.0
cylinder 20 0.4582 355.0 0.0
hexprism 30 0.6375 355.0 0.0
media 2 1 10
media 5 1 20 -10
media 6 1 30 -20
boundary 30
global unit 5
rhexprism 10 11.800 355.0 0.0
rhexprism 20 11.800 355.0 0.0 origin y=23.6
rhexprism 30 11.800 355.0 0.0 origin x=20.4382 y=11.8
rhexprism 40 11.800 355.0 0.0 origin x=20.4382 y=35.4
cuboid 50 20.4382 0.0 35.4 0.0 375.0 -20.0
array 1 10 -20 -30 -40 place 12 12 1 0.0 0.0 0.0
array 2 20 -10 -30 -40 place 12 12 1 0.0 23.6 0.0
array 2 30 -10 -20 -40 place 12 12 1 20.4382 11.8 0.0
array 1 40 -10 -20 -30 place 12 12 1 20.4382 35.4 0.0
media 4 1 50 -10 -20 -30 -40
boundary 50
end geom
read array
ara=1 typ=shexagonal nux=23 nuy=23 nuz=1
fill
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3
3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3
3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3
3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3
3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3
3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3
3 3 3 3 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
end fill
ara=2 typ=shexagonal nux=23 nuy=23 nuz=1
fill
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2
2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2
2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2
2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2
2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2
2 2 2 2 2 2 1 1 1 1 1 1 1 1 1 1 1 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
end fill
end array
read plot
lpi=10 scr=yes
ttl='VVER assembly x-y x-section'
xul=-0.1 yul=35.5 zul=10
xlr=20.6 ylr=-0.1 zlr=10
uax=1 vdn=-1.0
nax=640 pic=mat end plt1
end plot
read volume
type=random batches=1000
end volume
end data
end}(hhh jubah}(h]h]h]h]h]jjuhjh!jIhM
h jhhubh)}(h
.. _fig2-2-4:h]h}(h]h]h]h]h]hfig2-2-4uhh
hMFh jhhh!jIubj)}(hhh](j)}(hj.. figure:: figs/CSAS6/fig4.png
:align: center
:width: 400
MOX or UO\ :sub:`2` hexagonal assembly.
h]h}(h]h]h]h]h]width400urifigs/CSAS6/fig4.pngj}jjsuhjh jh!jIhMubj)}(h'MOX or UO\ :sub:`2` hexagonal assembly.h](h/MOX or UO }(hMOX or UO\ h jubj)}(h:sub:`2`h]h/2}(hhh jʘubah}(h]h]h]h]h]uhjh jubh/ hexagonal assembly.}(h hexagonal assembly.h jubeh}(h]h]h]h]h]uhjh!jIhMh jubeh}(h](id82jeh]h]fig2-2-4ah]h]jcenteruhjhMh jhhh!jIj}jjsj}jjsubh)}(h
.. _fig2-2-5:h]h}(h]h]h]h]h]hfig2-2-5uhh
hMMh jhhh!jIubj)}(hhh](j)}(h.. figure:: figs/CSAS6/fig5.png
:align: center
:width: 400
Infinite array of MOX assemblies interspersed between UO\ :sub:`2` assemblies.
h]h}(h]h]h]h]h]width400urifigs/CSAS6/fig5.pngj}jj suhjh jh!jIhMubj)}(hNInfinite array of MOX assemblies interspersed between UO\ :sub:`2` assemblies.h](h/:Infinite array of MOX assemblies interspersed between UO }(h:Infinite array of MOX assemblies interspersed between UO\ h jubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ assemblies.}(h assemblies.h jubeh}(h]h]h]h]h]uhjh!jIhMh jubeh}(h](id83jeh]h]fig2-2-5ah]h]jcenteruhjhMh jhhh!jIj}j2jsj}jjsubeh}(h]9sample-problem-8-infinite-array-of-mox-and-uo2-assembliesah]h]9sample problem 8 infinite array of mox and uo2 assembliesah]h]uhh#h jRhhh!jIhMubeh}(h]sample-problemsah]h]h]jRah]uhh#h j8hhh!jIhMjmKubh$)}(hhh](h))}(hWarning and Error Messagesh]h/Warning and Error Messages}(hjLh jJhhh!NhNubah}(h]h]h]h]h]uhh(h jGhhh!jIhMubh;)}(hXCSAS6 contains two types of warning and error messages. The first type
of message is from XSProc is common to many of the SCALE analytical
sequences. The second type of message is from the CSAS6 subroutines and
is identified by CS- followed by a number. These messages are listed in
numerical order below. For additional information concerning a
message, simply look up the number in this section.h]h/XCSAS6 contains two types of warning and error messages. The first type
of message is from XSProc is common to many of the SCALE analytical
sequences. The second type of message is from the CSAS6 subroutines and
is identified by CS- followed by a number. These messages are listed in
numerical order below. For additional information concerning a
message, simply look up the number in this section.}(hjZh jXhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jGhhubh;)}(hX3Warning messages appear when a possible error is encountered. It is the
responsibility of the user to verify whether the data are correct when a
warning message is encountered. The functional modules activated by
CSAS6 and related sequences will be executed even though a warning
message has been generated.h]h/X3Warning messages appear when a possible error is encountered. It is the
responsibility of the user to verify whether the data are correct when a
warning message is encountered. The functional modules activated by
CSAS6 and related sequences will be executed even though a warning
message has been generated.}(hjhh jfhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jGhhubh;)}(hXWhen an error is recognized, an error message is written and an error
flag is set so the functional modules will not be activated. The code
stops immediately if the error is too severe to allow continuation of
input. However, it will continue to read and check the data if it is
able. When the data reading is completed, execution is terminated if an
error flag was set when the data were being processed. If the error flag
has not been set, execution continues. When error messages are printed,
the user should focus on the first error message, because subsequent
messages may have been caused by the error that generated the first
message.h]h/XWhen an error is recognized, an error message is written and an error
flag is set so the functional modules will not be activated. The code
stops immediately if the error is too severe to allow continuation of
input. However, it will continue to read and check the data if it is
able. When the data reading is completed, execution is terminated if an
error flag was set when the data were being processed. If the error flag
has not been set, execution continues. When error messages are printed,
the user should focus on the first error message, because subsequent
messages may have been caused by the error that generated the first
message.}(hjvh jthhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jGhhubh;)}(hXyThe following messages originate in the part of CSAS6 that reads,
checks, and prepares data for KENO‑VI. The same set of error messages
are also used for CSAS5 that reads, checks, and prepares data for
KENO V.a and MODIFY. CSAS6 is not capable of performing searches at this
time. An error message referring to a SEARCH routine, from a CSAS6
problem, indicates a code error.h]h/XyThe following messages originate in the part of CSAS6 that reads,
checks, and prepares data for KENO‑VI. The same set of error messages
are also used for CSAS5 that reads, checks, and prepares data for
KENO V.a and MODIFY. CSAS6 is not capable of performing searches at this
time. An error message referring to a SEARCH routine, from a CSAS6
problem, indicates a code error.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jIhMh jGhhubjl)}(hhh](jl)}(hXCS-16 \***WARNING**\* READ FLAG NOT FOUND. ASSUME KENO V PARAMETER DATA FOLLOWS.
This message from subroutine CPARAM indicates that the word READ is not
the first word of KENO-VI data following the Material Information
Processor input data. If parameter data is to be entered, the code
expects the words READ PARAMETERS to precede the parameter input data.
If the word READ is not the first word, the code assumes the data are
parameter input data.
h](jl)}(hPCS-16 \***WARNING**\* READ FLAG NOT FOUND. ASSUME KENO V PARAMETER DATA FOLLOWS.h]h/PCS-16 ***WARNING*** READ FLAG NOT FOUND. ASSUME KENO V PARAMETER DATA FOLLOWS.}(hPCS-16 \***WARNING**\* READ FLAG NOT FOUND. ASSUME KENO V PARAMETER DATA FOLLOWS.h jubah}(h]h]h]h]h]uhjlh!jIhMh jubjl)}(hhh]h;)}(hXoThis message from subroutine CPARAM indicates that the word READ is not
the first word of KENO-VI data following the Material Information
Processor input data. If parameter data is to be entered, the code
expects the words READ PARAMETERS to precede the parameter input data.
If the word READ is not the first word, the code assumes the data are
parameter input data.h]h/XoThis message from subroutine CPARAM indicates that the word READ is not
the first word of KENO-VI data following the Material Information
Processor input data. If parameter data is to be entered, the code
expects the words READ PARAMETERS to precede the parameter input data.
If the word READ is not the first word, the code assumes the data are
parameter input data.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!jIhMh jubjl)}(hXCS-21 A UNIT NUMBER WAS ENTERED FOR THE CROSS-SECTION LIBRARY. (LIB= IN PARAMETER DATA.) THE DEFAULT VALUE SHOULD BE USED IN ORDER TO UTILIZE THE CROSS SECTIONS GENERATED BY CSAS. MAKE CERTAIN THE CORRECT CROSS-SECTION LIBRARY IS BEING USED.
This message is from subroutine CPARAM. It indicates that a value has
been entered for the cross-section library in the KENO-VI parameter
data. The cross-section library created by the analytical sequence
should be used. MAKE CERTAIN THAT THE CORRECT CROSS SECTIONS ARE BEING
USED.
h](jl)}(hCS-21 A UNIT NUMBER WAS ENTERED FOR THE CROSS-SECTION LIBRARY. (LIB= IN PARAMETER DATA.) THE DEFAULT VALUE SHOULD BE USED IN ORDER TO UTILIZE THE CROSS SECTIONS GENERATED BY CSAS. MAKE CERTAIN THE CORRECT CROSS-SECTION LIBRARY IS BEING USED.h]h/CS-21 A UNIT NUMBER WAS ENTERED FOR THE CROSS-SECTION LIBRARY. (LIB= IN PARAMETER DATA.) THE DEFAULT VALUE SHOULD BE USED IN ORDER TO UTILIZE THE CROSS SECTIONS GENERATED BY CSAS. MAKE CERTAIN THE CORRECT CROSS-SECTION LIBRARY IS BEING USED.}(hjəh jǙubah}(h]h]h]h]h]uhjlh!jIhMh jÙubjl)}(hhh]h;)}(hXThis message is from subroutine CPARAM. It indicates that a value has
been entered for the cross-section library in the KENO-VI parameter
data. The cross-section library created by the analytical sequence
should be used. MAKE CERTAIN THAT THE CORRECT CROSS SECTIONS ARE BEING
USED.h]h/XThis message is from subroutine CPARAM. It indicates that a value has
been entered for the cross-section library in the KENO-VI parameter
data. The cross-section library created by the analytical sequence
should be used. MAKE CERTAIN THAT THE CORRECT CROSS SECTIONS ARE BEING
USED.}(hjڙh jؙubah}(h]h]h]h]h]uhh:h!jIhMh jՙubah}(h]h]h]h]h]uhjlh jÙubeh}(h]h]h]h]h]uhjlh!jIhMh jhhubjl)}(hXCS-55 \**\* ERRORS WERE ENCOUNTERED IN PROCESSING THE CSAS-KENO6 DATA. EXECUTION IS IMPOSSIBLE. \**\*
This message from subroutine SASSY is printed if errors were found in
the KENO-VI input data for CSAS. If a search is being made, data reading
will continue until all the data have been entered or a fatal error
terminates the data reading. When the data reading and checking have
been completed, the problem will terminate without executing. Check the
printout to locate the errors responsible for this message.
h](jl)}(heCS-55 \**\* ERRORS WERE ENCOUNTERED IN PROCESSING THE CSAS-KENO6 DATA. EXECUTION IS IMPOSSIBLE. \**\*h]h/eCS-55 *** ERRORS WERE ENCOUNTERED IN PROCESSING THE CSAS-KENO6 DATA. EXECUTION IS IMPOSSIBLE. ***}(heCS-55 \**\* ERRORS WERE ENCOUNTERED IN PROCESSING THE CSAS-KENO6 DATA. EXECUTION IS IMPOSSIBLE. \**\*h jubah}(h]h]h]h]h]uhjlh!jIhMh jubjl)}(hhh]h;)}(hXThis message from subroutine SASSY is printed if errors were found in
the KENO-VI input data for CSAS. If a search is being made, data reading
will continue until all the data have been entered or a fatal error
terminates the data reading. When the data reading and checking have
been completed, the problem will terminate without executing. Check the
printout to locate the errors responsible for this message.h]h/XThis message from subroutine SASSY is printed if errors were found in
the KENO-VI input data for CSAS. If a search is being made, data reading
will continue until all the data have been entered or a fatal error
terminates the data reading. When the data reading and checking have
been completed, the problem will terminate without executing. Check the
printout to locate the errors responsible for this message.}(hj
h jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!jIhMh jhhubjl)}(hXCS-62 \**\* ERROR \**\* MIXTURE \_____\_ IN THE GEOMETRY WAS NOT CREATED IN THE STANDARD COMPOSITIONS SPECIFICATION DATA.
This message from subroutine MIXCHK indicates that a mixture specified
in the KENO-VI geometry was not created in the standard composition
data.
h](jl)}(hyCS-62 \**\* ERROR \**\* MIXTURE \_____\_ IN THE GEOMETRY WAS NOT CREATED IN THE STANDARD COMPOSITIONS SPECIFICATION DATA.h]h/yCS-62 *** ERROR *** MIXTURE ______ IN THE GEOMETRY WAS NOT CREATED IN THE STANDARD COMPOSITIONS SPECIFICATION DATA.}(hyCS-62 \**\* ERROR \**\* MIXTURE \_____\_ IN THE GEOMETRY WAS NOT CREATED IN THE STANDARD COMPOSITIONS SPECIFICATION DATA.h j&ubah}(h]h]h]h]h]uhjlh!jIhMh j"ubjl)}(hhh]h;)}(hThis message from subroutine MIXCHK indicates that a mixture specified
in the KENO-VI geometry was not created in the standard composition
data.h]h/This message from subroutine MIXCHK indicates that a mixture specified
in the KENO-VI geometry was not created in the standard composition
data.}(hj:h j8ubah}(h]h]h]h]h]uhh:h!jIhMh j5ubah}(h]h]h]h]h]uhjlh j"ubeh}(h]h]h]h]h]uhjlh!jIhMh jhhubjl)}(hXCS-68 \**\* ERROR \**\* AN INPUT DATA ERROR HAS BEEN ENCOUNTERED IN THE DATA ENTERED FOR THIS PROBLEM.
This message from the main program, CSAS6, is printed if the subroutine
library routine LRDERR returns a value of “TRUE,” indicating that a
reading error has been encountered in the “KENO PARAMETER” data. The
appropriate data type is printed in the message. Locate the unnumbered
message stating “****\* ERROR IN INPUT. CARD IMAGE PRINTED ON NEXT LINE
\*****.” Correct the data and resubmit the problem.
h](jl)}(hfCS-68 \**\* ERROR \**\* AN INPUT DATA ERROR HAS BEEN ENCOUNTERED IN THE DATA ENTERED FOR THIS PROBLEM.h]h/fCS-68 *** ERROR *** AN INPUT DATA ERROR HAS BEEN ENCOUNTERED IN THE DATA ENTERED FOR THIS PROBLEM.}(hfCS-68 \**\* ERROR \**\* AN INPUT DATA ERROR HAS BEEN ENCOUNTERED IN THE DATA ENTERED FOR THIS PROBLEM.h jVubah}(h]h]h]h]h]uhjlh!jIhMh jRubjl)}(hhh]h;)}(hXThis message from the main program, CSAS6, is printed if the subroutine
library routine LRDERR returns a value of “TRUE,” indicating that a
reading error has been encountered in the “KENO PARAMETER” data. The
appropriate data type is printed in the message. Locate the unnumbered
message stating “****\* ERROR IN INPUT. CARD IMAGE PRINTED ON NEXT LINE
\*****.” Correct the data and resubmit the problem.h](h/X3This message from the main program, CSAS6, is printed if the subroutine
library routine LRDERR returns a value of “TRUE,” indicating that a
reading error has been encountered in the “KENO PARAMETER” data. The
appropriate data type is printed in the message. Locate the unnumbered
message stating “}(hX3This message from the main program, CSAS6, is printed if the subroutine
library routine LRDERR returns a value of “TRUE,” indicating that a
reading error has been encountered in the “KENO PARAMETER” data. The
appropriate data type is printed in the message. Locate the unnumbered
message stating “h jhubh problematic)}(h**h]h/**}(hhh jsubah}(h]id35ah]h]h]h]refidid34uhjqh jhubhA)}(h;**\* ERROR IN INPUT. CARD IMAGE PRINTED ON NEXT LINE
\*****h]h/7* ERROR IN INPUT. CARD IMAGE PRINTED ON NEXT LINE
***}(hhh jubah}(h]h]h]h]h]uhh@h jhubh//.” Correct the data and resubmit the problem.}(h/.” Correct the data and resubmit the problem.h jhubeh}(h]h]h]h]h]uhh:h!jIhMh jeubah}(h]h]h]h]h]uhjlh jRubeh}(h]h]h]h]h]uhjlh!jIhMh jhhubjl)}(hXMCS-69 \***ERROR**\* MIXTURE \_____\_ IS AN INAPPROPRIATE MIXTURE NUMBER FOR USE IN THE KENO GEOMETRY DATA BECAUSE IT IS A COMPONENT OF THE CELL-WEIGHTED MIXTURE CREATED BY XSDRNPM.
This message from subroutine CMXCHK indicates that a mixture that is a
component of a cell-weighted mixture has been used in the KENO-VI
geometry data.
h](jl)}(hCS-69 \***ERROR**\* MIXTURE \_____\_ IS AN INAPPROPRIATE MIXTURE NUMBER FOR USE IN THE KENO GEOMETRY DATA BECAUSE IT IS A COMPONENT OF THE CELL-WEIGHTED MIXTURE CREATED BY XSDRNPM.h]h/CS-69 ***ERROR*** MIXTURE ______ IS AN INAPPROPRIATE MIXTURE NUMBER FOR USE IN THE KENO GEOMETRY DATA BECAUSE IT IS A COMPONENT OF THE CELL-WEIGHTED MIXTURE CREATED BY XSDRNPM.}(hCS-69 \***ERROR**\* MIXTURE \_____\_ IS AN INAPPROPRIATE MIXTURE NUMBER FOR USE IN THE KENO GEOMETRY DATA BECAUSE IT IS A COMPONENT OF THE CELL-WEIGHTED MIXTURE CREATED BY XSDRNPM.h jubah}(h]h]h]h]h]uhjlh!jIhMh jubjl)}(hhh]h;)}(hThis message from subroutine CMXCHK indicates that a mixture that is a
component of a cell-weighted mixture has been used in the KENO-VI
geometry data.h]h/This message from subroutine CMXCHK indicates that a mixture that is a
component of a cell-weighted mixture has been used in the KENO-VI
geometry data.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!jIhMh jhhubjl)}(hX(CS-82 \**\* AN ERROR WAS ENCOUNTERED IN ONE OF THE FUNCTIONAL MODULES.
This message from CSAS6 indicates that an error was encountered during
execution of one of the functional modules such as CRAWDAD, BONAMI,
CENTRM, PMC, XSDRNPM, or KENO-VI. Check the printout to locate and
correct the error.
h](jl)}(hFCS-82 \**\* AN ERROR WAS ENCOUNTERED IN ONE OF THE FUNCTIONAL MODULES.h]h/FCS-82 *** AN ERROR WAS ENCOUNTERED IN ONE OF THE FUNCTIONAL MODULES.}(hFCS-82 \**\* AN ERROR WAS ENCOUNTERED IN ONE OF THE FUNCTIONAL MODULES.h jݚubah}(h]h]h]h]h]uhjlh!jIhMh jٚubjl)}(hhh]h;)}(hThis message from CSAS6 indicates that an error was encountered during
execution of one of the functional modules such as CRAWDAD, BONAMI,
CENTRM, PMC, XSDRNPM, or KENO-VI. Check the printout to locate and
correct the error.h]h/This message from CSAS6 indicates that an error was encountered during
execution of one of the functional modules such as CRAWDAD, BONAMI,
CENTRM, PMC, XSDRNPM, or KENO-VI. Check the printout to locate and
correct the error.}(hjh jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhjlh jٚubeh}(h]h]h]h]h]uhjlh!jIhMh jhhubjl)}(hXKCS-99 THIS PROBLEM WILL NOT BE RUN BECAUSE PARM=CHECK WAS ENTERED IN THE ANALYTICAL SEQUENCE SPECIFICATION.
This message from subroutine CSAS indicates that the problem data were
read and checked and no errors were found. To execute the problem,
remove the PARM=CHECK or PARM=CHK from the analytical sequence indicator
data entry.
h](jl)}(hkCS-99 THIS PROBLEM WILL NOT BE RUN BECAUSE PARM=CHECK WAS ENTERED IN THE ANALYTICAL SEQUENCE SPECIFICATION.h]h/kCS-99 THIS PROBLEM WILL NOT BE RUN BECAUSE PARM=CHECK WAS ENTERED IN THE ANALYTICAL SEQUENCE SPECIFICATION.}(hjh j
ubah}(h]h]h]h]h]uhjlh!jIhMh j ubjl)}(hhh]h;)}(hThis message from subroutine CSAS indicates that the problem data were
read and checked and no errors were found. To execute the problem,
remove the PARM=CHECK or PARM=CHK from the analytical sequence indicator
data entry.h]h/This message from subroutine CSAS indicates that the problem data were
read and checked and no errors were found. To execute the problem,
remove the PARM=CHECK or PARM=CHK from the analytical sequence indicator
data entry.}(hj h jubah}(h]h]h]h]h]uhh:h!jIhMh jubah}(h]h]h]h]h]uhjlh j ubeh}(h]h]h]h]h]uhjlh!jIhMh jhhubjl)}(hCS-100 THIS PROBLEM WILL NOT BE RUN BECAUSE ERRORS WERE ENCOUNTERED IN THE INPUT DATA.
This message from subroutine CSAS is self-explanatory. Examine the
printout to locate the error or errors in the input data. Correct them
and resubmit the problem.
h](jl)}(hVCS-100 THIS PROBLEM WILL NOT BE RUN BECAUSE ERRORS WERE ENCOUNTERED IN THE INPUT DATA.h]h/VCS-100 THIS PROBLEM WILL NOT BE RUN BECAUSE ERRORS WERE ENCOUNTERED IN THE INPUT DATA.}(hj>h j<ubah}(h]h]h]h]h]uhjlh!jIhM h j8ubjl)}(hhh]h;)}(hThis message from subroutine CSAS is self-explanatory. Examine the
printout to locate the error or errors in the input data. Correct them
and resubmit the problem.h]h/This message from subroutine CSAS is self-explanatory. Examine the
printout to locate the error or errors in the input data. Correct them
and resubmit the problem.}(hjOh jMubah}(h]h]h]h]h]uhh:h!jIhMh jJubah}(h]h]h]h]h]uhjlh j8ubeh}(h]h]h]h]h]uhjlh!jIhM h jhhubeh}(h]h]h]h]h]uhjlh jGhhh!jIhNubh;)}(hhh]j)}(hhh](j#)}(hhh]h/mihalczo_brief_1999}(hhh jsubah}(h]h]h]h]h]j1uhj"h jpubh;)}(hhh](h/J.}(hJ.h jubj<h/T. Mihalczo.}(hT. Mihalczo.h jubh/ }(h h jubh/^Brief summary of unreflected and unmoderated cylindrical critical experiments with oralloy at }(h^Brief summary of unreflected and unmoderated cylindrical critical experiments with oralloy at h jubh/Oak}(hOakh jubh/ }(hjh jubh/Ridge}(hRidgeh jubh/.}(hjh jubj\h/DTechnical Report, Oak Ridge National Lab., Oak Ridge, TN (US), 1999.}(hDTechnical Report, Oak Ridge National Lab., Oak Ridge, TN (US), 1999.h jubeh}(h]h]h]h]h]uhh:h jpubeh}(h]mihalczo-brief-1999ah]hwah]mihalczo_brief_1999ah]h]jajjuhh|h jmjKubah}(h]1bibtex-bibliography-Criticality Safety Overview-2ah]h]h]h]uhh:h jGhhh!NhNubh)}(h
.. _CSAS6App:h]h}(h]h]h]h]h]hcsas6appuhh
hMh jGhhh!jubeh}(h]id33ah]h]h]warning and error messagesah]uhh#h j8hhh!jIhMjmKubh$)}(hhh](h))}(h(Additional Example Applications of CSAS6h]h/(Additional Example Applications of CSAS6}(hjۛh jٛhhh!NhNubah}(h]h]h]h]h]uhh(h j֛hhh!jhKubh;)}(hVSeveral example uses of CSAS6 are shown in this section for a variety of applications.h]h/VSeveral example uses of CSAS6 are shown in this section for a variety of applications.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jhKh j֛hhubh)}(h.. _run-KENO-CSAS6:h]h}(h]h]h]h]h]hrun-keno-csas6uhh
hMh j֛hhh!jubeh}(h]((additional-example-applications-of-csas6j͛eh]h]((additional example applications of csas6csas6appeh]h]uhh#h j8hhh!jhKj}jjÛsj}j͛jÛsubh$)}(hhh](h))}(hRun KENO-VI using CSAS6h]h/Run KENO-VI using CSAS6}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jhKubh;)}(hX%CSAS6 creates a microscopic working format library and a mixing table
that is passed to KENO-VI. The library is created using
CENTRM/PMC/WORKER to process the cross section data in the resolved
resonance regions of the isotopes contained in the library. CSAS6 then
executes KENO-VI, which calculates *k*\ :sub:`eff` for the problem. The
following examples are for using the multigroup mode of calculation for
KENO-VI. Using the continuous energy mode can be accomplished by simply
changing the library name to one of the continuous energy libraries.h](h/X,CSAS6 creates a microscopic working format library and a mixing table
that is passed to KENO-VI. The library is created using
CENTRM/PMC/WORKER to process the cross section data in the resolved
resonance regions of the isotopes contained in the library. CSAS6 then
executes KENO-VI, which calculates }(hX,CSAS6 creates a microscopic working format library and a mixing table
that is passed to KENO-VI. The library is created using
CENTRM/PMC/WORKER to process the cross section data in the resolved
resonance regions of the isotopes contained in the library. CSAS6 then
executes KENO-VI, which calculates h jhhh!NhNubh)}(h*k*h]h/k}(hhh j%ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j8ubah}(h]h]h]h]h]uhjh jubh/ for the problem. The
following examples are for using the multigroup mode of calculation for
KENO-VI. Using the continuous energy mode can be accomplished by simply
changing the library name to one of the continuous energy libraries.}(h for the problem. The
following examples are for using the multigroup mode of calculation for
KENO-VI. Using the continuous energy mode can be accomplished by simply
changing the library name to one of the continuous energy libraries.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhK
h jhhubh;)}(h?EXAMPLE 1. CSAS6 – Determine the *k*\ :sub:`eff` of a system.h](h/#EXAMPLE 1. CSAS6 – Determine the }(h#EXAMPLE 1. CSAS6 – Determine the h jQhhh!NhNubh)}(h*k*h]h/k}(hhh jZubah}(h]h]h]h]h]uhhh jQubh/ }(h\ h jQhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jmubah}(h]h]h]h]h]uhjh jQubh/
of a system.}(h
of a system.h jQhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubh;)}(hX6Consider a problem consisting of eight uranium metal cylinders that are
93.2% wt enriched, having a density of 18.76 g/cm\ :sup:`3`. The
cylinders are arranged in a 2 × 2 × 2 array. Each has a radius of
5.748 cm and a height of 10.765 cm. The center-to-center spacing in the
horizontal (X-Y) plane is 13.74 cm and the vertical center-to-center
spacing is 13.01 cm. Because the cross section processing will be done
assuming an infinite homogeneous medium and no cell mixtures are used,
there is no unit cell data. The input data for this problem follow.h](h/}Consider a problem consisting of eight uranium metal cylinders that are
93.2% wt enriched, having a density of 18.76 g/cm }(h}Consider a problem consisting of eight uranium metal cylinders that are
93.2% wt enriched, having a density of 18.76 g/cm\ h jhhh!NhNubj)}(h:sup:`3`h]h/3}(hhh jubah}(h]h]h]h]h]uhjh jubh/X. The
cylinders are arranged in a 2 × 2 × 2 array. Each has a radius of
5.748 cm and a height of 10.765 cm. The center-to-center spacing in the
horizontal (X-Y) plane is 13.74 cm and the vertical center-to-center
spacing is 13.01 cm. Because the cross section processing will be done
assuming an infinite homogeneous medium and no cell mixtures are used,
there is no unit cell data. The input data for this problem follow.}(hX. The
cylinders are arranged in a 2 × 2 × 2 array. Each has a radius of
5.748 cm and a height of 10.765 cm. The center-to-center spacing in the
horizontal (X-Y) plane is 13.74 cm and the vertical center-to-center
spacing is 13.01 cm. Because the cross section processing will be done
assuming an infinite homogeneous medium and no cell mixtures are used,
there is no unit cell data. The input data for this problem follow.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubj)}(hhh]h}(h]h]h]h]h]langscaleforcelinenothresholduhjh jhhh!jhK"ubj)}(hX=CSAS6
SET UP 2C8 IN CSAS6
V7-238
READ COMP
URANIUM 1 DEN=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 END
END COMP
READ PARAMETERS FLX=YES FDN=YES FAR=YES END PARAMETERS
READ GEOMETRY
UNIT 1
CYLINDER 10 5.748 5.3825 -5.3825
CUBOID 20 6.87 -6.87 6.87 -6.87 6.505 -6.505
MEDIA 1 1 10
MEDIA 0 1 20 -10
BOUNDARY 20
GLOBAL UNIT 2
CUBOID 10 4P13.74 2P13.010
ARRAY 1 10 PLACE 1 1 1 -6.87 -6.87 -6.505
BOUNDARY 10
END GEOMETRY
READ ARRAY
GBL=1 ARA=1 NUX=2 NUY=2 NUZ=2 FILL F1 END FILL
END ARRAY
END DATA
ENDh]h/X=CSAS6
SET UP 2C8 IN CSAS6
V7-238
READ COMP
URANIUM 1 DEN=18.76 1 293 92235 93.2 92238 5.6 92234 1.0 92236 0.2 END
END COMP
READ PARAMETERS FLX=YES FDN=YES FAR=YES END PARAMETERS
READ GEOMETRY
UNIT 1
CYLINDER 10 5.748 5.3825 -5.3825
CUBOID 20 6.87 -6.87 6.87 -6.87 6.505 -6.505
MEDIA 1 1 10
MEDIA 0 1 20 -10
BOUNDARY 20
GLOBAL UNIT 2
CUBOID 10 4P13.74 2P13.010
ARRAY 1 10 PLACE 1 1 1 -6.87 -6.87 -6.505
BOUNDARY 10
END GEOMETRY
READ ARRAY
GBL=1 ARA=1 NUX=2 NUY=2 NUZ=2 FILL F1 END FILL
END ARRAY
END DATA
END}(hhh jubah}(h]h]h]h]h]jjuhjh!jhK%h jhhubh;)}(hxEXAMPLE 2. CSAS6 – Determine the *k*\ :sub:`eff` of an array of fuel pellets in
a UO\ :sub:`2`\ F\ :sub:`2` solution.h](h/#EXAMPLE 2. CSAS6 – Determine the }(h#EXAMPLE 2. CSAS6 – Determine the h jÜhhh!NhNubh)}(h*k*h]h/k}(hhh j̜ubah}(h]h]h]h]h]uhhh jÜubh/ }(h\ h jÜhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jߜubah}(h]h]h]h]h]uhjh jÜubh/& of an array of fuel pellets in
a UO }(h& of an array of fuel pellets in
a UO\ h jÜhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jÜubh/ F }(h\ F\ h jÜhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jÜubh/ solution.}(h solution.h jÜhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhK>h jhhubh;)}(hXzConsider a 60 cm inside diameter cylindrical tank filled with
5.0%-enriched UO\ :sub:`2` fuel rods and 5.0%‑enriched
UO\ :sub:`2`\ F\ :sub:`2` solution at 295 gm/liter. A 51 × 51 × 1 array
of fuel rods is centered on the bottom of the tank. The fuel rods are
366 cm long, 0.45 cm in radius, clad with 0.01-cm-thick Al, and at a
pitch of 1.5 cm. The fuel rods sit on the bottom of the container and
the container and solution rise 5.0 cm above the top of the rods. The
container is 10 cm thick in the side and bottom and open at the top.
Determine the *k*\ :sub:`eff` of the system. Input data for this problem
follow.h](h/QConsider a 60 cm inside diameter cylindrical tank filled with
5.0%-enriched UO }(hQConsider a 60 cm inside diameter cylindrical tank filled with
5.0%-enriched UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j'ubah}(h]h]h]h]h]uhjh jubh/# fuel rods and 5.0%‑enriched
UO }(h# fuel rods and 5.0%‑enriched
UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j:ubah}(h]h]h]h]h]uhjh jubh/ F }(h\ F\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jMubah}(h]h]h]h]h]uhjh jubh/X solution at 295 gm/liter. A 51 × 51 × 1 array
of fuel rods is centered on the bottom of the tank. The fuel rods are
366 cm long, 0.45 cm in radius, clad with 0.01-cm-thick Al, and at a
pitch of 1.5 cm. The fuel rods sit on the bottom of the container and
the container and solution rise 5.0 cm above the top of the rods. The
container is 10 cm thick in the side and bottom and open at the top.
Determine the }(hX solution at 295 gm/liter. A 51 × 51 × 1 array
of fuel rods is centered on the bottom of the tank. The fuel rods are
366 cm long, 0.45 cm in radius, clad with 0.01-cm-thick Al, and at a
pitch of 1.5 cm. The fuel rods sit on the bottom of the container and
the container and solution rise 5.0 cm above the top of the rods. The
container is 10 cm thick in the side and bottom and open at the top.
Determine the h jhhh!NhNubh)}(h*k*h]h/k}(hhh j`ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jsubah}(h]h]h]h]h]uhjh jubh/3 of the system. Input data for this problem
follow.}(h3 of the system. Input data for this problem
follow.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKAh jhhubj)}(hXZ=CSAS6
UO2 pins in a UO2F2 solution
V7-238
READ COMP
UO2 1 0.95 300 92235 5.0 92238 95.0 END
AL 2 1.0 300 END
SOLNUO2F2 3 295 0.0 1.0 300 92235 5.0 92238 95.0 END
AL 4 1.0 300 END
SOLNUO2F2 5 295 0.0 1.0 300 92235 5.0 92238 95.0 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.50 3 FUELD=0.9 1 CLADD=0.94 2 END
END CELLDATA
READ GEOM
UNIT 1
COM='FUEL PIN'
CYLINDER 10 0.45 2P183.0
CYLINDER 20 0.47 2P183.1
CUBOID 30 4P0.75 2P183.1
MEDIA 1 1 10
MEDIA 2 1 20 -10
MEDIA 3 1 30 -20 -10
BOUNDARY 30
GLOBAL UNIT 2
COM='FUEL PINS AND SOLUTION IN TANK'
CUBOID 10 4p38.25 2P183.1
CYLINDER 20 60.0 188.1 -183.1
CYLINDER 30 70.0 188.1 -193.1
ARRAY 1 10 PLACE 26 26 1 3*0.0
MEDIA 5 1 20 -10
MEDIA 4 1 30 -20
BOUNDARY 30
END GEOM
READ ARRAY
ARA=1 NUX=51 NUY=51 NUZ=1 FILL F1 END FILL
END ARRAY
END DATA
ENDh]h/XZ=CSAS6
UO2 pins in a UO2F2 solution
V7-238
READ COMP
UO2 1 0.95 300 92235 5.0 92238 95.0 END
AL 2 1.0 300 END
SOLNUO2F2 3 295 0.0 1.0 300 92235 5.0 92238 95.0 END
AL 4 1.0 300 END
SOLNUO2F2 5 295 0.0 1.0 300 92235 5.0 92238 95.0 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.50 3 FUELD=0.9 1 CLADD=0.94 2 END
END CELLDATA
READ GEOM
UNIT 1
COM='FUEL PIN'
CYLINDER 10 0.45 2P183.0
CYLINDER 20 0.47 2P183.1
CUBOID 30 4P0.75 2P183.1
MEDIA 1 1 10
MEDIA 2 1 20 -10
MEDIA 3 1 30 -20 -10
BOUNDARY 30
GLOBAL UNIT 2
COM='FUEL PINS AND SOLUTION IN TANK'
CUBOID 10 4p38.25 2P183.1
CYLINDER 20 60.0 188.1 -183.1
CYLINDER 30 70.0 188.1 -193.1
ARRAY 1 10 PLACE 26 26 1 3*0.0
MEDIA 5 1 20 -10
MEDIA 4 1 30 -20
BOUNDARY 30
END GEOM
READ ARRAY
ARA=1 NUX=51 NUY=51 NUZ=1 FILL F1 END FILL
END ARRAY
END DATA
END}(hhh jubah}(h]h]h]h]h]jjuhjh!jhKNh jhhubeh}(h](run-keno-vi-using-csas6jeh]h](run keno-vi using csas6run-keno-csas6eh]h]uhh#h j8hhh!jhKj}jjsj}jjsubh$)}(hhh](h))}(h-Run KENO-VI containing cell-weighted mixturesh]h/-Run KENO-VI containing cell-weighted mixtures}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!+jhKvubh;)}(hXCSAS6 creates a microscopic working format library and a mixing table
that is passed to KENO-VI. The microscopic cross sections of the
nuclides used in the unit cell geometry description are cell‑weighted by
specifying CELLMIX= followed by a unique mixture number. This mixture
number utilizes the cell-weighted cross sections that represent the
heterogeneous system. CSAS6 executes KENO-VI and calculates *k*\ :sub:`eff` for
the problem.h](h/XCSAS6 creates a microscopic working format library and a mixing table
that is passed to KENO-VI. The microscopic cross sections of the
nuclides used in the unit cell geometry description are cell‑weighted by
specifying CELLMIX= followed by a unique mixture number. This mixture
number utilizes the cell-weighted cross sections that represent the
heterogeneous system. CSAS6 executes KENO-VI and calculates }(hXCSAS6 creates a microscopic working format library and a mixing table
that is passed to KENO-VI. The microscopic cross sections of the
nuclides used in the unit cell geometry description are cell‑weighted by
specifying CELLMIX= followed by a unique mixture number. This mixture
number utilizes the cell-weighted cross sections that represent the
heterogeneous system. CSAS6 executes KENO-VI and calculates h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jҝubah}(h]h]h]h]h]uhjh jubh/ for
the problem.}(h for
the problem.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKxh jhhubh;)}(hvEXAMPLE 1. CSAS6 – Calculate the *k*\ :sub:`eff` of an array of fuel assemblies
using cell-weighted cross sections.h](h/#EXAMPLE 1. CSAS6 – Calculate the }(h#EXAMPLE 1. CSAS6 – Calculate the h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/D of an array of fuel assemblies
using cell-weighted cross sections.}(hD of an array of fuel assemblies
using cell-weighted cross sections.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubh;)}(hXConsider the 4 × 4 × 1 array of fuel assemblies in a square aluminum
cask described in Sect. 2.2.A.1.1, Example 2. Calculate the *k*\ :sub:`eff` of
the system by using the cell-weighted mixture 200 to represent the fuel
pins in the fuel assembly. Note that mixtures 1, 2, and 3, representing
UO\ :sub:`2`, zirconium, and water, respectively, are used in the unit
cell description. Cell-weighting is applied to the microscopic
cross sections that are used in the cell, making them incorrect for use
elsewhere. Because water is used both inside the cell and between the
fuel assemblies, an additional mixture, mixture 6, has been added to
represent the water between the fuel assemblies. The input data for this
problem follow.h](h/Consider the 4 × 4 × 1 array of fuel assemblies in a square aluminum
cask described in Sect. 2.2.A.1.1, Example 2. Calculate the }(hConsider the 4 × 4 × 1 array of fuel assemblies in a square aluminum
cask described in Sect. 2.2.A.1.1, Example 2. Calculate the h j hhh!NhNubh)}(h*k*h]h/k}(hhh j)ubah}(h]h]h]h]h]uhhh j ubh/ }(h\ h j hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j<ubah}(h]h]h]h]h]uhjh j ubh/ of
the system by using the cell-weighted mixture 200 to represent the fuel
pins in the fuel assembly. Note that mixtures 1, 2, and 3, representing
UO }(h of
the system by using the cell-weighted mixture 200 to represent the fuel
pins in the fuel assembly. Note that mixtures 1, 2, and 3, representing
UO\ h j hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jOubah}(h]h]h]h]h]uhjh j ubh/X, zirconium, and water, respectively, are used in the unit
cell description. Cell-weighting is applied to the microscopic
cross sections that are used in the cell, making them incorrect for use
elsewhere. Because water is used both inside the cell and between the
fuel assemblies, an additional mixture, mixture 6, has been added to
represent the water between the fuel assemblies. The input data for this
problem follow.}(hX, zirconium, and water, respectively, are used in the unit
cell description. Cell-weighting is applied to the microscopic
cross sections that are used in the cell, making them incorrect for use
elsewhere. Because water is used both inside the cell and between the
fuel assemblies, an additional mixture, mixture 6, has been added to
represent the water between the fuel assemblies. The input data for this
problem follow.h j hhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubj)}(hXO=CSAS6
SQUARE FUEL CASK EXAMPLE USING HOMOGENEOUS MOCKUP
V7-238
READ COMP
UO2 1 DEN=9.21 1.0 293. 92235 2.35 92238 97.65 END
ZR 2 1 END
H2O 3 1 END
B4C 4 0.367 END
AL 4 0.636 END
AL 5 1 END
H2O 6 1 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.3 3 FUELD=0.8 1 CLADD=0.94 2 CELLMIX=200 END
END CELLDATA
READ PARAM FAR=YES GEN=253 END PARAM
READ GEOM
UNIT 2
COM='FUEL ASSEMBLY'
CUBOID 10 4P11.05 2P183.07
CUBOID 20 4P11.70 2P183.72
CUBOID 30 4P12.20 2P184.22
MEDIA 200 1 10
MEDIA 4 1 20 -10
MEDIA 6 1 30 -20 -10
BOUNDARY 30
GLOBAL UNIT 3
COM='FUEL CASK CONTAINING 4X4 ARRAY OF ASSEMBLIES'
CUBOID 10 4P48.8 2P184.22
CUBOID 20 4P58.8 2P194.22
ARRAY 1 10 PLACE 1 1 1 -36.6 -36.6 0.0
MEDIA 5 1 20 -10
BOUNDARY 20
END GEOM
READ ARRAY
ARA=1 NUX=4 NUY=4 NUZ=1 FILL F2 END FILL
END ARRAY
END DATA
ENDh]h/XO=CSAS6
SQUARE FUEL CASK EXAMPLE USING HOMOGENEOUS MOCKUP
V7-238
READ COMP
UO2 1 DEN=9.21 1.0 293. 92235 2.35 92238 97.65 END
ZR 2 1 END
H2O 3 1 END
B4C 4 0.367 END
AL 4 0.636 END
AL 5 1 END
H2O 6 1 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.3 3 FUELD=0.8 1 CLADD=0.94 2 CELLMIX=200 END
END CELLDATA
READ PARAM FAR=YES GEN=253 END PARAM
READ GEOM
UNIT 2
COM='FUEL ASSEMBLY'
CUBOID 10 4P11.05 2P183.07
CUBOID 20 4P11.70 2P183.72
CUBOID 30 4P12.20 2P184.22
MEDIA 200 1 10
MEDIA 4 1 20 -10
MEDIA 6 1 30 -20 -10
BOUNDARY 30
GLOBAL UNIT 3
COM='FUEL CASK CONTAINING 4X4 ARRAY OF ASSEMBLIES'
CUBOID 10 4P48.8 2P184.22
CUBOID 20 4P58.8 2P194.22
ARRAY 1 10 PLACE 1 1 1 -36.6 -36.6 0.0
MEDIA 5 1 20 -10
BOUNDARY 20
END GEOM
READ ARRAY
ARA=1 NUX=4 NUY=4 NUZ=1 FILL F2 END FILL
END ARRAY
END DATA
END}(hhh jhubah}(h]h]h]h]h]jjuhjh!jhKh jhhubh;)}(hEXAMPLE 2. CSAS6 – Determine the *k*\ :sub:`eff` of an array of fuel pellets in
a UO\ :sub:`2`\ F\ :sub:`2` solution using cell‑weighted cross sections.h](h/#EXAMPLE 2. CSAS6 – Determine the }(h#EXAMPLE 2. CSAS6 – Determine the h jvhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jvubh/ }(h\ h jvhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jvubh/& of an array of fuel pellets in
a UO }(h& of an array of fuel pellets in
a UO\ h jvhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jvubh/ F }(h\ F\ h jvhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jvubh/0 solution using cell‑weighted cross sections.}(h0 solution using cell‑weighted cross sections.h jvhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubh;)}(hThis is the same problem as described in :ref:`run-KENO-CSAS6` Example 2.
However, the rods and solutions have been replaced with a cell-weighted
mixture 50. Determine the *k*\ :sub:`eff` of the container. Input data for this
problem follow.h](h/)This is the same problem as described in }(h)This is the same problem as described in h jўhhh!NhNubh_)}(h:ref:`run-KENO-CSAS6`h]he)}(hjܞh]h/run-KENO-CSAS6}(hhh jޞubah}(h]h](jstdstd-refeh]h]h]uhhdh jڞubah}(h]h]h]h]h]refdocj refdomainjreftyperefrefexplicitrefwarnjrun-keno-csas6uhh^h!jhKh jўubh/o Example 2.
However, the rods and solutions have been replaced with a cell-weighted
mixture 50. Determine the }(ho Example 2.
However, the rods and solutions have been replaced with a cell-weighted
mixture 50. Determine the h jўhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jўubh/ }(h\ h jўhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jўubh/6 of the container. Input data for this
problem follow.}(h6 of the container. Input data for this
problem follow.h jўhhh!NhNubeh}(h]h]h]h]h]uhh:h!jhKh jhhubj)}(hX=CSAS6
UO2 pins in a UO2F2 solution, cell-weighted mixture
V7-238
READ COMP
UO2 1 0.95 300 92235 5.0 92238 95.0 END
AL 2 1.0 300 END
SOLNUO2F2 3 295 0.0 1.0 300 92235 5.0 92238 95.0 END
AL 4 1.0 300 END
SOLNUO2F2 5 295 0.0 1.0 300 92235 5.0 92238 95.0 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.50 3 FUELD=0.9 1 CLADD=0.94 2 CELLMIX=50 END
END CELLDATA
READ GEOM
GLOBAL UNIT 2
COM='FUEL PINS AND SOLUTION IN TANK'
CUBOID 10 4p38.25 2P183.1
CYLINDER 20 60.0 188.1 -183.1
CYLINDER 30 70.0 188.1 -193.1
MEDIA 50 1 10
MEDIA 5 1 20 -10
MEDIA 4 1 30 -20
BOUNDARY 30
END GEOM
END DATA
ENDh]h/X=CSAS6
UO2 pins in a UO2F2 solution, cell-weighted mixture
V7-238
READ COMP
UO2 1 0.95 300 92235 5.0 92238 95.0 END
AL 2 1.0 300 END
SOLNUO2F2 3 295 0.0 1.0 300 92235 5.0 92238 95.0 END
AL 4 1.0 300 END
SOLNUO2F2 5 295 0.0 1.0 300 92235 5.0 92238 95.0 END
END COMP
READ CELLDATA
LATTICECELL SQUAREPITCH PITCH=1.50 3 FUELD=0.9 1 CLADD=0.94 2 CELLMIX=50 END
END CELLDATA
READ GEOM
GLOBAL UNIT 2
COM='FUEL PINS AND SOLUTION IN TANK'
CUBOID 10 4p38.25 2P183.1
CYLINDER 20 60.0 188.1 -183.1
CYLINDER 30 70.0 188.1 -193.1
MEDIA 50 1 10
MEDIA 5 1 20 -10
MEDIA 4 1 30 -20
BOUNDARY 30
END GEOM
END DATA
END}(hhh j+ubah}(h]h]h]h]h]jjuhjh!jhKh jhhubeh}(h]-run-keno-vi-containing-cell-weighted-mixturesah]h]-run keno-vi containing cell-weighted mixturesah]h]uhh#h j8hhh!jhKvubjxeh}(h](Jcsas6-control-module-for-enhanced-criticality-safety-analysis-with-keno-vicsas6eh]h](Kcsas6: control module for enhanced criticality safety analysis with keno-vicsas6eh]h]uhh#h h%hhh!jIhKj}jHh)}(h
.. _CSAS6:h]h}(h]h]h]h]h]hjDuhh
hMh h$)}(hhh](h))}(hOFuel Bundles Separated by Flux Traps — Critical Search Boron and Al Densitiesh]h/OFuel Bundles Separated by Flux Traps — Critical Search Boron and Al Densities}(hj[h jYhhh!NhNubah}(h]h]h]h]h]uhh(h jVhhh!CSAS5App.rsthM_ubh;)}(hXThe fuel bundles in this problem represent 17 × 17 PWR fuel assemblies.
The fuel pins are smeared together, making a mixture 100. The fuel pins
consist of 4.35 wt % :sup:`235`\ U having a diameter of 0.823 cm,
zirconium cladding having an outer diameter of 0.9627 cm, and a pitch of
1.275 cm. The fuel bundle is represented as a 10.8375 cm × 10.8375 cm ×
366 cm cuboid of mixture 100 surrounded by Boral and then water. The
Boral has a density of 2.61 g/cm\ :sup:`3` and has an initial composed
of 50.0 wt % B\ :sub:`4`\ C and 50.0 wt % Al. The fuel bundles are at a
fixed pitch of 13.0 cm. Boral plates surrounding the X and Y sides of
each fuel assembly are 0.1625 cm thick. Full density water is between
the Boral plates.h](h/The fuel bundles in this problem represent 17 × 17 PWR fuel assemblies.
The fuel pins are smeared together, making a mixture 100. The fuel pins
consist of 4.35 wt % }(hThe fuel bundles in this problem represent 17 × 17 PWR fuel assemblies.
The fuel pins are smeared together, making a mixture 100. The fuel pins
consist of 4.35 wt % h jhhhh!NhNubj)}(h
:sup:`235`h]h/235}(hhh jqubah}(h]h]h]h]h]uhjh jhubh/X$ U having a diameter of 0.823 cm,
zirconium cladding having an outer diameter of 0.9627 cm, and a pitch of
1.275 cm. The fuel bundle is represented as a 10.8375 cm × 10.8375 cm ×
366 cm cuboid of mixture 100 surrounded by Boral and then water. The
Boral has a density of 2.61 g/cm }(hX$\ U having a diameter of 0.823 cm,
zirconium cladding having an outer diameter of 0.9627 cm, and a pitch of
1.275 cm. The fuel bundle is represented as a 10.8375 cm × 10.8375 cm ×
366 cm cuboid of mixture 100 surrounded by Boral and then water. The
Boral has a density of 2.61 g/cm\ h jhhhh!NhNubj)}(h:sup:`3`h]h/3}(hhh jubah}(h]h]h]h]h]uhjh jhubh// and has an initial composed
of 50.0 wt % B }(h/ and has an initial composed
of 50.0 wt % B\ h jhhhh!NhNubj)}(h:sub:`4`h]h/4}(hhh jubah}(h]h]h]h]h]uhjh jhubh/ C and 50.0 wt % Al. The fuel bundles are at a
fixed pitch of 13.0 cm. Boral plates surrounding the X and Y sides of
each fuel assembly are 0.1625 cm thick. Full density water is between
the Boral plates.}(h\ C and 50.0 wt % Al. The fuel bundles are at a
fixed pitch of 13.0 cm. Boral plates surrounding the X and Y sides of
each fuel assembly are 0.1625 cm thick. Full density water is between
the Boral plates.h jhhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMah jVhhubh;)}(hXA critical concentration search is performed on the Boral plates
searching for a system *k*\ :sub:`eff` = 0.95. The Boral plates are at a fixed
density of 2.61 gm/cc. As the density of the B\ :sub:`4`\ C changes, the
density of the Al changes in the opposite direction maintaining a
constant Boral density. There are two entries in the MORE search data.
The first entry, MIX=4 SCNAME=b4c factor=1.0 specifies that the
B\ :sub:`4`\ C of mixture 4 is to be altered during the search. The
second entry, MIX=4 SCNAME=al factor = −1.0 specifies that aluminum is
to be changed in the opposite direction and proportionally to
B\ :sub:`4`\ C during the search. Both B\ :sub:`4`\ C and Al have the
same initial density of 0.5 \* 2.61 = 1.305 gm/cc.h](h/XA critical concentration search is performed on the Boral plates
searching for a system }(hXA critical concentration search is performed on the Boral plates
searching for a system h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j̟ubah}(h]h]h]h]h]uhjh jubh/] = 0.95. The Boral plates are at a fixed
density of 2.61 gm/cc. As the density of the B }(h] = 0.95. The Boral plates are at a fixed
density of 2.61 gm/cc. As the density of the B\ h jhhh!NhNubj)}(h:sub:`4`h]h/4}(hhh jߟubah}(h]h]h]h]h]uhjh jubh/ C changes, the
density of the Al changes in the opposite direction maintaining a
constant Boral density. There are two entries in the MORE search data.
The first entry, MIX=4 SCNAME=b4c factor=1.0 specifies that the
B }(h\ C changes, the
density of the Al changes in the opposite direction maintaining a
constant Boral density. There are two entries in the MORE search data.
The first entry, MIX=4 SCNAME=b4c factor=1.0 specifies that the
B\ h jhhh!NhNubj)}(h:sub:`4`h]h/4}(hhh jubah}(h]h]h]h]h]uhjh jubh/ C of mixture 4 is to be altered during the search. The
second entry, MIX=4 SCNAME=al factor = −1.0 specifies that aluminum is
to be changed in the opposite direction and proportionally to
B }(h\ C of mixture 4 is to be altered during the search. The
second entry, MIX=4 SCNAME=al factor = −1.0 specifies that aluminum is
to be changed in the opposite direction and proportionally to
B\ h jhhh!NhNubj)}(h:sub:`4`h]h/4}(hhh jubah}(h]h]h]h]h]uhjh jubh/ C during the search. Both B }(h\ C during the search. Both B\ h jhhh!NhNubj)}(h:sub:`4`h]h/4}(hhh jubah}(h]h]h]h]h]uhjh jubh/I C and Al have the
same initial density of 0.5 * 2.61 = 1.305 gm/cc.}(hI\ C and Al have the
same initial density of 0.5 \* 2.61 = 1.305 gm/cc.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMmh jVhhubh;)}(h2The maximum constraint is calculated according to:h]h/2The maximum constraint is calculated according to:}(hj3h j1hhh!NhNubah}(h]h]h]h]h]uhh:h!jghMyh jVhhubj
)}(hhh]h;)}(h&+CON= (2.59695/1.305 − 1)/1.0 = 0.99h]h/&+CON= (2.59695/1.305 − 1)/1.0 = 0.99}(hjDh jBubah}(h]h]h]h]h]uhh:h!jghM{h j?ubah}(h]h]h]h]h]uhj h jVhhh!jghNubh;)}(h2The minimum constraint is calculated according to:h]h/2The minimum constraint is calculated according to:}(hjXh jVhhh!NhNubah}(h]h]h]h]h]uhh:h!jghM}h jVhhubj
)}(hhh]h;)}(h)−CON= (0.1305/1.305 − 1)/1.0 = −0.9h]h/)−CON= (0.1305/1.305 − 1)/1.0 = −0.9}(hjih jgubah}(h]h]h]h]h]uhh:h!jghMh jdubah}(h]h]h]h]h]uhj h jVhhh!jghNubh;)}(hAThe search data and final search results for this problem follow:h]h/AThe search data and final search results for this problem follow:}(hj}h j{hhh!NhNubah}(h]h]h]h]h]uhh:h!jghMh jVhhubj)}(hX=csas5s
array of fuel bundles with flux trap
v7-238
read comp
uo2 1 .84 300. 92235 4.35 92238 95.65 end
zr 2 1 end
h2o 3 1 end
b4c 4 den=2.61 0.5 end
al 4 den=2.61 0.5 end
h2o 5 1.0 end
end comp
read celldata
latticecell squarepitch pitch=1.275 3 fueld=0.823 1 cladd=0.9627 2 cellmix=100 end
end celldata
read param far=yes gen=203 npg=1000 end param
read geom
global unit 1
cuboid 100 1 4p10.8375 2p183.0
cuboid 4 1 4p11.0 2p183.0
cuboid 5 1 4p13.0 2p183.0
end geom
read bounds xfc=mirror yfc=mirror end bounds
end data
read search critical concentration kef=0.95 more
alter mix=4 scname=arbmb4c factor=1.0
alter mix=4 scname=al factor=-1.0
-con=-0.9 +con=0.99
end search
endh]h/X=csas5s
array of fuel bundles with flux trap
v7-238
read comp
uo2 1 .84 300. 92235 4.35 92238 95.65 end
zr 2 1 end
h2o 3 1 end
b4c 4 den=2.61 0.5 end
al 4 den=2.61 0.5 end
h2o 5 1.0 end
end comp
read celldata
latticecell squarepitch pitch=1.275 3 fueld=0.823 1 cladd=0.9627 2 cellmix=100 end
end celldata
read param far=yes gen=203 npg=1000 end param
read geom
global unit 1
cuboid 100 1 4p10.8375 2p183.0
cuboid 4 1 4p11.0 2p183.0
cuboid 5 1 4p13.0 2p183.0
end geom
read bounds xfc=mirror yfc=mirror end bounds
end data
read search critical concentration kef=0.95 more
alter mix=4 scname=arbmb4c factor=1.0
alter mix=4 scname=al factor=-1.0
-con=-0.9 +con=0.99
end search
end}(hhh jubah}(h]h]h]h]h]jjuhjh!jghMh jVhhubj)}(hX|$=csas5s
array of fuel bundles with flux trap
v7-238
read comp
uo2 1 .84 300. 92235 4.35 92238 95.65 end
zr 2 1 end
h2o 3 1 end
b4c 4 den=2.61 0.5 end
al 4 den=2.61 0.5 end
h2o 5 1.0 end
end comp
read celldata
latticecell squarepitch pitch=1.275 3 fueld=0.823 1 cladd=0.9627 2 cellmix=100 end
end celldata
read param far=yes gen=203 npg=1000 end param
read geom
global unit 1
cuboid 100 1 4p10.8375 2p183.0
cuboid 4 1 4p11.0 2p183.0
cuboid 5 1 4p13.0 2p183.0
end geom
read bounds xfc=mirror yfc=mirror end bounds
end data
read search critical concentration kef=0.95 more
alter mix=4 scname=arbmb4c factor=1.0
alter mix=4 scname=al factor=-1.0
-con=-0.9 +con=0.99
end search
end
******************* search pass 1 keff= 8.22991E-01 + or - 1.79474E-03 ******************
the parameter was 0.00000E+00
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 8.01629E-01 + or - 1.78327E-03 ******************
the parameter was 9.90000E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 9.82092E-01 + or - 1.63305E-03 ******************
the parameter was -9.00000E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 4 keff= 9.01534E-01 + or - 1.74845E-03 ******************
the parameter was -7.66111E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 5 keff= 9.38557E-01 + or - 1.59285E-03 ******************
the parameter was -8.52032E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 6 keff= 9.48930E-01 + or - 1.69920E-03 ******************
the parameter was -8.65663E-01
array of fuel bundles with flux trap
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 6 the parameter was -8.65663E-01
the equation used in the search was:
k-eff = +8.66738E-01 +2.74121E-01*p +5.80563E-02*p**2 -4.25484E-01*p**3
k-effective= 9.48930E-01 + or - 1.69920E-03 the corresponding geometry follows;
array of fuel bundles with flux trap
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 9.2064
nuclide atom-dens. wgt. frac. za awt nuclide title
1008016 4.10835E-02 1.18491E-01 8016 15.9904 8O 16 from version 6 evaluation
1092235 9.04496E-04 3.83457E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.96373E-02 8.43163E-01 92238 238.0510 92U 238 ANL+EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 6.4900
nuclide atom-dens. wgt. frac. za awt nuclide title
2040000 4.28457E-02 1.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
mixture = 3 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 4 density(g/cc) = 2.6100
nuclide atom-dens. wgt. frac. za awt nuclide title
4005010 1.52119E-03 9.69077E-03 5010 10.0130 5b100lasl evaldec76 g.hale l.stewart mod1 12/11/92
4005011 6.12300E-03 4.28888E-02 5011 11.0096 5b11 gebnl evalsep71 c.cowan mod1 12/11/92 free gas
4006012 1.91105E-03 1.45903E-02 6000 12.0001 6cornl evaldec73 c.y.fu and f.g. perey mod2 12/11/92
4013027 5.43405E-02 9.32830E-01 13027 26.9818 13al270lasl evaldec73 p.g. young d.g mod1 11/29/88
mixture = 5 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
5001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
5008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 100 density(g/cc) = 0.0000
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 0.00000E+00 0.00000E+00 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
1008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
2040000 0.00000E+00 0.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
1092235 0.00000E+00 0.00000E+00 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 0.00000E+00 0.00000E+00 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
based on the preceding data, the best estimate of the parameter is -8.66988E-01
the mixing table corresponding to this parameter follows:
array of fuel bundles with flux trap
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 9.2064
nuclide atom-dens. wgt. frac. za awt nuclide title
1008016 4.10835E-02 1.18491E-01 8016 15.9904 8O 16 from version 6 evaluation
1092235 9.04496E-04 3.83457E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.96373E-02 8.43163E-01 92238 238.0510 92U 238 ANL+EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 6.4900
nuclide atom-dens. wgt. frac. za awt nuclide title
2040000 4.28457E-02 1.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
mixture = 3 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 4 density(g/cc) = 2.6100
nuclide atom-dens. wgt. frac. za awt nuclide title
4005010 1.50619E-03 9.59518E-03 5010 10.0130 5b 100lasl evaldec76 g.hale l.stewart mod1 12/11/92
4005011 6.06261E-03 4.24657E-02 5011 11.0096 5b11 gebnl evalsep71 c.cowan mod1 12/11/92 free gas
4006012 1.89220E-03 1.44464E-02 6000 12.0001 6c ornl evaldec73 c.y.fu and f.g. perey mod2 12/11/92
4013027 5.43791E-02 9.33493E-01 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1 11/29/88
mixture = 5 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
5001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
5008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 100 density(g/cc) = 0.0000
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 0.00000E+00 0.00000E+00 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
1008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
2040000 0.00000E+00 0.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
1092235 0.00000E+00 0.00000E+00 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 0.00000E+00 0.00000E+00 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
*******************************************************************************************************
*******************************************************************************************************h]h/X|$=csas5s
array of fuel bundles with flux trap
v7-238
read comp
uo2 1 .84 300. 92235 4.35 92238 95.65 end
zr 2 1 end
h2o 3 1 end
b4c 4 den=2.61 0.5 end
al 4 den=2.61 0.5 end
h2o 5 1.0 end
end comp
read celldata
latticecell squarepitch pitch=1.275 3 fueld=0.823 1 cladd=0.9627 2 cellmix=100 end
end celldata
read param far=yes gen=203 npg=1000 end param
read geom
global unit 1
cuboid 100 1 4p10.8375 2p183.0
cuboid 4 1 4p11.0 2p183.0
cuboid 5 1 4p13.0 2p183.0
end geom
read bounds xfc=mirror yfc=mirror end bounds
end data
read search critical concentration kef=0.95 more
alter mix=4 scname=arbmb4c factor=1.0
alter mix=4 scname=al factor=-1.0
-con=-0.9 +con=0.99
end search
end
******************* search pass 1 keff= 8.22991E-01 + or - 1.79474E-03 ******************
the parameter was 0.00000E+00
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 8.01629E-01 + or - 1.78327E-03 ******************
the parameter was 9.90000E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 9.82092E-01 + or - 1.63305E-03 ******************
the parameter was -9.00000E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 4 keff= 9.01534E-01 + or - 1.74845E-03 ******************
the parameter was -7.66111E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 5 keff= 9.38557E-01 + or - 1.59285E-03 ******************
the parameter was -8.52032E-01
**** xsdrnpm mesh intervals ****
4 mesh intervals in zone 1
4 mesh intervals in zone 2
14 mesh intervals in zone 3
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 6 keff= 9.48930E-01 + or - 1.69920E-03 ******************
the parameter was -8.65663E-01
array of fuel bundles with flux trap
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 6 the parameter was -8.65663E-01
the equation used in the search was:
k-eff = +8.66738E-01 +2.74121E-01*p +5.80563E-02*p**2 -4.25484E-01*p**3
k-effective= 9.48930E-01 + or - 1.69920E-03 the corresponding geometry follows;
array of fuel bundles with flux trap
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 9.2064
nuclide atom-dens. wgt. frac. za awt nuclide title
1008016 4.10835E-02 1.18491E-01 8016 15.9904 8O 16 from version 6 evaluation
1092235 9.04496E-04 3.83457E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.96373E-02 8.43163E-01 92238 238.0510 92U 238 ANL+EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 6.4900
nuclide atom-dens. wgt. frac. za awt nuclide title
2040000 4.28457E-02 1.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
mixture = 3 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 4 density(g/cc) = 2.6100
nuclide atom-dens. wgt. frac. za awt nuclide title
4005010 1.52119E-03 9.69077E-03 5010 10.0130 5b100lasl evaldec76 g.hale l.stewart mod1 12/11/92
4005011 6.12300E-03 4.28888E-02 5011 11.0096 5b11 gebnl evalsep71 c.cowan mod1 12/11/92 free gas
4006012 1.91105E-03 1.45903E-02 6000 12.0001 6cornl evaldec73 c.y.fu and f.g. perey mod2 12/11/92
4013027 5.43405E-02 9.32830E-01 13027 26.9818 13al270lasl evaldec73 p.g. young d.g mod1 11/29/88
mixture = 5 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
5001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
5008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 100 density(g/cc) = 0.0000
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 0.00000E+00 0.00000E+00 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
1008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
2040000 0.00000E+00 0.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
1092235 0.00000E+00 0.00000E+00 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 0.00000E+00 0.00000E+00 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
based on the preceding data, the best estimate of the parameter is -8.66988E-01
the mixing table corresponding to this parameter follows:
array of fuel bundles with flux trap
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 9.2064
nuclide atom-dens. wgt. frac. za awt nuclide title
1008016 4.10835E-02 1.18491E-01 8016 15.9904 8O 16 from version 6 evaluation
1092235 9.04496E-04 3.83457E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.96373E-02 8.43163E-01 92238 238.0510 92U 238 ANL+EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 6.4900
nuclide atom-dens. wgt. frac. za awt nuclide title
2040000 4.28457E-02 1.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
mixture = 3 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 4 density(g/cc) = 2.6100
nuclide atom-dens. wgt. frac. za awt nuclide title
4005010 1.50619E-03 9.59518E-03 5010 10.0130 5b 100lasl evaldec76 g.hale l.stewart mod1 12/11/92
4005011 6.06261E-03 4.24657E-02 5011 11.0096 5b11 gebnl evalsep71 c.cowan mod1 12/11/92 free gas
4006012 1.89220E-03 1.44464E-02 6000 12.0001 6c ornl evaldec73 c.y.fu and f.g. perey mod2 12/11/92
4013027 5.43791E-02 9.33493E-01 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1 11/29/88
mixture = 5 density(g/cc) = 0.99817
nuclide atom-dens. wgt. frac. za awt nuclide title
5001001 6.67692E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
5008016 3.33846E-02 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
mixture = 100 density(g/cc) = 0.0000
nuclide atom-dens. wgt. frac. za awt nuclide title
3001001 0.00000E+00 0.00000E+00 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
3008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
1008016 0.00000E+00 0.00000E+00 8016 15.9904 8O 16 from version 6 evaluation
2040000 0.00000E+00 0.00000E+00 40000 91.2196 40zr sai evalapr76 m.drake d.sa mod2 01/03/89
1092235 0.00000E+00 0.00000E+00 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 0.00000E+00 0.00000E+00 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
*******************************************************************************************************
*******************************************************************************************************}(hhh jubah}(h]h]h]h]h]jjuhjh!jghMh jVhhubjLeh}(h]Kfuel-bundles-separated-by-flux-traps-critical-search-boron-and-al-densitiesah]h]Ofuel bundles separated by flux traps — critical search boron and al densitiesah]h]uhh#h h$)}(hhh](h))}(hCritical concentration searchh]h/Critical concentration search}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!jghMeubh;)}(hXA critical concentration search alters the concentration of the
specified standard composition in the specified mixture to obtain a
specified value of *k*\ :sub:`eff`. A critical concentration search is
activated by entering “CRITICAL CONCENTRATION” in the search data. There
are no defaulted search data in a critical concentration search except
for the value of *k*\ :sub:`eff`. If something other than *k*\ :sub:`eff` = 1.0 is
desired the user must specify KEF=**, where \*\* is the desired value of
*k*\ :sub:`eff`. The remaining data is entered after the keyword MORE in the
search data block. The user must specify the material and standard
composition name to be changed and the manner in which they will be
changed as described in the auxiliary search commands.h](h/A critical concentration search alters the concentration of the
specified standard composition in the specified mixture to obtain a
specified value of }(hA critical concentration search alters the concentration of the
specified standard composition in the specified mixture to obtain a
specified value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jǠubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jڠubah}(h]h]h]h]h]uhjh jubh/. A critical concentration search is
activated by entering “CRITICAL CONCENTRATION” in the search data. There
are no defaulted search data in a critical concentration search except
for the value of }(h. A critical concentration search is
activated by entering “CRITICAL CONCENTRATION” in the search data. There
are no defaulted search data in a critical concentration search except
for the value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/. If something other than }(h. If something other than h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh j&ubah}(h]h]h]h]h]uhjh jubh/U = 1.0 is
desired the user must specify KEF=**, where ** is the desired value of
}(hU = 1.0 is
desired the user must specify KEF=**, where \*\* is the desired value of
h jhhh!NhNubh)}(h*k*h]h/k}(hhh j9ubah}(h]h]h]h]h]uhhh jubh/ }(hj٠h jubj)}(h
:sub:`eff`h]h/eff}(hhh jKubah}(h]h]h]h]h]uhjh jubh/. The remaining data is entered after the keyword MORE in the
search data block. The user must specify the material and standard
composition name to be changed and the manner in which they will be
changed as described in the auxiliary search commands.}(h. The remaining data is entered after the keyword MORE in the
search data block. The user must specify the material and standard
composition name to be changed and the manner in which they will be
changed as described in the auxiliary search commands.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMgh jhhubh;)}(hXA concentration search is performed by altering the atom densities of
the specified standard compositions in the specified materials. The
ratio of how the standard compositions change relative to each other is
controlled using FACTOR. If a material and standard composition is not
listed in the search data it remains unchanged. The concentration search
can vary from zero to some upper limit. The code will prevent the
concentration from falling below zero, but the user is responsible for
setting constraints that prevent the concentration from exceeding
reasonable values. In most cases the theoretical density is a reasonable
upper limit.h]h/XA concentration search is performed by altering the atom densities of
the specified standard compositions in the specified materials. The
ratio of how the standard compositions change relative to each other is
controlled using FACTOR. If a material and standard composition is not
listed in the search data it remains unchanged. The concentration search
can vary from zero to some upper limit. The code will prevent the
concentration from falling below zero, but the user is responsible for
setting constraints that prevent the concentration from exceeding
reasonable values. In most cases the theoretical density is a reasonable
upper limit.}(hjfh jdhhh!NhNubah}(h]h]h]h]h]uhh:h!jghMsh jhhubh$)}(hhh](h))}(hGArray of Spheres in H\ :sub:`2`\ O — Search on H\ :sub:`2`\ O Densityh](h/Array of Spheres in H }(hArray of Spheres in H\ h juhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j~ubah}(h]h]h]h]h]uhjh juubh/ O — Search on H }(h\ O — Search on H\ h juhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh juubh/ O Density}(h\ O Densityh juhhh!NhNubeh}(h]h]h]h]h]uhh(h jrhhh!jghMubh;)}(hXConsider a 10 × 10 × 10 array of uranium spheres arranged in an array
having a “square” pitch. The uranium spheres are 2 cm in radius, and the
center-to-center spacing is 8 cm. The uranium spheres and their
associated spacing are defined to be unit 1, and the 10 × 10 × 10 array
is defined to be array 1.0 cm. The spheres are initially moderated by ½
density water.h]h/XConsider a 10 × 10 × 10 array of uranium spheres arranged in an array
having a “square” pitch. The uranium spheres are 2 cm in radius, and the
center-to-center spacing is 8 cm. The uranium spheres and their
associated spacing are defined to be unit 1, and the 10 × 10 × 10 array
is defined to be array 1.0 cm. The spheres are initially moderated by ½
density water.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jghMh jrhhubh;)}(hXA critical concentration search is performed on the water yielding
system *k*\ :sub:`eff` = 1.0 for various densities of water. In the MORE search
data, MIX=2 and SCNAME=H2O specify that the water component of mixture 2
is to be altered during the search from an initial density of 0.5 gm/cc.
The maximum allowed density is full density water (1.0 gm/cc). The
minimum allowed water density is 0.0005 gm/cc.h](h/JA critical concentration search is performed on the water yielding
system }(hJA critical concentration search is performed on the water yielding
system h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jԡubah}(h]h]h]h]h]uhjh jubh/XC = 1.0 for various densities of water. In the MORE search
data, MIX=2 and SCNAME=H2O specify that the water component of mixture 2
is to be altered during the search from an initial density of 0.5 gm/cc.
The maximum allowed density is full density water (1.0 gm/cc). The
minimum allowed water density is 0.0005 gm/cc.}(hXC = 1.0 for various densities of water. In the MORE search
data, MIX=2 and SCNAME=H2O specify that the water component of mixture 2
is to be altered during the search from an initial density of 0.5 gm/cc.
The maximum allowed density is full density water (1.0 gm/cc). The
minimum allowed water density is 0.0005 gm/cc.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMh jrhhubh;)}(h2The maximum constraint is calculated according to:h]h/2The maximum constraint is calculated according to:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jghMh jrhhubj
)}(hhh]h;)}(h+CON= (1.0/0.5 − 1)/1.0 = 1.0h]h/+CON= (1.0/0.5 − 1)/1.0 = 1.0}(hjh jubah}(h]h]h]h]h]uhh:h!jghMh jubah}(h]h]h]h]h]uhj h jrhhh!jghNubh;)}(h2The minimum constraint is calculated according to:h]h/2The minimum constraint is calculated according to:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jghMh jrhhubj
)}(hhh]h;)}(h)−CON= (0.0005/0.5 − 1)/1.0 = −0.999h]h/)−CON= (0.0005/0.5 − 1)/1.0 = −0.999}(hj%h j#ubah}(h]h]h]h]h]uhh:h!jghMh j ubah}(h]h]h]h]h]uhj h jrhhh!jghNubh;)}(hAThe search data and final search results for this problem follow:h]h/AThe search data and final search results for this problem follow:}(hj9h j7hhh!NhNubah}(h]h]h]h]h]uhh:h!jghMh jrhhubj)}(hX=CSAS5S
10x10x10 ARRAY - CONCENTRATION SEARCH
V7-238
READ COMP
URANIUM 1 1.0 300.0 92235 90.0 92238 10.0 END
H2O 2 0.5 300.0 END
END COMP
READ CELLDATA
LATTICECELL SPHSQUAREP PITCH=8.0 2 FUELD=4.0 1 END
END CELLDATA
READ GEOMETRY
UNIT 1
SPHERE 1 1 2.0
CUBOID 2 1 6P4.0
END GEOMETRY
READ ARRAY
ARA=1 NUX=10 NUY=10 NUZ=10 FILL F1 END FILL
END ARRAY
END DATA
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=2 SCNAME=H2O factor=1.0
-CON=-0.999 +CON=1.0
END SEARCH
ENDh]h/X=CSAS5S
10x10x10 ARRAY - CONCENTRATION SEARCH
V7-238
READ COMP
URANIUM 1 1.0 300.0 92235 90.0 92238 10.0 END
H2O 2 0.5 300.0 END
END COMP
READ CELLDATA
LATTICECELL SPHSQUAREP PITCH=8.0 2 FUELD=4.0 1 END
END CELLDATA
READ GEOMETRY
UNIT 1
SPHERE 1 1 2.0
CUBOID 2 1 6P4.0
END GEOMETRY
READ ARRAY
ARA=1 NUX=10 NUY=10 NUZ=10 FILL F1 END FILL
END ARRAY
END DATA
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=2 SCNAME=H2O factor=1.0
-CON=-0.999 +CON=1.0
END SEARCH
END}(hhh jEubah}(h]h]h]h]h]jjuhjh!jghMh jrhhubj)}(hXm******************* search pass 1 keff= 1.22228E+00 + or - 1.75549E-03 ******************
the parameter was 0.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 4.97499E-01 + or - 1.19161E-03 ******************
the parameter was -9.99000E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 1.15356E+00 + or - 1.85214E-03 ******************
the parameter was -3.06377E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 4 keff= 9.72210E-01 + or - 1.89881E-03 ******************
the parameter was -5.52436E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 5 keff= 1.00805E+00 + or - 1.91023E-03 ******************
the parameter was -5.21036E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 6 keff= 1.00056E+00 + or - 2.05463E-03 ******************
the parameter was -5.28450E-01
10x10x10 array - concentration search
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 6 the parameter was -5.28450E-01
the equation used in the search was:
k-eff = +1.19891E+00 -5.90957E-01*p -2.41575E+00*p**2 -1.11098E+00*p**3
k-effective= 1.00056E+00 + or - 2.05463E-03 the corresponding geometry follows;
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23534
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.57425E-02 1.11926E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.87126E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
based on the preceding data, the best estimate of the parameter is -5.28963E-01
the mixing table corresponding to this parameter follows:
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23509
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.57254E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.86270E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
****************************************************************************************************
****************************************************************************************************h]h/Xm******************* search pass 1 keff= 1.22228E+00 + or - 1.75549E-03 ******************
the parameter was 0.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 4.97499E-01 + or - 1.19161E-03 ******************
the parameter was -9.99000E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 1.15356E+00 + or - 1.85214E-03 ******************
the parameter was -3.06377E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 4 keff= 9.72210E-01 + or - 1.89881E-03 ******************
the parameter was -5.52436E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 5 keff= 1.00805E+00 + or - 1.91023E-03 ******************
the parameter was -5.21036E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 6 keff= 1.00056E+00 + or - 2.05463E-03 ******************
the parameter was -5.28450E-01
10x10x10 array - concentration search
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 6 the parameter was -5.28450E-01
the equation used in the search was:
k-eff = +1.19891E+00 -5.90957E-01*p -2.41575E+00*p**2 -1.11098E+00*p**3
k-effective= 1.00056E+00 + or - 2.05463E-03 the corresponding geometry follows;
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23534
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.57425E-02 1.11926E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.87126E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
based on the preceding data, the best estimate of the parameter is -5.28963E-01
the mixing table corresponding to this parameter follows:
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23509
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.57254E-02 1.11927E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.86270E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
****************************************************************************************************
****************************************************************************************************}(hhh jSubah}(h]h]h]h]h]jjuhjh!jghMh jrhhubeh}(h]id26ah]h]h]1array of spheres in h2o — search on h2o densityah]uhh#h jhhh!jghMjmKubh$)}(hhh](h))}(hGArray of Spheres in H\ :sub:`2`\ O — Search on H\ :sub:`2`\ O Densityh](h/Array of Spheres in H }(hArray of Spheres in H\ h jlhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh juubah}(h]h]h]h]h]uhjh jlubh/ O — Search on H }(h\ O — Search on H\ h jlhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jlubh/ O Density}(h\ O Densityh jlhhh!NhNubeh}(h]h]h]h]h]uhh(h jihhh!jghMubh;)}(hXThis is the same problem as described above with the exception of the
initial water density, which is now 0.25 gm/cc. A critical concentration
search is performed on the water yielding a system *k*\ :sub:`eff` = 1.0 for
various densities of water. In the MORE search data, MIX=2 and
SCNAME=H2O specify that the water component of mixture 2 is to be
altered during the search from an initial value of 0.25 gm/cc. The
maximum allowed density is ½ density water (0.5 gm/cc). The minimum
allowed water density is 0.1 gm/cc.h](h/This is the same problem as described above with the exception of the
initial water density, which is now 0.25 gm/cc. A critical concentration
search is performed on the water yielding a system }(hThis is the same problem as described above with the exception of the
initial water density, which is now 0.25 gm/cc. A critical concentration
search is performed on the water yielding a system h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/X> = 1.0 for
various densities of water. In the MORE search data, MIX=2 and
SCNAME=H2O specify that the water component of mixture 2 is to be
altered during the search from an initial value of 0.25 gm/cc. The
maximum allowed density is ½ density water (0.5 gm/cc). The minimum
allowed water density is 0.1 gm/cc.}(hX> = 1.0 for
various densities of water. In the MORE search data, MIX=2 and
SCNAME=H2O specify that the water component of mixture 2 is to be
altered during the search from an initial value of 0.25 gm/cc. The
maximum allowed density is ½ density water (0.5 gm/cc). The minimum
allowed water density is 0.1 gm/cc.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMh jihhubh;)}(h2The maximum constraint is calculated according to:h]h/2The maximum constraint is calculated according to:}(hjآh j֢hhh!NhNubah}(h]h]h]h]h]uhh:h!jghM
h jihhubj
)}(hhh]h;)}(h +CON= (5.0/0.25 − 1)/1.0 = 1.0h]h/ +CON= (5.0/0.25 − 1)/1.0 = 1.0}(hjh jubah}(h]h]h]h]h]uhh:h!jghM
h jubah}(h]h]h]h]h]uhj h jihhh!jghNubh;)}(h2The minimum constraint is calculated according to:h]h/2The minimum constraint is calculated according to:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jghM
h jihhubj
)}(hhh]h;)}(h&−CON= (0.1/0.25 − 1)/1.0 = − 0.6h]h/&−CON= (0.1/0.25 − 1)/1.0 = − 0.6}(hjh jubah}(h]h]h]h]h]uhh:h!jghM
h j ubah}(h]h]h]h]h]uhj h jihhh!jghNubh;)}(hAThe search data and final search results for this problem follow:h]h/AThe search data and final search results for this problem follow:}(hj"h j hhh!NhNubah}(h]h]h]h]h]uhh:h!jghM
h jihhubj)}(hX=CSAS5S
10x10x10 ARRAY - CONCENTRATION SEARCH
V7-238
READ COMP
URANIUM 1 1.0 300.0 92235 90.0 92238 10.0 END
H2O 2 0.25 300.0 END
END COMP
READ CELLDATA
LATTICECELL SPHSQUAREP PITCH=8.0 2 FUELD=4.0 1 END
END CELLDATA
READ GEOMETRY
UNIT 1
SPHERE 1 1 2.0
CUBOID 2 1 6P4.0
END GEOMETRY
READ ARRAY
ARA=1 NUX=10 NUY=10 NUZ=10 FILL F1 END FILL
END ARRAY
END DATA
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=2 SCNAME=H2O factor=1.0
-CON=-0.6 +CON=1.0
END SEARCH
ENDh]h/X=CSAS5S
10x10x10 ARRAY - CONCENTRATION SEARCH
V7-238
READ COMP
URANIUM 1 1.0 300.0 92235 90.0 92238 10.0 END
H2O 2 0.25 300.0 END
END COMP
READ CELLDATA
LATTICECELL SPHSQUAREP PITCH=8.0 2 FUELD=4.0 1 END
END CELLDATA
READ GEOMETRY
UNIT 1
SPHERE 1 1 2.0
CUBOID 2 1 6P4.0
END GEOMETRY
READ ARRAY
ARA=1 NUX=10 NUY=10 NUZ=10 FILL F1 END FILL
END ARRAY
END DATA
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=2 SCNAME=H2O factor=1.0
-CON=-0.6 +CON=1.0
END SEARCH
END}(hhh j.ubah}(h]h]h]h]h]jjuhjh!jghM
h jihhubj)}(hX
******************* search pass 1 keff= 1.02599E+00 + or - 1.98346E-03 ******************
the parameter was 0.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 6.69203E-01 + or - 1.55844E-03 ******************
the parameter was -6.00000E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 1.00197E+00 + or - 1.73659E-03 ******************
the parameter was -4.37073E-02
10x10x10 array - concentration search
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 3 the parameter was -4.37073E-02
the equation used in the search was:
k-eff = +0.00000E+00 +0.00000E+00*p +0.00000E+00*p**2 +0.00000E+00*p**3
k-effective= 1.00197E+00 + or - 1.73659E-03 the corresponding geometry follows;
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23864
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.59627E-02 1.11926E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.98136E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
based on the preceding data, the best estimate of the parameter is -4.37073E-02
the mixing table corresponding to this parameter follows:
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23864
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.59627E-02 1.11926E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.98136E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
****************************************************************************************************
****************************************************************************************************h]h/X
******************* search pass 1 keff= 1.02599E+00 + or - 1.98346E-03 ******************
the parameter was 0.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 6.69203E-01 + or - 1.55844E-03 ******************
the parameter was -6.00000E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 1.00197E+00 + or - 1.73659E-03 ******************
the parameter was -4.37073E-02
10x10x10 array - concentration search
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 3 the parameter was -4.37073E-02
the equation used in the search was:
k-eff = +0.00000E+00 +0.00000E+00*p +0.00000E+00*p**2 +0.00000E+00*p**3
k-effective= 1.00197E+00 + or - 1.73659E-03 the corresponding geometry follows;
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23864
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.59627E-02 1.11926E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.98136E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
based on the preceding data, the best estimate of the parameter is -4.37073E-02
the mixing table corresponding to this parameter follows:
10x10x10 array - concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 19.050
nuclide atom-dens. wgt. frac. za awt nuclide title
1092235 4.39277E-02 9.00000E-01 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 4.81921E-03 1.00000E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3 02/13/92
mixture = 2 density(g/cc) = 0.23864
nuclide atom-dens. wgt. frac. za awt nuclide title
2001001 1.59627E-02 1.11926E-01 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
2008016 7.98136E-03 8.88074E-01 8016 15.9904 8O 16 from version 6 evaluation
****************************************************************************************************
****************************************************************************************************}(hhh j<ubah}(h]h]h]h]h]jjuhjh!jghM(
h jihhubeh}(h]id27ah]h]h]1array of spheres in h2o — search on h2o densityah]uhh#h jhhh!jghMjmKubh$)}(hhh](h))}(h`UO\ :sub:`2`\ F\ :sub:`2` Solution Tank — Critical Search on UO\ :sub:`2`\ F\ :sub:`2` Densityh](h/UO }(hUO\ h jUhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j^ubah}(h]h]h]h]h]uhjh jUubh/ F }(h\ F\ h jUhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jqubah}(h]h]h]h]h]uhjh jUubh/* Solution Tank — Critical Search on UO }(h* Solution Tank — Critical Search on UO\ h jUhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jUubh/ F }(hjph jUubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jUubh/ Density}(h Densityh jUhhh!NhNubeh}(h]h]h]h]h]uhh(h jRhhh!jghM`
ubh;)}(hXeConsider a large spherical tank partially filled with
UO\ :sub:`2`\ F\ :sub:`2` solution. The tank has a radius of 34.6 cm and
is filled with solution to a height of 30.0 cm above the midpoint. The
tank is composed of a 0.759 cm thick Al shell. The
UO\ :sub:`2`\ F\ :sub:`2` solution is composed of three standard
compositions: UO2F2, HF acid, and H2O. The code combines these using a
set algorithm. This may or may not produce a solution at the desired
density. If the density of the solution is known it should be entered.
Also, extra acid can be added to the solution by specifying a non-zero
acid molarity.h](h/:Consider a large spherical tank partially filled with
UO }(h:Consider a large spherical tank partially filled with
UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ F }(h\ F\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jˣubah}(h]h]h]h]h]uhjh jubh/ solution. The tank has a radius of 34.6 cm and
is filled with solution to a height of 30.0 cm above the midpoint. The
tank is composed of a 0.759 cm thick Al shell. The
UO }(h solution. The tank has a radius of 34.6 cm and
is filled with solution to a height of 30.0 cm above the midpoint. The
tank is composed of a 0.759 cm thick Al shell. The
UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jޣubah}(h]h]h]h]h]uhjh jubh/ F }(hjʣh jubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/XP solution is composed of three standard
compositions: UO2F2, HF acid, and H2O. The code combines these using a
set algorithm. This may or may not produce a solution at the desired
density. If the density of the solution is known it should be entered.
Also, extra acid can be added to the solution by specifying a non-zero
acid molarity.}(hXP solution is composed of three standard
compositions: UO2F2, HF acid, and H2O. The code combines these using a
set algorithm. This may or may not produce a solution at the desired
density. If the density of the solution is known it should be entered.
Also, extra acid can be added to the solution by specifying a non-zero
acid molarity.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMb
h jRhhubh;)}(hXA critical concentration search is performed on the water yielding
system *k*\ :sub:`eff` = 1.0 for various densities of UO\ :sub:`2`\ F\ :sub:`2`
in the solution. In the MORE search data, MIX=1 and SCNAME=UO2F2 specify
that the UO\ :sub:`2`\ F\ :sub:`2` component of the mixture 1 solution
is to be altered during the search. The code calculates the density of
the solution. The initial uranium fuel density is 300 gm/liter. The
maximum allowed uranium density is 600 gm/liter. The minimum allowed
uranium density is 150 gm/liter.h](h/JA critical concentration search is performed on the water yielding
system }(hJA critical concentration search is performed on the water yielding
system h j hhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh j ubh/ }(h\ h j hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j%ubah}(h]h]h]h]h]uhjh j ubh/& = 1.0 for various densities of UO }(h& = 1.0 for various densities of UO\ h j hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j8ubah}(h]h]h]h]h]uhjh j ubh/ F }(h\ F\ h j hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jKubah}(h]h]h]h]h]uhjh j ubh/W
in the solution. In the MORE search data, MIX=1 and SCNAME=UO2F2 specify
that the UO }(hW
in the solution. In the MORE search data, MIX=1 and SCNAME=UO2F2 specify
that the UO\ h j hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j^ubah}(h]h]h]h]h]uhjh j ubh/ F }(hjJh j ubj)}(h:sub:`2`h]h/2}(hhh jpubah}(h]h]h]h]h]uhjh j ubh/X component of the mixture 1 solution
is to be altered during the search. The code calculates the density of
the solution. The initial uranium fuel density is 300 gm/liter. The
maximum allowed uranium density is 600 gm/liter. The minimum allowed
uranium density is 150 gm/liter.}(hX component of the mixture 1 solution
is to be altered during the search. The code calculates the density of
the solution. The initial uranium fuel density is 300 gm/liter. The
maximum allowed uranium density is 600 gm/liter. The minimum allowed
uranium density is 150 gm/liter.h j hhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMm
h jRhhubh;)}(h2The maximum constraint is calculated according to:h]h/2The maximum constraint is calculated according to:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jghMv
h jRhhubj
)}(hhh]h;)}(h+CON= (600/300 − 1)/1.0 = 1.0h]h/+CON= (600/300 − 1)/1.0 = 1.0}(hjh jubah}(h]h]h]h]h]uhh:h!jghMx
h jubah}(h]h]h]h]h]uhj h jRhhh!jghNubh;)}(h2The minimum constraint is calculated according to:h]h/2The minimum constraint is calculated according to:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jghMz
h jRhhubj
)}(hhh]h;)}(h$−CON= (150/300 − 1)/1.0 = −0.5h]h/$−CON= (150/300 − 1)/1.0 = −0.5}(hjh jubah}(h]h]h]h]h]uhh:h!jghM|
h jubah}(h]h]h]h]h]uhj h jRhhh!jghNubh;)}(hAThe search data and final search results for this problem follow:h]h/AThe search data and final search results for this problem follow:}(hjդh jӤhhh!NhNubah}(h]h]h]h]h]uhh:h!jghM~
h jRhhubj)}(hX=CSAS5S
SOLUTION TANK - CRITICAL CONCENTRATION SEARCH
V7-238
READ COMP
SOLNUO2F2 1 300 0 1 300.0 92235 4.89 92238 95.09 92234 0.02 END
AL 2 1.0 300.0 END
END COMP
READ GEOM
HEMISPHE-Z 1 1 34.6 CHORD 30.
SPHERE 0 1 34.6
SPHERE 2 1 34.759
END GEOM
END DATA
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=1 SCNAME=UO2F2 FACTOR=1.0
-CON=-0.5 +CON=1.0
END SEARCH
ENDh]h/X=CSAS5S
SOLUTION TANK - CRITICAL CONCENTRATION SEARCH
V7-238
READ COMP
SOLNUO2F2 1 300 0 1 300.0 92235 4.89 92238 95.09 92234 0.02 END
AL 2 1.0 300.0 END
END COMP
READ GEOM
HEMISPHE-Z 1 1 34.6 CHORD 30.
SPHERE 0 1 34.6
SPHERE 2 1 34.759
END GEOM
END DATA
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=1 SCNAME=UO2F2 FACTOR=1.0
-CON=-0.5 +CON=1.0
END SEARCH
END}(hhh jubah}(h]h]h]h]h]jjuhjh!jghM
h jRhhubj)}(hX3 ******************* search pass 1 keff= 8.31461E-01 + or - 1.14626E-03 ******************
the parameter was 0.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 1.05426E+00 + or - 1.63141E-03 ******************
the parameter was 1.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 1.01773E+00 + or - 1.42881E-03 ******************
the parameter was 7.56451E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 4 keff= 9.97887E-01 + or - 1.42235E-03 ******************
the parameter was 6.59454E-01
solution tank - critical concentration search
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 4 the parameter was 6.59454E-01
the equation used in the search was:
k-eff = +8.31461E-01 +2.45656E-01*p +7.41484E-02*p**2 -9.70021E-02*p**3
k-effective= 9.97887E-01 + or - 1.42235E-03 the corresponding geometry follows;
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5960
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.36618E-02 6.67438E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.43513E-02 5.71507E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.52040E-03 4.98199E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars mod3
12/16/88
1092234 2.56198E-07 6.23860E-05 92234 234.0405 92U234 BNL HEDL+EVALJUL78 DIVADEENAM MOD3
01/10/91
1092235 6.23730E-05 1.52534E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.19757E-03 2.96614E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
based on the preceding data, the best estimate of the parameter is 6.69249E-01
the mixing table corresponding to this parameter follows:
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5998
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.36618E-02 6.65852E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.43662E-02 5.70395E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.53528E-03 4.99948E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars mod3
12/16/88
1092234 2.57710E-07 6.26050E-05 92234 234.0405 92U 234 BNL HEDL+EVALJUL78 DIVADEENAM MOD3
01/10/91
1092235 6.27412E-05 1.53069E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.20464E-03 2.97655E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
****************************************************************************************************
****************************************************************************************************h]h/X3 ******************* search pass 1 keff= 8.31461E-01 + or - 1.14626E-03 ******************
the parameter was 0.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 2 keff= 1.05426E+00 + or - 1.63141E-03 ******************
the parameter was 1.00000E+00
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 3 keff= 1.01773E+00 + or - 1.42881E-03 ******************
the parameter was 7.56451E-01
***** modified keno v data has been rewritten on unit 95 *****
******************* search pass 4 keff= 9.97887E-01 + or - 1.42235E-03 ******************
the parameter was 6.59454E-01
solution tank - critical concentration search
****************************************************************************************************
****************************************************************************************************
convergence was achieved on pass 4 the parameter was 6.59454E-01
the equation used in the search was:
k-eff = +8.31461E-01 +2.45656E-01*p +7.41484E-02*p**2 -9.70021E-02*p**3
k-effective= 9.97887E-01 + or - 1.42235E-03 the corresponding geometry follows;
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5960
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.36618E-02 6.67438E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.43513E-02 5.71507E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.52040E-03 4.98199E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars mod3
12/16/88
1092234 2.56198E-07 6.23860E-05 92234 234.0405 92U234 BNL HEDL+EVALJUL78 DIVADEENAM MOD3
01/10/91
1092235 6.23730E-05 1.52534E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.19757E-03 2.96614E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
based on the preceding data, the best estimate of the parameter is 6.69249E-01
the mixing table corresponding to this parameter follows:
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5998
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.36618E-02 6.65852E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.43662E-02 5.70395E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.53528E-03 4.99948E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars mod3
12/16/88
1092234 2.57710E-07 6.26050E-05 92234 234.0405 92U 234 BNL HEDL+EVALJUL78 DIVADEENAM MOD3
01/10/91
1092235 6.27412E-05 1.53069E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.20464E-03 2.97655E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
****************************************************************************************************
****************************************************************************************************}(hhh jubah}(h]h]h]h]h]jjuhjh!jghM
h jRhhubh;)}(hX`The final solution for this search contains 500 gm/liter of uranium. The
search, however, did not change the amount of acid or water in the
solution. To get a better estimation of the solution density and
*k*\ :sub:`eff` for this concentration of uranium the problem should be run
again with an initial uranium density of 500 gm/liter as shown below.h](h/The final solution for this search contains 500 gm/liter of uranium. The
search, however, did not change the amount of acid or water in the
solution. To get a better estimation of the solution density and
}(hThe final solution for this search contains 500 gm/liter of uranium. The
search, however, did not change the amount of acid or water in the
solution. To get a better estimation of the solution density and
h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/ for this concentration of uranium the problem should be run
again with an initial uranium density of 500 gm/liter as shown below.}(h for this concentration of uranium the problem should be run
again with an initial uranium density of 500 gm/liter as shown below.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghM
h jRhhubeh}(h]4uo2f2-solution-tank-critical-search-on-uo2f2-densityah]h]8uo2f2 solution tank — critical search on uo2f2 densityah]h]uhh#h jhhh!jghM`
ubh$)}(hhh](h))}(hgUO\ :sub:`2`\ F\ :sub:`2` Solution Tank — Critical Search on UO\ :sub:`2`\ F\ :sub:`2` Density, Checkh](h/UO }(hUO\ h j=hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jFubah}(h]h]h]h]h]uhjh j=ubh/ F }(h\ F\ h j=hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jYubah}(h]h]h]h]h]uhjh j=ubh/* Solution Tank — Critical Search on UO }(h* Solution Tank — Critical Search on UO\ h j=hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jlubah}(h]h]h]h]h]uhjh j=ubh/ F }(hjXh j=ubj)}(h:sub:`2`h]h/2}(hhh j~ubah}(h]h]h]h]h]uhjh j=ubh/ Density, Check}(h Density, Checkh j=hhh!NhNubeh}(h]h]h]h]h]uhh(h j:hhh!jghM
ubh;)}(hXNThis is the same UO\ :sub:`2`\ F\ :sub:`2` solution tank problem
examined above except the initial uranium density is 500 gm/liter. This
problem is run again so the code will calculate water and acid densities
associated with this density of uranium. The search data has also been
modified to account for the new density of uranium.h](h/This is the same UO }(hThis is the same UO\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/ F }(h\ F\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh jubh/X$ solution tank problem
examined above except the initial uranium density is 500 gm/liter. This
problem is run again so the code will calculate water and acid densities
associated with this density of uranium. The search data has also been
modified to account for the new density of uranium.}(hX$ solution tank problem
examined above except the initial uranium density is 500 gm/liter. This
problem is run again so the code will calculate water and acid densities
associated with this density of uranium. The search data has also been
modified to account for the new density of uranium.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghM
h j:hhubh;)}(hXA critical concentration search is performed on the water yielding
system *k*\ :sub:`eff` = 1.0 for various densities of UO\ :sub:`2`\ F\ :sub:`2`
in the solution. In the MORE search data, MIX=1 and SCNAME=UO2F2 specify
that the UO\ :sub:`2`\ F\ :sub:`2` component of the mixture 1 solution
is to be altered during the search. The code calculates the density of
the solution. The initial uranium fuel density is 500 gm/liter. The
maximum allowed uranium density is 600 gm/liter. The minimum allowed
uranium density is 400 gm/liter.h](h/JA critical concentration search is performed on the water yielding
system }(hJA critical concentration search is performed on the water yielding
system h j̥hhh!NhNubh)}(h*k*h]h/k}(hhh jեubah}(h]h]h]h]h]uhhh j̥ubh/ }(h\ h j̥hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh j̥ubh/& = 1.0 for various densities of UO }(h& = 1.0 for various densities of UO\ h j̥hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh j̥ubh/ F }(h\ F\ h j̥hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jubah}(h]h]h]h]h]uhjh j̥ubh/W
in the solution. In the MORE search data, MIX=1 and SCNAME=UO2F2 specify
that the UO }(hW
in the solution. In the MORE search data, MIX=1 and SCNAME=UO2F2 specify
that the UO\ h j̥hhh!NhNubj)}(h:sub:`2`h]h/2}(hhh j!ubah}(h]h]h]h]h]uhjh j̥ubh/ F }(hj
h j̥ubj)}(h:sub:`2`h]h/2}(hhh j3ubah}(h]h]h]h]h]uhjh j̥ubh/X component of the mixture 1 solution
is to be altered during the search. The code calculates the density of
the solution. The initial uranium fuel density is 500 gm/liter. The
maximum allowed uranium density is 600 gm/liter. The minimum allowed
uranium density is 400 gm/liter.}(hX component of the mixture 1 solution
is to be altered during the search. The code calculates the density of
the solution. The initial uranium fuel density is 500 gm/liter. The
maximum allowed uranium density is 600 gm/liter. The minimum allowed
uranium density is 400 gm/liter.h j̥hhh!NhNubeh}(h]h]h]h]h]uhh:h!jghM
h j:hhubh;)}(h2The maximum constraint is calculated according to:h]h/2The maximum constraint is calculated according to:}(hjNh jLhhh!NhNubah}(h]h]h]h]h]uhh:h!jghM
h j:hhubj
)}(hhh]h;)}(h+CON= (600/500 − 1)/1.0 = 0.2h]h/+CON= (600/500 − 1)/1.0 = 0.2}(hj_h j]ubah}(h]h]h]h]h]uhh:h!jghM
h jZubah}(h]h]h]h]h]uhj h j:hhh!jghNubh;)}(h2The minimum constraint is calculated according to:h]h/2The minimum constraint is calculated according to:}(hjsh jqhhh!NhNubah}(h]h]h]h]h]uhh:h!jghM
h j:hhubj
)}(hhh]h;)}(h$−CON= (400/500 − 1)/1.0 = −0.2h]h/$−CON= (400/500 − 1)/1.0 = −0.2}(hjh jubah}(h]h]h]h]h]uhh:h!jghM
h jubah}(h]h]h]h]h]uhj h j:hhh!jghNubh;)}(hAThe search data and final search results for this problem follow:h]h/AThe search data and final search results for this problem follow:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!jghMh j:hhubj)}(hX=csas5s
solution tank - critical concentration search
v7-238
read comp
solnuo2f2 1 500 0 1 300.0 92235 4.89 92238 95.09 92234 0.02 end
al 2 1.0 300.0 end
end comp
read geom
hemisphe-z 1 1 34.6 chord 30.
sphere 0 1 34.6
sphere 2 1 34.759
end geom
end data
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=1 SCNAME=uo2f2 factor=1.0
-CON=-0.2 +CON=0.2
END SEARCH
endh]h/X=csas5s
solution tank - critical concentration search
v7-238
read comp
solnuo2f2 1 500 0 1 300.0 92235 4.89 92238 95.09 92234 0.02 end
al 2 1.0 300.0 end
end comp
read geom
hemisphe-z 1 1 34.6 chord 30.
sphere 0 1 34.6
sphere 2 1 34.759
end geom
end data
READ SEARCH CRITICAL CONCENTRATION KEF=1.0 MORE
ALTER MIX=1 SCNAME=uo2f2 factor=1.0
-CON=-0.2 +CON=0.2
END SEARCH
end}(hhh jubah}(h]h]h]h]h]jjuhjh!jghMh j:hhubj)}(hXU
******************* search pass 1 keff= 9.99662E-01 + or - 1.40567E-03 ******************
the parameter was 0.00000E+00
solution tank - critical concentration search
****************************************************************************************************
convergence was achieved on pass 1 the parameter was 0.00000E+00
the equation used in the search was:
k-eff = +0.00000E+00 +0.00000E+00*p +0.00000E+00*p**2 +0.00000E+00*p**3
k-effective= 9.99662E-01 + or - 1.40567E-03 the corresponding geometry follows;
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5656
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.14448E-02 6.56680E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.32538E-02 5.63969E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.53136E-03 5.10061E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars
mod312/16/88
1092234 2.57312E-07 6.38714E-05 92234 234.0405 92U 234 BNL HEDL+EVALJUL78 DIVADEENAMMOD3
01/10/91
1092235 6.26441E-05 1.56166E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.20278E-03 3.03676E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
based on the preceding data, the best estimate of the parameter is 0.00000E+00
the mixing table corresponding to this parameter follows:
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5656
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.14448E-02 6.56680E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.32538E-02 5.63969E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.53136E-03 5.10061E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars mod3
12/16/88
1092234 2.57312E-07 6.38714E-05 92234 234.0405 92U 234 BNL HEDL+EVALJUL78 DIVADEENAM MOD3
01/10/91
1092235 6.26441E-05 1.56166E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.20278E-03 3.03676E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
****************************************************************************************************h]h/XU
******************* search pass 1 keff= 9.99662E-01 + or - 1.40567E-03 ******************
the parameter was 0.00000E+00
solution tank - critical concentration search
****************************************************************************************************
convergence was achieved on pass 1 the parameter was 0.00000E+00
the equation used in the search was:
k-eff = +0.00000E+00 +0.00000E+00*p +0.00000E+00*p**2 +0.00000E+00*p**3
k-effective= 9.99662E-01 + or - 1.40567E-03 the corresponding geometry follows;
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5656
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.14448E-02 6.56680E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.32538E-02 5.63969E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.53136E-03 5.10061E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars
mod312/16/88
1092234 2.57312E-07 6.38714E-05 92234 234.0405 92U 234 BNL HEDL+EVALJUL78 DIVADEENAMMOD3
01/10/91
1092235 6.26441E-05 1.56166E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.20278E-03 3.03676E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
based on the preceding data, the best estimate of the parameter is 0.00000E+00
the mixing table corresponding to this parameter follows:
solution tank - critical concentration search
mixing table
number of scattering angles = 2
cross section message threshold =5.7E-02
mixture = 1 density(g/cc) = 1.5656
nuclide atom-dens. wgt. frac. za awt nuclide title
1001001 6.14448E-02 6.56680E-02 1001 1.0077 hydrogen in water 1301/1002 mod1 11/23/92
1008016 3.32538E-02 5.63969E-01 8016 15.9904 8O 16 from version 6 evaluation
1009019 2.53136E-03 5.10061E-02 9019 18.9982 9f 19 ornl evaljul74 c.y.fu d.c.lars mod3
12/16/88
1092234 2.57312E-07 6.38714E-05 92234 234.0405 92U 234 BNL HEDL+EVALJUL78 DIVADEENAM MOD3
01/10/91
1092235 6.26441E-05 1.56166E-02 92235 235.0441 92u 235 bnl evalapr77 m.r.bhat mod3 02/28/89
1092238 1.20278E-03 3.03676E-01 92238 238.0510 92U 238 ANL+ EVALJUN77 E.PENNINGTON MOD3
02/13/92
mixture = 2 density(g/cc) = 2.7020
nuclide atom-dens. wgt. frac. za awt nuclide title
2013027 6.03066E-02 1.00000E+00 13027 26.9818 13al 270lasl evaldec73 p.g. young d.g mod1
11/29/88
****************************************************************************************************}(hhh jubah}(h]h]h]h]h]jjuhjh!jghMh j:hhubh;)}(hXThis problem converged on the first pass, so the amount of uranium, HF
acid, and water in the solution were reasonably good estimates. For this
problem the HF acid and H\ :sub:`2`\ O only changed marginally and,
therefore, had very little effect on the system *k*\ :sub:`eff`. This is not
always the case; therefore if a search is being done on a solution, the
problem should always be rerun with the final search densities.h](h/This problem converged on the first pass, so the amount of uranium, HF
acid, and water in the solution were reasonably good estimates. For this
problem the HF acid and H }(hThis problem converged on the first pass, so the amount of uranium, HF
acid, and water in the solution were reasonably good estimates. For this
problem the HF acid and H\ h jhhh!NhNubj)}(h:sub:`2`h]h/2}(hhh jɦubah}(h]h]h]h]h]uhjh jubh/Q O only changed marginally and,
therefore, had very little effect on the system }(hQ\ O only changed marginally and,
therefore, had very little effect on the system h jhhh!NhNubh)}(h*k*h]h/k}(hhh jܦubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/. This is not
always the case; therefore if a search is being done on a solution, the
problem should always be rerun with the final search densities.}(h. This is not
always the case; therefore if a search is being done on a solution, the
problem should always be rerun with the final search densities.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!jghMWh j:hhubeh}(h]:uo2f2-solution-tank-critical-search-on-uo2f2-density-checkah]h]?uo2f2 solution tank — critical search on uo2f2 density, checkah]h]uhh#h jhhh!jghM
ubjVeh}(h]critical-concentration-searchah]h]critical concentration searchah]h]uhh#h h$)}(hhh](h))}(hXCSAS5: Control Module For Enhanced Criticality Safety Analysis Sequences With KENO V.ah]h/XCSAS5: Control Module For Enhanced Criticality Safety Analysis Sequences With KENO V.a}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh! CSAS5.rsthKubh;)}(hc*L. M. Petrie, K. B. Bekar, S. Goluoglu,*\ :sup:`\*` *D. F. Hollenbach,*\ :sup:`\*` *N. F. Landers*h](h)}(h)*L. M. Petrie, K. B. Bekar, S. Goluoglu,*h]h/'L. M. Petrie, K. B. Bekar, S. Goluoglu,}(hhh j.ubah}(h]h]h]h]h]uhhh j*ubh/ }(h\ h j*hhh!NhNubj)}(h :sup:`\*`h]h/*}(hhh jAubah}(h]h]h]h]h]uhjh j*ubh/ }(hjTh j*hhh!NhNubh)}(h*D. F. Hollenbach,*h]h/D. F. Hollenbach,}(hhh jSubah}(h]h]h]h]h]uhhh j*ubh/ }(hj@h j*ubj)}(h :sup:`\*`h]h/*}(hhh jeubah}(h]h]h]h]h]uhjh j*ubh/ }(hjTh j*ubh)}(h*N. F. Landers*h]h/
N. F. Landers}(hhh jwubah}(h]h]h]h]h]uhhh j*ubeh}(h]h]h]h]h]uhh:h!j)hKh jhhubh;)}(hXwThe **C**\ riticality **S**\ afety **A**\ nalysis **S**\ equences with
KENO V.a (CSAS5) provides reliable and efficient means of performing
*k*\ :sub:`eff` calculations for systems that are routinely encountered in
engineering practice. In the multigroup calculation mode, CSAS5 uses
XSProc to process the cross sections for temperature corrections and
problem-dependent resonance self-shielding and calculates the *k*\ :sub:`eff`
of a three-dimensional (3-D) system model. If the continuous energy
calculation mode is selected no resonance processing is needed and the
continuous energy cross sections are used directly in KENO V.a, with
temperature corrections provided as the cross sections are loaded. The
geometric modeling capabilities available in KENO V.a coupled with the
automated cross-section processing within the control sequences allow
complex, 3-D systems to be easily analyzed. A search capability is
achieved by repeatedly activating the control module MODIFY, to alter
either the system dimensions or densities, and the functional module
KENO V.a to calculate the *k*\ :sub:`eff` for the modified dimensions or
densities.h](h/The }(hThe h jhhh!NhNubhA)}(h**C**h]h/C}(hhh jubah}(h]h]h]h]h]uhh@h jubh/
riticality }(h
\ riticality h jhhh!NhNubhA)}(h**S**h]h/S}(hhh jubah}(h]h]h]h]h]uhh@h jubh/ afety }(h\ afety h jhhh!NhNubhA)}(h**A**h]h/A}(hhh jubah}(h]h]h]h]h]uhh@h jubh/
nalysis }(h
\ nalysis h jhhh!NhNubhA)}(h**S**h]h/S}(hhh jͧubah}(h]h]h]h]h]uhh@h jubh/U equences with
KENO V.a (CSAS5) provides reliable and efficient means of performing
}(hU\ equences with
KENO V.a (CSAS5) provides reliable and efficient means of performing
h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/X calculations for systems that are routinely encountered in
engineering practice. In the multigroup calculation mode, CSAS5 uses
XSProc to process the cross sections for temperature corrections and
problem-dependent resonance self-shielding and calculates the }(hX calculations for systems that are routinely encountered in
engineering practice. In the multigroup calculation mode, CSAS5 uses
XSProc to process the cross sections for temperature corrections and
problem-dependent resonance self-shielding and calculates the h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/X
of a three-dimensional (3-D) system model. If the continuous energy
calculation mode is selected no resonance processing is needed and the
continuous energy cross sections are used directly in KENO V.a, with
temperature corrections provided as the cross sections are loaded. The
geometric modeling capabilities available in KENO V.a coupled with the
automated cross-section processing within the control sequences allow
complex, 3-D systems to be easily analyzed. A search capability is
achieved by repeatedly activating the control module MODIFY, to alter
either the system dimensions or densities, and the functional module
KENO V.a to calculate the }(hX
of a three-dimensional (3-D) system model. If the continuous energy
calculation mode is selected no resonance processing is needed and the
continuous energy cross sections are used directly in KENO V.a, with
temperature corrections provided as the cross sections are loaded. The
geometric modeling capabilities available in KENO V.a coupled with the
automated cross-section processing within the control sequences allow
complex, 3-D systems to be easily analyzed. A search capability is
achieved by repeatedly activating the control module MODIFY, to alter
either the system dimensions or densities, and the functional module
KENO V.a to calculate the h jhhh!NhNubh)}(h*k*h]h/k}(hhh j,ubah}(h]h]h]h]h]uhhh jubh/ }(hjh jubj)}(h
:sub:`eff`h]h/eff}(hhh j>ubah}(h]h]h]h]h]uhjh jubh/* for the modified dimensions or
densities.}(h* for the modified dimensions or
densities.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hK h jhhubh;)}(h.\*Formerly with Oak Ridge National Laboratory.h]h/.*Formerly with Oak Ridge National Laboratory.}(h.\*Formerly with Oak Ridge National Laboratory.h jWhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hKh jhhubh$)}(hhh](h))}(hAcknowledgmentsh]h/Acknowledgments}(hjkh jihhh!NhNubah}(h]h]h]h]h]uhh(h jfhhh!j)hKubh;)}(hXCSAS5 and its related Criticality Safety Analysis Sequences are based on the old CSAS2 control
module (no longer in SCALE) and the KENO V.a functional module described in the KENO V.a chapter.
Therefore, special acknowledgment is made to J. A. Bucholz, R. M. Westfall, and J. R. Knight who developed CSAS2.
G. E. Whitesides is acknowledged for his contributions through early versions of KENO.
Appreciation is expressed to C. V. Parks and S. M. Bowman for their guidance in developing CSAS5.h]h/XCSAS5 and its related Criticality Safety Analysis Sequences are based on the old CSAS2 control
module (no longer in SCALE) and the KENO V.a functional module described in the KENO V.a chapter.
Therefore, special acknowledgment is made to J. A. Bucholz, R. M. Westfall, and J. R. Knight who developed CSAS2.
G. E. Whitesides is acknowledged for his contributions through early versions of KENO.
Appreciation is expressed to C. V. Parks and S. M. Bowman for their guidance in developing CSAS5.}(hjyh jwhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hK h jfhhubh;)}(hqSpecial appreciation is expressed to S. J. Poarch and S. Y. Walker for their efforts in formatting this document.h]h/qSpecial appreciation is expressed to S. J. Poarch and S. Y. Walker for their efforts in formatting this document.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hK&h jfhhubh)}(h.. _2-1:h]h}(h]h]h]h]h]hid10uhh
hKh jfhhh!j)ubeh}(h]acknowledgmentsah]h]acknowledgmentsah]h]uhh#h jhhh!j)hKubh$)}(hhh](h))}(hIntroductionh]h/Introduction}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hK+ubh;)}(hX
Criticality Safety Analysis Sequence with KENO V.a (CSAS5) provides
reliable and efficient means of performing *k*\ :sub:`eff` calculations for
systems that are routinely encountered in engineering practice,
especially in the calculation of *k*\ :sub:`eff` of three-dimensional (3-D)
system models. CSAS5 implements XSProc to process material input and
provide a temperature and resonance-corrected cross-section library
based on the physical characteristics of the problem being analyzed. If
a continuous energy cross-section library is specified, no resonance
processing is needed and the continuous energy cross sections are used
directly in KENO V.a, with temperature corrections provided as the cross
sections are loaded. A search capability is available to find a desired
values of *k*\ :sub:`eff` as a function of dimensions or densities. The two
basic search options offered are (1) an optimum search seeking a maximum
or minimum value of *k*\ :sub:`eff` and (2) a critical search seeking a fixed
value of *k*\ :sub:`eff`.h](h/pCriticality Safety Analysis Sequence with KENO V.a (CSAS5) provides
reliable and efficient means of performing }(hpCriticality Safety Analysis Sequence with KENO V.a (CSAS5) provides
reliable and efficient means of performing h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jӨubah}(h]h]h]h]h]uhjh jubh/s calculations for
systems that are routinely encountered in engineering practice,
especially in the calculation of }(hs calculations for
systems that are routinely encountered in engineering practice,
especially in the calculation of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/X of three-dimensional (3-D)
system models. CSAS5 implements XSProc to process material input and
provide a temperature and resonance-corrected cross-section library
based on the physical characteristics of the problem being analyzed. If
a continuous energy cross-section library is specified, no resonance
processing is needed and the continuous energy cross sections are used
directly in KENO V.a, with temperature corrections provided as the cross
sections are loaded. A search capability is available to find a desired
values of }(hX of three-dimensional (3-D)
system models. CSAS5 implements XSProc to process material input and
provide a temperature and resonance-corrected cross-section library
based on the physical characteristics of the problem being analyzed. If
a continuous energy cross-section library is specified, no resonance
processing is needed and the continuous energy cross sections are used
directly in KENO V.a, with temperature corrections provided as the cross
sections are loaded. A search capability is available to find a desired
values of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/ as a function of dimensions or densities. The two
basic search options offered are (1) an optimum search seeking a maximum
or minimum value of }(h as a function of dimensions or densities. The two
basic search options offered are (1) an optimum search seeking a maximum
or minimum value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh j2ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jEubah}(h]h]h]h]h]uhjh jubh/5 and (2) a critical search seeking a fixed
value of }(h5 and (2) a critical search seeking a fixed
value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jXubah}(h]h]h]h]h]uhhh jubh/ }(hjҨh jubj)}(h
:sub:`eff`h]h/eff}(hhh jjubah}(h]h]h]h]h]uhjh jubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hK-h jhhubh;)}(hAll the control sequences in the CSAS5 control module are listed in
:numref:`tab2-1` with the modules they invoke. The first four sequences are
subsets of the CSAS5 sequence.h](h/DAll the control sequences in the CSAS5 control module are listed in
}(hDAll the control sequences in the CSAS5 control module are listed in
h jhhh!NhNubh_)}(h:numref:`tab2-1`h]j)}(hjh]h/tab2-1}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-1uhh^h!j)hK=h jubh/Z with the modules they invoke. The first four sequences are
subsets of the CSAS5 sequence.}(hZ with the modules they invoke. The first four sequences are
subsets of the CSAS5 sequence.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hK=h jhhubh)}(h.. _tab2-1:h]h}(h]h]h]h]h]htab2-1uhh
hKh jhhh!j)ubj)}(hhh](h))}(h&CSAS5 sequences for criticality safetyh]h/&CSAS5 sequences for criticality safety}(hjƩh jĩubah}(h]h]h]h]h]uhh(h!j)hKBh jubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jҩubj$)}(hhh]h}(h]h]h]h]h]colwidthK#uhj#h jҩubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jҩubj$)}(hhh]h}(h]h]h]h]h]colwidthK
uhj#h jҩubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jҩubjs)}(hhh]j5)}(hhh](j:)}(hhh]h;)}(hControl sequenceh]h/Control sequence}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKFh j
ubah}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h;)}(hFunctionh]h/Function}(hj)h j'ubah}(h]h]h]h]h]uhh:h!j)hKFh j$ubah}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h;)}(hLFunctional modules
executed by the
control sequence
for multigroup librariesh]h/LFunctional modules
executed by the
control sequence
for multigroup libraries}(hj@h j>ubah}(h]h]h]h]h]uhh:h!j)hKFh j;ubah}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j
ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j
ubeh}(h]h]h]h]h]uhj4h jubah}(h]h]h]h]h]uhjrh jҩubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(hCSAS5h]h/CSAS5}(hj{h jyubah}(h]h]h]h]h]uhh:h!j)hKKh jvubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h;)}(h:math:`k_{eff}` (3-D)h](j)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jubah}(h]h]h]h]h]uhjh jubh/ (3-D)}(h (3-D)h jubeh}(h]h]h]h]h]uhh:h!j)hKKh jubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h;)}(hXSProch]h/XSProc}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKKh jubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h;)}(hKENO V.ah]h/KENO V.a}(hjϪh jͪubah}(h]h]h]h]h]uhh:h!j)hKKh jʪubah}(h]h]h]h]h]uhj9h jsubj:)}(hhh]h}(h]h]h]h]h]uhj9h jsubeh}(h]h]h]h]h]uhj4h jpubj5)}(hhh](j:)}(hhh]h;)}(hCSAS5Sh]h/CSAS5S}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h:math:`k_{eff}` (3-D) searchh](j)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jubah}(h]h]h]h]h]uhjh j
ubh/
(3-D) search}(h
(3-D) searchh j
ubeh}(h]h]h]h]h]uhh:h!j)hKMh j
ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hXSProch]h/XSProc}(hj5h j3ubah}(h]h]h]h]h]uhh:h!j)hKMh j0ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hKENO V.ah]h/KENO V.a}(hjLh jJubah}(h]h]h]h]h]uhh:h!j)hKMh jGubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hMODIFYh]h/MODIFY}(hjch jaubah}(h]h]h]h]h]uhh:h!j)hKMh j^ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jpubeh}(h]h]h]h]h]uhj/h jҩubeh}(h]h]h]h]h]colsKuhjh jubeh}(h](id73jeh]h]tab2-1ah]h]jcenteruhjh jhhh!j)hNj}jjsj}jjsubeh}(h](introductionjeh]h]2-1ah]jah]uhh#h jhhh!j)hK+jmKj}jjsj}jjsubh$)}(hhh](h))}(hSequence Capabilitiesh]h/Sequence Capabilities}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hKQubh;)}(hXzIn order to minimize human error, the SCALE data handling is automated
as much as possible. CSAS5 and many other SCALE sequences apply a
standardized procedure to provide appropriate number densities and
cross sections for the calculation. XSProc is responsible for reading
the standard composition data and other engineering-type specifications,
including volume fraction or percent theoretical density, temperature,
and isotopic distribution as well as the unit cell data. XSProc then
generates number densities and related information, prepares geometry
data for resonance self-shielding and flux-weighting cell calculations,
if needed, and (if needed) provides problem-dependent multigroup
cross-section processing. Sequences that execute KENO V.a include a
KENO V.a Data Processor to read and check the KENO V.a data. Sequences
that execute a search use a Search Data Processor to read and check the
search data. When the data checking has been completed, the control
sequence executes XSProc to prepare a resonance-corrected microscopic
cross-section library in the AMPX working library format if a multigroup
library has been selected.h]h/XzIn order to minimize human error, the SCALE data handling is automated
as much as possible. CSAS5 and many other SCALE sequences apply a
standardized procedure to provide appropriate number densities and
cross sections for the calculation. XSProc is responsible for reading
the standard composition data and other engineering-type specifications,
including volume fraction or percent theoretical density, temperature,
and isotopic distribution as well as the unit cell data. XSProc then
generates number densities and related information, prepares geometry
data for resonance self-shielding and flux-weighting cell calculations,
if needed, and (if needed) provides problem-dependent multigroup
cross-section processing. Sequences that execute KENO V.a include a
KENO V.a Data Processor to read and check the KENO V.a data. Sequences
that execute a search use a Search Data Processor to read and check the
search data. When the data checking has been completed, the control
sequence executes XSProc to prepare a resonance-corrected microscopic
cross-section library in the AMPX working library format if a multigroup
library has been selected.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hKSh jhhubh;)}(hXFor each unit cell specified as being cell-weighted, XSProc performs the
necessary calculations and produces a cell-weighted microscopic
cross-section library. KENO V.a may be executed to calculate the
*k*\ :sub:`eff` or neutron multiplication factor using the cross-section
library that was prepared by the control sequence. MODIFY may be invoked
to perform a search :cite:`lorek_improved_1979` by repeatedly altering the unit cell
(multigroup mode only) and KENO V.a data prior to executing the next
pass through the calculation. Cross sections are updated at the
beginning of each search pass with the modified data. If unit cell data
is altered as part of the search, i.e., pitch or material search, the
cross-sections are correctly processed with the updated data.h](h/For each unit cell specified as being cell-weighted, XSProc performs the
necessary calculations and produces a cell-weighted microscopic
cross-section library. KENO V.a may be executed to calculate the
}(hFor each unit cell specified as being cell-weighted, XSProc performs the
necessary calculations and produces a cell-weighted microscopic
cross-section library. KENO V.a may be executed to calculate the
h jhhh!NhNubh)}(h*k*h]h/k}(hhh jūubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jثubah}(h]h]h]h]h]uhjh jubh/ or neutron multiplication factor using the cross-section
library that was prepared by the control sequence. MODIFY may be invoked
to perform a search }(h or neutron multiplication factor using the cross-section
library that was prepared by the control sequence. MODIFY may be invoked
to perform a search h jhhh!NhNubh_)}(hlorek_improved_1979h]he)}(hjh]h/[lorek_improved_1979]}(hhh jubah}(h]h]h]h]h]uhhdh jubah}(h]id11ah]hwah]h]h] refdomainh|reftypeh~ reftargetjrefwarnsupport_smartquotesuhh^h!j)hKeh jhhubh/Xy by repeatedly altering the unit cell
(multigroup mode only) and KENO V.a data prior to executing the next
pass through the calculation. Cross sections are updated at the
beginning of each search pass with the modified data. If unit cell data
is altered as part of the search, i.e., pitch or material search, the
cross-sections are correctly processed with the updated data.}(hXy by repeatedly altering the unit cell
(multigroup mode only) and KENO V.a data prior to executing the next
pass through the calculation. Cross sections are updated at the
beginning of each search pass with the modified data. If unit cell data
is altered as part of the search, i.e., pitch or material search, the
cross-sections are correctly processed with the updated data.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hKeh jhhubh;)}(hXGThe search capability is implemented by the control module MODIFY. It
performs operations according to the specified search data to determine
(1) the maximum or minimum value of :math:`k_{eff}` as a function of pitch,
dimensions or densities or (2) the pitch, dimensions, or densities
corresponding to a specified value of :math:`k_{eff}`. An iterative procedure
is used, making use of all previous information to modify the dimensions
or densities to achieve the desired result. The procedures for
conducting optimum and critical searches are summarized in the following
sections.h](h/The search capability is implemented by the control module MODIFY. It
performs operations according to the specified search data to determine
(1) the maximum or minimum value of }(hThe search capability is implemented by the control module MODIFY. It
performs operations according to the specified search data to determine
(1) the maximum or minimum value of h jhhh!NhNubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jubah}(h]h]h]h]h]uhjh jubh/ as a function of pitch,
dimensions or densities or (2) the pitch, dimensions, or densities
corresponding to a specified value of }(h as a function of pitch,
dimensions or densities or (2) the pitch, dimensions, or densities
corresponding to a specified value of h jhhh!NhNubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh j/ubah}(h]h]h]h]h]uhjh jubh/. An iterative procedure
is used, making use of all previous information to modify the dimensions
or densities to achieve the desired result. The procedures for
conducting optimum and critical searches are summarized in the following
sections.}(h. An iterative procedure
is used, making use of all previous information to modify the dimensions
or densities to achieve the desired result. The procedures for
conducting optimum and critical searches are summarized in the following
sections.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hKqh jhhubh$)}(hhh](h))}(h Optimum (minimum/maximum) searchh]h/ Optimum (minimum/maximum) search}(hjMh jKhhh!NhNubah}(h]h]h]h]h]uhh(h jHhhh!j)hK|ubh;)}(hXBecause only an initial value of :math:`k_{eff}` and a set of boundary
constraints are available, four initial points are generated spanning
the range defined by the constraints. The search package identifies the
type of cubic equation [i.e., a cubic with no local extrema (type A) or
a cubic with two local extrema (type B)] and utilizes this knowledge in
determining the pitch, dimensions, or material densities corresponding
to the maximum (or minimum) value of :math:`k_{eff}`. The optimum search
procedure is summarized as follows:h](h/!Because only an initial value of }(h!Because only an initial value of h jYhhh!NhNubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jbubah}(h]h]h]h]h]uhjh jYubh/X and a set of boundary
constraints are available, four initial points are generated spanning
the range defined by the constraints. The search package identifies the
type of cubic equation [i.e., a cubic with no local extrema (type A) or
a cubic with two local extrema (type B)] and utilizes this knowledge in
determining the pitch, dimensions, or material densities corresponding
to the maximum (or minimum) value of }(hX and a set of boundary
constraints are available, four initial points are generated spanning
the range defined by the constraints. The search package identifies the
type of cubic equation [i.e., a cubic with no local extrema (type A) or
a cubic with two local extrema (type B)] and utilizes this knowledge in
determining the pitch, dimensions, or material densities corresponding
to the maximum (or minimum) value of h jYhhh!NhNubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh juubah}(h]h]h]h]h]uhjh jYubh/8. The optimum search
procedure is summarized as follows:}(h8. The optimum search
procedure is summarized as follows:h jYhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hKh jHhhubj
)}(hhh]j )}(hhh](j)}(h5Calculate :math:`k_{eff}` for the specified problem.
h]h;)}(h4Calculate :math:`k_{eff}` for the specified problem.h](h/
Calculate }(h
Calculate h jubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jubah}(h]h]h]h]h]uhjh jubh/ for the specified problem.}(h for the specified problem.h jubeh}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhjh jubj)}(h6Calculate :math:`k_{eff}` for the minimum constraint.
h]h;)}(h5Calculate :math:`k_{eff}` for the minimum constraint.h](h/
Calculate }(h
Calculate h jĬubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jͬubah}()h]h]h]h]h]uhjh jĬubh/ for the minimum constraint.}(h for the minimum constraint.h jĬubeh}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhjh jubj)}(h6Calculate :math:`k_{eff}` for the maximum constraint.
h]h;)}(h5Calculate :math:`k_{eff}` for the maximum constraint.h](h/
Calculate }(h
Calculate h jubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jubah}(h]h]h]h]h]uhjh jubh/ for the maximum constraint.}(h for the maximum constraint.h jubeh}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhjh jubj)}(hCalculate :math:`k_{eff}` for a fourth point that lies approximately
equidistant between the initial guess and the constraint that is
farthest from it.
h]h;)}(hCalculate :math:`k_{eff}` for a fourth point that lies approximately
equidistant between the initial guess and the constraint that is
farthest from it.h](h/
Calculate }(h
Calculate h jubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh j%ubah}(h]h]h]h]h]uhjh jubh/~ for a fourth point that lies approximately
equidistant between the initial guess and the constraint that is
farthest from it.}(h~ for a fourth point that lies approximately
equidistant between the initial guess and the constraint that is
farthest from it.h jubeh}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhjh jubj)}(hOUtilize a weighted least-squares fit to a cubic polynomial on the
data points.
h]h;)}(hNUtilize a weighted least-squares fit to a cubic polynomial on the
data points.h]h/NUtilize a weighted least-squares fit to a cubic polynomial on the
data points.}(hjJh jHubah}(h]h]h]h]h]uhh:h!j)hKh jDubah}(h]h]h]h]h]uhjh jubj)}(hBDetermine the type of cubic. For a type A cubic, go to step 11.
h]h;)}(hADetermine the type of cubic. For a type A cubic, go to step 11.h]h/ADetermine the type of cubic. For a type A cubic, go to step 11.}(hjbh j`ubah}(h]h]h]h]h]uhh:h!j)hKh j\ubah}(h]h]h]h]h]uhjh jubj)}(h6Take the first derivative of the least-squares cubic.
h]h;)}(h5Take the first derivative of the least-squares cubic.h]h/5Take the first derivative of the least-squares cubic.}(hjzh jxubah}(h]h]h]h]h]uhh:h!j)hKh jtubah}(h]h]h]h]h]uhjh jubj)}(h#Solve the quadratic for its roots.
h]h;)}(h"Solve the quadratic for its roots.h]h/"Solve the quadratic for its roots.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhjh jubj)}(hX+Take the second derivative of the least-squares cubic to determine
which root is the maximum (or minimum), and if it falls within
the constraints, use this root as the next guess. Otherwise,
convergence has been defined as occurring at the constraint with
the maximum (or minimum) :math:`k_{eff}`.
h]h;)}(hX*Take the second derivative of the least-squares cubic to determine
which root is the maximum (or minimum), and if it falls within
the constraints, use this root as the next guess. Otherwise,
convergence has been defined as occurring at the constraint with
the maximum (or minimum) :math:`k_{eff}`.h](h/XTake the second derivative of the least-squares cubic to determine
which root is the maximum (or minimum), and if it falls within
the constraints, use this root as the next guess. Otherwise,
convergence has been defined as occurring at the constraint with
the maximum (or minimum) }(hXTake the second derivative of the least-squares cubic to determine
which root is the maximum (or minimum), and if it falls within
the constraints, use this root as the next guess. Otherwise,
convergence has been defined as occurring at the constraint with
the maximum (or minimum) h jubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jubah}(h]h]h]h]h]uhjh jubh/.}(hjh jubeh}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhjh jubj)}(hCalculate the :math:`k_{eff}` corresponding to the next guess. Go to
step 5. Repeat this procedure until convergence is achieved.
h]h;)}(hCalculate the :math:`k_{eff}` corresponding to the next guess. Go to
step 5. Repeat this procedure until convergence is achieved.h](h/Calculate the }(hCalculate the h jӭubj)}(h:math:`k_{eff}`h]h/k_{eff}}(hhh jܭubah}(h]h]h]h]h]uhjh jӭubh/e corresponding to the next guess. Go to
step 5. Repeat this procedure until convergence is achieved.}(he corresponding to the next guess. Go to
step 5. Repeat this procedure until convergence is achieved.h jӭubeh}(h]h]h]h]h]uhh:h!j)hKh jϭubah}(h]h]h]h]h]uhjh jubj)}(hIf the cubic equation is a type A cubic, the optimum lies on one of
the boundaries. If the fit shows that the cubic is actually a
type B cubic, go to step 7 and continue.
h]h;)}(hIf the cubic equation is a type A cubic, the optimum lies on one of
the boundaries. If the fit shows that the cubic is actually a
type B cubic, go to step 7 and continue.h]h/If the cubic equation is a type A cubic, the optimum lies on one of
the boundaries. If the fit shows that the cubic is actually a
type B cubic, go to step 7 and continue.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhjh jubeh}(h]h]h]h]h]j j j hj juhj h jubah}(h]h]h]h]h]uhj h jHhhh!NhNubh;)}(hXConvergence is defined as occurring when a *k*\ :sub:`eff` has been calculated
for a point on the curve where the value of the curve is within epsilon
of the maximum (or minimum) of the curve. Additionally, the calculated
*k*\ :sub:`eff` must be within two standard deviations of the value of the
curve at that point. The search is terminated when convergence is
achieved, when the code determines there is no local maximum within the
constraints, or the maximum number of search iterations is reached.h](h/+Convergence is defined as occurring when a }(h+Convergence is defined as occurring when a h jhhh!NhNubh)}(h*k*h]h/k}(hhh j(ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh j;ubah}(h]h]h]h]h]uhjh jubh/ has been calculated
for a point on the curve where the value of the curve is within epsilon
of the maximum (or minimum) of the curve. Additionally, the calculated
}(h has been calculated
for a point on the curve where the value of the curve is within epsilon
of the maximum (or minimum) of the curve. Additionally, the calculated
h jhhh!NhNubh)}(h*k*h]h/k}(hhh jNubah}(h]h]h]h]h]uhhh jubh/ }(hj:h jubj)}(h
:sub:`eff`h]h/eff}(hhh j`ubah}(h]h]h]h]h]uhjh jubh/X must be within two standard deviations of the value of the
curve at that point. The search is terminated when convergence is
achieved, when the code determines there is no local maximum within the
constraints, or the maximum number of search iterations is reached.}(hX must be within two standard deviations of the value of the
curve at that point. The search is terminated when convergence is
achieved, when the code determines there is no local maximum within the
constraints, or the maximum number of search iterations is reached.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hKh jHhhubh note)}(hXAt the beginning of each search pass, the cross sections are
updated using the updated values of pitch, dimensions, or material
densities. Also, the unit or material being modified can be directly
tied to a unit cell, so that unit cell is updated during the search.
Therefore, the final result should be consistent with the results
obtained by running a non-search problem using the data from the last
pass.h]h;)}(hXAt the beginning of each search pass, the cross sections are
updated using the updated values of pitch, dimensions, or material
densities. Also, the unit or material being modified can be directly
tied to a unit cell, so that unit cell is updated during the search.
Therefore, the final result should be consistent with the results
obtained by running a non-search problem using the data from the last
pass.h]h/XAt the beginning of each search pass, the cross sections are
updated using the updated values of pitch, dimensions, or material
densities. Also, the unit or material being modified can be directly
tied to a unit cell, so that unit cell is updated during the search.
Therefore, the final result should be consistent with the results
obtained by running a non-search problem using the data from the last
pass.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKh j{ubah}(h]h]h]h]h]uhjyh jHhhh!j)hNubeh}(h]optimum-minimum-maximum-searchah]h] optimum (minimum/maximum) searchah]h]uhh#h jhhh!j)hK|ubh$)}(hhh](h))}(hCritical searchh]h/Critical search}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hKubh;)}(hXfThe critical search option searches for the pitch, dimensions, or
material densities corresponding to a specified value of *k*\ :sub:`eff`. If
the calculated value of *k*\ :sub:`eff` is within the specified search
tolerance (EPS) of the desired *k*\ :sub:`eff`, the search is considered to be
complete. The critical search procedure is summarized as follows:h](h/{The critical search option searches for the pitch, dimensions, or
material densities corresponding to a specified value of }(h{The critical search option searches for the pitch, dimensions, or
material densities corresponding to a specified value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jȮubah}(h]h]h]h]h]uhjh jubh/. If
the calculated value of }(h. If
the calculated value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jۮubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/? is within the specified search
tolerance (EPS) of the desired }(h? is within the specified search
tolerance (EPS) of the desired h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(hjǮh jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/b, the search is considered to be
complete. The critical search procedure is summarized as follows:}(hb, the search is considered to be
complete. The critical search procedure is summarized as follows:h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hKh jhhubj
)}(hhh](h;)}(h1. Calculate *k*\ :sub:`eff` for the specified problem. If it is within EPS of
the specified *k*\ :sub:`eff`, convergence has been achieved.h](h/
1. Calculate }(h
1. Calculate h j/ubh)}(h*k*h]h/k}(hhh j8ubah}(h]h]h]h]h]uhhh j/ubh/ }(h\ h j/ubj)}(h
:sub:`eff`h]h/eff}(hhh jKubah}(h]h]h]h]h]uhjh j/ubh/A for the specified problem. If it is within EPS of
the specified }(hA for the specified problem. If it is within EPS of
the specified h j/ubh)}(h*k*h]h/k}(hhh j^ubah}(h]h]h]h]h]uhhh j/ubh/ }(hjJh j/ubj)}(h
:sub:`eff`h]h/eff}(hhh jpubah}(h]h]h]h]h]uhjh j/ubh/ , convergence has been achieved.}(h , convergence has been achieved.h j/ubeh}(h]h]h]h]h]uhh:h!j)hKh j,ubh;)}(hXb2. Calculate *k*\ :sub:`eff` for one of the constraints. If the specified
*k*\ :sub:`eff` of the system does not fall between the initial value and
the *k*\ :sub:`eff` of the constraint, calculate the *k*\ :sub:`eff` of the other
constraint. If the calculated *k*\ :sub:`eff` is within EPS of the specified
*k*\ :sub:`eff`, convergence has been achieved.h](h/
2. Calculate }(h
2. Calculate h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/. for one of the constraints. If the specified
}(h. for one of the constraints. If the specified
h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh j˯ubah}(h]h]h]h]h]uhjh jubh/? of the system does not fall between the initial value and
the }(h? of the system does not fall between the initial value and
the h jubh)}(h*k*h]h/k}(hhh jޯubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/" of the constraint, calculate the }(h" of the constraint, calculate the h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/, of the other
constraint. If the calculated }(h, of the other
constraint. If the calculated h jubh)}(h*k*h]h/k}(hhh j*ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh j=ubah}(h]h]h]h]h]uhjh jubh/ is within EPS of the specified
}(h is within EPS of the specified
h jubh)}(h*k*h]h/k}(hhh jPubah}(h]h]h]h]h]uhhh jubh/ }(hjh jubj)}(h
:sub:`eff`h]h/eff}(hhh jbubah}(h]h]h]h]h]uhjh jubh/ , convergence has been achieved.}(h , convergence has been achieved.h jubeh}(h]h]h]h]h]uhh:h!j)hKh j,ubh;)}(h3. Calculate *k*\ :sub:`eff` for a point chosen from a linear fit of the two
existing points closest to the specified *k*\ :sub:`eff`.h](h/
3. Calculate }(h
3. Calculate h j{ubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh j{ubh/ }(h\ h j{ubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh j{ubh/Z for a point chosen from a linear fit of the two
existing points closest to the specified }(hZ for a point chosen from a linear fit of the two
existing points closest to the specified h j{ubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh j{ubh/ }(hjh j{ubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh j{ubh/.}(hjh j{ubeh}(h]h]h]h]h]uhh:h!j)hKh j,ubh;)}(hX/4. Repeat step 3 until convergence has been achieved, the program
determines that the specified value lies outside the constraints, or
the maximum number of search iterations is reached. Convergence has
been achieved when the calculated \**k*\ :sub:`eff` is within EPS of the
specified *k*\ :sub:`eff`.h](h/4. Repeat step 3 until convergence has been achieved, the program
determines that the specified value lies outside the constraints, or
the maximum number of search iterations is reached. Convergence has
been achieved when the calculated **k* }(h4. Repeat step 3 until convergence has been achieved, the program
determines that the specified value lies outside the constraints, or
the maximum number of search iterations is reached. Convergence has
been achieved when the calculated \**k*\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jݰubah}(h]h]h]h]h]uhjh jubh/ is within EPS of the
specified }(h is within EPS of the
specified h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/.}(hjh jubeh}(h]h]h]h]h]uhh:h!j)hKh j,ubh;)}(hX5. If convergence is achieved, calculate *k*\ :sub:`eff` for a point determined
from fitting the previous points to a cubic and solving the cubic for
the point closest to the desired *k*\ :sub:`eff`. If all roots lie outside
the constraints, the problem is terminated and an appropriate message
is written. If the maximum number of iterations is reached without
the problem converging, the problem is terminated and an appropriate
message is written.h](h/)5. If convergence is achieved, calculate }(h)5. If convergence is achieved, calculate h jubh)}(h*k*h]h/k}(hhh j$ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh j7ubah}(h]h]h]h]h]uhjh jubh/ for a point determined
from fitting the previous points to a cubic and solving the cubic for
the point closest to the desired }(h for a point determined
from fitting the previous points to a cubic and solving the cubic for
the point closest to the desired h jubh)}(h*k*h]h/k}(hhh jJubah}(h]h]h]h]h]uhhh jubh/ }(hj6h jubj)}(h
:sub:`eff`h]h/eff}(hhh j\ubah}(h]h]h]h]h]uhjh jubh/. If all roots lie outside
the constraints, the problem is terminated and an appropriate message
is written. If the maximum number of iterations is reached without
the problem converging, the problem is terminated and an appropriate
message is written.}(h. If all roots lie outside
the constraints, the problem is terminated and an appropriate message
is written. If the maximum number of iterations is reached without
the problem converging, the problem is terminated and an appropriate
message is written.h jubeh}(h]h]h]h]h]uhh:h!j)hKh j,ubeh}(h]h]h]h]h]uhj h jhhh!j)hNubjz)}(hXAt the beginning of each search pass, the cross sections are
updated using the updated values of pitch, dimensions, or material
densities. Also, the unit or material being modified can be directly
tied to a unit cell, so that unit cell is updated during the search.
Therefore, the final result should be consistent with the results
obtained by running a non-search problem using the data from the last
pass.h]h;)}(hXAt the beginning of each search pass, the cross sections are
updated using the updated values of pitch, dimensions, or material
densities. Also, the unit or material being modified can be directly
tied to a unit cell, so that unit cell is updated during the search.
Therefore, the final result should be consistent with the results
obtained by running a non-search problem using the data from the last
pass.h]h/XAt the beginning of each search pass, the cross sections are
updated using the updated values of pitch, dimensions, or material
densities. Also, the unit or material being modified can be directly
tied to a unit cell, so that unit cell is updated during the search.
Therefore, the final result should be consistent with the results
obtained by running a non-search problem using the data from the last
pass.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKh j{ubah}(h]h]h]h]h]uhjyh jhhh!j)hNubeh}(h]critical-searchah]h]critical searchah]h]uhh#h jhhh!j)hKubh$)}(hhh](h))}(hMultigroup CSAS5 limitationsh]h/Multigroup CSAS5 limitations}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hKubh;)}(hXThe CSAS5 control module was developed to use simple input data and
prepare problem-dependent cross sections for use in calculating the
effective neutron multiplication factor of a 3-D system using KENO V.a.
An attempt was made to make the system as general as possible within the
constraints of the standardized methods chosen to be used in SCALE.
Standardized methods of data input were adopted to allow easy data entry
and for quality assurance purposes. Some of the limitations of the CSAS5
multigroup sequences are a result of using preprocessed multigroup
cross sections. Inherent limitations in multigroup CSAS5 calculations
are as follows:h]h/XThe CSAS5 control module was developed to use simple input data and
prepare problem-dependent cross sections for use in calculating the
effective neutron multiplication factor of a 3-D system using KENO V.a.
An attempt was made to make the system as general as possible within the
constraints of the standardized methods chosen to be used in SCALE.
Standardized methods of data input were adopted to allow easy data entry
and for quality assurance purposes. Some of the limitations of the CSAS5
multigroup sequences are a result of using preprocessed multigroup
cross sections. Inherent limitations in multigroup CSAS5 calculations
are as follows:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hKh jhhubj
)}(hhh]h;)}(hX1. Two-dimensional (2-D) effects such as fuel rods in assemblies where
some positions are filled with control rod guide tubes, burnable
poison rods and/or fuel rods of different enrichments. The
cross sections are processed as if the rods are in an infinite
lattice of identical rods. If the user inputs a Dancoff factor for
the cell (such as one computed by MCDancoff), XSProc can produce an
infinite lattice cell, which reproduces that Dancoff. This can
mitigate some two dimensional lattice effectsh]h/X1. Two-dimensional (2-D) effects such as fuel rods in assemblies where
some positions are filled with control rod guide tubes, burnable
poison rods and/or fuel rods of different enrichments. The
cross sections are processed as if the rods are in an infinite
lattice of identical rods. If the user inputs a Dancoff factor for
the cell (such as one computed by MCDancoff), XSProc can produce an
infinite lattice cell, which reproduces that Dancoff. This can
mitigate some two dimensional lattice effects}(hjh jubah}(h]h]h]h]h]uhh:h!j)hKh jubah}(h]h]h]h]h]uhj h jhhh!j)hNubeh}(h]multigroup-csas5-limitationsah]h]multigroup csas5 limitationsah]h]uhh#h jhhh!j)hKubh$)}(hhh](h))}(h#Continuous energy CSAS5 limitationsh]h/#Continuous energy CSAS5 limitations}(hjޱh jܱhhh!NhNubah}(h]h]h]h]h]uhh(h jٱhhh!j)hKubh;)}(hXWhen continuous energy KENO calculations are desired, none of the
resonance processing capabilities of XSProc are applicable or needed.
The continuous energy cross sections are directly used in KENO. An
existing multigroup input file can easily be converted to a continuous
energy input file by simply specifying the continuous energy library. In
this case, all cell data is ignored. However, the following limitations
exist:h]h/XWhen continuous energy KENO calculations are desired, none of the
resonance processing capabilities of XSProc are applicable or needed.
The continuous energy cross sections are directly used in KENO. An
existing multigroup input file can easily be converted to a continuous
energy input file by simply specifying the continuous energy library. In
this case, all cell data is ignored. However, the following limitations
exist:}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMh jٱhhubj
)}(hhh]j )}(hhh](j)}(hIf CELLMIX is defined in the cell data, the problem will not run in
the continuous energy mode. CELLMIX implies new mixture cross
sections are generated using XSDRNPM-calculated cell fluxes and
therefore is not applicable in the continuous energy mode.
h]h;)}(hIf CELLMIX is defined in the cell data, the problem will not run in
the continuous energy mode. CELLMIX implies new mixture cross
sections are generated using XSDRNPM-calculated cell fluxes and
therefore is not applicable in the continuous energy mode.h]h/If CELLMIX is defined in the cell data, the problem will not run in
the continuous energy mode. CELLMIX implies new mixture cross
sections are generated using XSDRNPM-calculated cell fluxes and
therefore is not applicable in the continuous energy mode.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM h jubah}(h]h]h]h]h]uhjh jubj)}(hOnly VACUUM, MIRROR, PERIODIC, and WHITE boundary conditions are
allowed. Other albedos, e.g., WATER, CARBON, POLY, etc. are for
multigroup only.
h]h;)}(hOnly VACUUM, MIRROR, PERIODIC, and WHITE boundary conditions are
allowed. Other albedos, e.g., WATER, CARBON, POLY, etc. are for
multigroup only.h]h/Only VACUUM, MIRROR, PERIODIC, and WHITE boundary conditions are
allowed. Other albedos, e.g., WATER, CARBON, POLY, etc. are for
multigroup only.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhjh jubj)}(h^Problems with DOUBLEHET cell data are not allowed as they inherently
utilize CELLMIX feature.
h]h;)}(h]Problems with DOUBLEHET cell data are not allowed as they inherently
utilize CELLMIX feature.h]h/]Problems with DOUBLEHET cell data are not allowed as they inherently
utilize CELLMIX feature.}(hj4h j2ubah}(h]h]h]h]h]uhh:h!j)hMh j.ubah}(h]h]h]h]h]uhjh jubeh}(h]h]h]h]h]j j j hj juhj h jubah}(h]h]h]h]h]uhj h jٱhhh!NhNubeh}(h]#continuous-energy-csas5-limitationsah]h]#continuous energy csas5 limitationsah]h]uhh#h jhhh!j)hKubeh}(h]sequence-capabilitiesah]h]h]jah]uhh#h jhhh!j)hKQjmKubh$)}(hhh](h))}(hInput Data Guideh]h/Input Data Guide}(hjfh jdhhh!NhNubah}(h]h]h]h]h]uhh(h jahhh!j)hMubh;)}(hThis section describes the input data required for CSAS5. Several
subsets of the CSAS5 sequences listed in :numref:`tab2-1` are available to
achieve several different levels of processing.h](h/kThis section describes the input data required for CSAS5. Several
subsets of the CSAS5 sequences listed in }(hkThis section describes the input data required for CSAS5. Several
subsets of the CSAS5 sequences listed in h jrhhh!NhNubh_)}(h:numref:`tab2-1`h]j)}(hj}h]h/tab2-1}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh j{ubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-1uhh^h!j)hMh jrubh/A are available to
achieve several different levels of processing.}(hA are available to
achieve several different levels of processing.h jrhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jahhubh;)}(hXThe input data for these CSAS5 sequences are composed of three broad
categories of data. The first is XSProc, including Standard Composition
Specification Data and Unit Cell Geometry Specification. This first
category specifies the cross-section library and defines the composition
of each mixture and optionally unit cell geometry that may be used to
process the cross sections. This data block is necessary for all CSAS5
sequences. The second category of data, the KENO V.a input data, is used
to specify the geometric and boundary conditions that represent the
physical 3-D configuration of a KENO V.a problem. Both data blocks are
necessary for CSAS5 and CSAS5S. The last category of data is the search
data and is required only for CSAS5S.h]h/XThe input data for these CSAS5 sequences are composed of three broad
categories of data. The first is XSProc, including Standard Composition
Specification Data and Unit Cell Geometry Specification. This first
category specifies the cross-section library and defines the composition
of each mixture and optionally unit cell geometry that may be used to
process the cross sections. This data block is necessary for all CSAS5
sequences. The second category of data, the KENO V.a input data, is used
to specify the geometric and boundary conditions that represent the
physical 3-D configuration of a KENO V.a problem. Both data blocks are
necessary for CSAS5 and CSAS5S. The last category of data is the search
data and is required only for CSAS5S.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMh jahhubh;)}(hXAll data are entered in free form, allowing alphanumeric data,
floating-point data, and integer data to be entered in an unstructured
manner. Up to 252 columns of data entry per line are allowed. Data can
usually start or end in any column with a few exceptions. As an example,
the word END beginning in column 1 and followed by two blank spaces or a
new line will end the problem and any data following will be ignored.
Each data entry must be followed by one or more blanks to terminate the
data entry. For numeric data, either a comma or a blank can be used to
terminate each data entry. Integers may be entered for floating-point
values. For example, 10 will be interpreted as 10.0. Imbedded blanks are
not allowed within a data entry unless an E precedes a single blank as
in an unsigned exponent in a floating-point number. For example, 1.0E 4
would be correctly interpreted as 1.0 × 10\ :sup:`4`.h](h/XAll data are entered in free form, allowing alphanumeric data,
floating-point data, and integer data to be entered in an unstructured
manner. Up to 252 columns of data entry per line are allowed. Data can
usually start or end in any column with a few exceptions. As an example,
the word END beginning in column 1 and followed by two blank spaces or a
new line will end the problem and any data following will be ignored.
Each data entry must be followed by one or more blanks to terminate the
data entry. For numeric data, either a comma or a blank can be used to
terminate each data entry. Integers may be entered for floating-point
values. For example, 10 will be interpreted as 10.0. Imbedded blanks are
not allowed within a data entry unless an E precedes a single blank as
in an unsigned exponent in a floating-point number. For example, 1.0E 4
would be correctly interpreted as 1.0 × 10 }(hXAll data are entered in free form, allowing alphanumeric data,
floating-point data, and integer data to be entered in an unstructured
manner. Up to 252 columns of data entry per line are allowed. Data can
usually start or end in any column with a few exceptions. As an example,
the word END beginning in column 1 and followed by two blank spaces or a
new line will end the problem and any data following will be ignored.
Each data entry must be followed by one or more blanks to terminate the
data entry. For numeric data, either a comma or a blank can be used to
terminate each data entry. Integers may be entered for floating-point
values. For example, 10 will be interpreted as 10.0. Imbedded blanks are
not allowed within a data entry unless an E precedes a single blank as
in an unsigned exponent in a floating-point number. For example, 1.0E 4
would be correctly interpreted as 1.0 × 10\ h jhhh!NhNubj)}(h:sup:`4`h]h/4}(hhh jubah}(h]h]h]h]h]uhjh jubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hM(h jahhubh;)}(hX7The word “END” is a special data item. An “END” may have a name or label
associated with it (e.g., “END DATA”). The name or label associated with
an “END” is separated from the “END” by a single blank and is a maximum
of 12 characters long. *At least two blanks or a new line MUST follow
every labeled and unlabeled “END.” It is the user’s responsibility to
ensure compliance with this restriction. Failure to observe this
restriction can result in the use of incorrect or incomplete data
without the benefit of warning or error messages.*h](h/XThe word “END” is a special data item. An “END” may have a name or label
associated with it (e.g., “END DATA”). The name or label associated with
an “END” is separated from the “END” by a single blank and is a maximum
of 12 characters long. }(hXThe word “END” is a special data item. An “END” may have a name or label
associated with it (e.g., “END DATA”). The name or label associated with
an “END” is separated from the “END” by a single blank and is a maximum
of 12 characters long. h jղhhh!NhNubh)}(hX0*At least two blanks or a new line MUST follow
every labeled and unlabeled “END.” It is the user’s responsibility to
ensure compliance with this restriction. Failure to observe this
restriction can result in the use of incorrect or incomplete data
without the benefit of warning or error messages.*h]h/X.At least two blanks or a new line MUST follow
every labeled and unlabeled “END.” It is the user’s responsibility to
ensure compliance with this restriction. Failure to observe this
restriction can result in the use of incorrect or incomplete data
without the benefit of warning or error messages.}(hhh jubah}(h]h]h]h]h]uhhh jղubeh}(h]h]h]h]h]uhh:h!j)hM6h jahhubh;)}(hXMultiple entries of the same data value can be achieved by specifying
the number of times the data value is to be entered, followed by either
R, \*, or $, followed by the data value to be repeated. Imbedded blanks
are not allowed between the number of repeats and the repeat flag. For
example, 5R12, 5*12, 5$12, or 5R 12, etc., will enter five successive
12s in the input data. Multiple zeros can be specified as nZ where n is
the number of zeroes to be entered.h]h/XMultiple entries of the same data value can be achieved by specifying
the number of times the data value is to be entered, followed by either
R, *, or $, followed by the data value to be repeated. Imbedded blanks
are not allowed between the number of repeats and the repeat flag. For
example, 5R12, 5*12, 5$12, or 5R 12, etc., will enter five successive
12s in the input data. Multiple zeros can be specified as nZ where n is
the number of zeroes to be entered.}(hXMultiple entries of the same data value can be achieved by specifying
the number of times the data value is to be entered, followed by either
R, \*, or $, followed by the data value to be repeated. Imbedded blanks
are not allowed between the number of repeats and the repeat flag. For
example, 5R12, 5*12, 5$12, or 5R 12, etc., will enter five successive
12s in the input data. Multiple zeros can be specified as nZ where n is
the number of zeroes to be entered.h jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hM?h jahhubh;)}(hThe purpose of this section is to define the input data in discrete
subsections relating to a particular type of data. Tables of the input
data are included in each subsection, and the entries are described in
more detail in the appropriate sections.h]h/The purpose of this section is to define the input data in discrete
subsections relating to a particular type of data. Tables of the input
data are included in each subsection, and the entries are described in
more detail in the appropriate sections.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMGh jahhubh;)}(hXResonance-corrected cross sections are generated using the appropriate
boundary conditions for the unit cell description (i.e., void for the
outer surface of a single unit, white for the outer surface of an
infinite array of cylinders). As many unit cells as needed may be
specified in a problem. A unit cell is cell-weighted by using the
keyword “CELLMIX=” followed by a unique user specified mixture number in
the unit cell data.h]h/XResonance-corrected cross sections are generated using the appropriate
boundary conditions for the unit cell description (i.e., void for the
outer surface of a single unit, white for the outer surface of an
infinite array of cylinders). As many unit cells as needed may be
specified in a problem. A unit cell is cell-weighted by using the
keyword “CELLMIX=” followed by a unique user specified mixture number in
the unit cell data.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMLh jahhubh;)}(hTo check the input data without actually processing the cross sections,
the words “PARM=CHECK” or “PARM=CHK” should be entered, as shown below.h]h/To check the input data without actually processing the cross sections,
the words “PARM=CHECK” or “PARM=CHK” should be entered, as shown below.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMTh jahhubj
)}(hhh]j)}(hhh](j)}(h=CSAS5 PARM=CHKh]h/=CSAS5 PARM=CHK}(hj3h j1ubah}(h]h]h]h]h]uhhjőKh j.h!j)hKubj)}(horh]h/or}(hjAh j?ubah}(h]h]h]h]h]uhhjőKh j.h!j)hKubj)}(h#CSAS5 PARM=CHKh]h/#CSAS5 PARM=CHK}(hjOh jMubah}(h]h]h]h]h]uhhjőKh j.h!j)hKubeh}(h]h]h]h]h]uhjh j+ubah}(h]h]h]h]h]uhj h jahhh!j)hNubh;)}(hXThis will cause the input data for CSAS5 to be checked and appropriate
error messages to be printed. If plots are specified in the data, they
will be printed. This feature allows the user to debug and verify the
input data while using a minimum of computer time.h]h/XThis will cause the input data for CSAS5 to be checked and appropriate
error messages to be printed. If plots are specified in the data, they
will be printed. This feature allows the user to debug and verify the
input data while using a minimum of computer time.}(hjih jghhh!NhNubah}(h]h]h]h]h]uhh:h!j)hM[h jahhubh$)}(hhh](h))}(hXSProc datah]h/XSProc data}(hjzh jxhhh!NhNubah}(h]h]h]h]h]uhh(h juhhh!j)hMaubh;)}(hXGThe XSProc reads the standard composition specification data and the
unit cell geometry specifications. It then produces the mixing table and
unit cell information necessary for processing the cross sections if
needed. The XSProc section of this manual provides a detailed
description of the input data and processing options.h]h/XGThe XSProc reads the standard composition specification data and the
unit cell geometry specifications. It then produces the mixing table and
unit cell information necessary for processing the cross sections if
needed. The XSProc section of this manual provides a detailed
description of the input data and processing options.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMch juhhubeh}(h]xsproc-dataah]h]h]jah]uhh#h jahhh!j)hMajmKubh$)}(hhh](h))}(h
KENO V.a datah]h/
KENO V.a data}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hMjubh;)}(hX{If the problem utilizes a sequence that contains KENO V.a as a
functional module, the input to KENO V.a comes after the XSProc input.
:numref:`tab2-2` contains the outline for the KENO V.a input and the SEARCH
input, which is required for a search case (i.e., CSAS5S). The KENO V.a
input is divided into 13 data blocks and CSAS5S includes an additional
block of search data. A brief outline of commonly used data blocks is
shown in :numref:`tab2-2`. Note that parameter data must precede all other
KENO data blocks. Information on all KENO V.a input is provided in the
KENO chapter of this document and will not be repeated here.h](h/If the problem utilizes a sequence that contains KENO V.a as a
functional module, the input to KENO V.a comes after the XSProc input.
}(hIf the problem utilizes a sequence that contains KENO V.a as a
functional module, the input to KENO V.a comes after the XSProc input.
h jhhh!NhNubh_)}(h:numref:`tab2-2`h]j)}(hjh]h/tab2-2}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jubah}(h]h]h]h]h]refdocj refdomainjóreftypenumrefrefexplicitrefwarnjtab2-2uhh^h!j)hMlh jubh/X contains the outline for the KENO V.a input and the SEARCH
input, which is required for a search case (i.e., CSAS5S). The KENO V.a
input is divided into 13 data blocks and CSAS5S includes an additional
block of search data. A brief outline of commonly used data blocks is
shown in }(hX contains the outline for the KENO V.a input and the SEARCH
input, which is required for a search case (i.e., CSAS5S). The KENO V.a
input is divided into 13 data blocks and CSAS5S includes an additional
block of search data. A brief outline of commonly used data blocks is
shown in h jhhh!NhNubh_)}(h:numref:`tab2-2`h]j)}(hjܳh]h/tab2-2}(hhh jubah}(h]h](jstd
std-numrefeh]h]h]uhjh jڳubah}(h]h]h]h]h]refdocj refdomainjreftypenumrefrefexplicitrefwarnjtab2-2uhh^h!j)hMlh jubh/. Note that parameter data must precede all other
KENO data blocks. Information on all KENO V.a input is provided in the
KENO chapter of this document and will not be repeated here.}(h. Note that parameter data must precede all other
KENO data blocks. Information on all KENO V.a input is provided in the
KENO chapter of this document and will not be repeated here.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMlh jhhubh)}(h.. _tab2-2:h]h}(h]h]h]h]h]htab2-2uhh
hM
h jhhh!j)ubj)}(hhh](h))}(hOutline of KENO datah]h/Outline of KENO data}(hjh jubah}(h]h]h]h]h]uhh(h!j)hMwh jubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j!ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j!ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j!ubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h j!ubj0)}(hhh](j5)}(hhh](j:)}(hhh]h;)}(h**Type of
data**h]hA)}(hjWh]h/Type of
data}(hhh jYubah}(h]h]h]h]h]uhh@h jUubah}(h]h]h]h]h]uhh:h!j)hM|h jRubah}(h]h]h]h]h]uhj9h jOubj:)}(hhh]h;)}(h**Starting
flag**h]hA)}(hjwh]h/
Starting
flag}(hhh jyubah}(h]h]h]h]h]uhh@h juubah}(h]h]h]h]h]uhh:h!j)hM|h jrubah}(h]h]h]h]h]uhj9h jOubj:)}(hhh]h;)}(h**Comments**h]hA)}(hjh]h/Comments}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!j)hM|h jubah}(h]h]h]h]h]uhj9h jOubj:)}(hhh]h;)}(h**Termination
flag**h]hA)}(hjh]h/Termination
flag}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!j)hM|h jubah}(h]h]h]h]h]uhj9h jOubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hParameters\*h]h/Parameters*}(hParameters\*h jubah}(h]h]h]h]h]uhh:h!j)hMh j۴ubah}(h]h]h]h]h]uhj9h jشubj:)}(hhh]h;)}(hREAD PARAMETERh]h/READ PARAMETER}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jشubj:)}(hhh]h;)}(hEnter
desired
parameter
datah]h/Enter
desired
parameter
data}(hjh j
ubah}(h]h]h]h]h]uhh:h!j)hMh j
ubah}(h]h]h]h]h]uhj9h jشubj:)}(hhh]h;)}(h
END PARAMETERh]h/
END PARAMETER}(hj&h j$ubah}(h]h]h]h]h]uhh:h!j)hMh j!ubah}(h]h]h]h]h]uhj9h jشubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hGeometryh]h/Geometry}(hjFh jDubah}(h]h]h]h]h]uhh:h!j)hMh jAubah}(h]h]h]h]h]uhj9h j>ubj:)}(hhh]h;)}(h
READ GEOMETRYh]h/
READ GEOMETRY}(hj]h j[ubah}(h]h]h]h]h]uhh:h!j)hMh jXubah}(h]h]h]h]h]uhj9h j>ubj:)}(hhh]h;)}(hEnter
desired
geometry
datah]h/Enter
desired
geometry
data}(hjth jrubah}(h]h]h]h]h]uhh:h!j)hMh joubah}(h]h]h]h]h]uhj9h j>ubj:)}(hhh]h;)}(hEND GEOMETRYh]h/END GEOMETRY}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h j>ubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(h
Array datah]h/
Array data}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
READ ARRAYh]h/
READ ARRAY}(hjµh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnter
desired
array datah]h/Enter
desired
array data}(hjٵh jubah}(h]h]h]h]h]uhh:h!j)hMh jԵubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h END ARRAYh]h/ END ARRAY}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hBoundary
conditionsh]h/Boundary
conditions}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hREAD BOUNDSh]h/READ BOUNDS}(hj'h j%ubah}(h]h]h]h]h]uhh:h!j)hMh j"ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h!Enter
desired
boundary
conditionsh]h/!Enter
desired
boundary
conditions}(hj>h j<ubah}(h]h]h]h]h]uhh:h!j)hMh j9ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
END BOUNDSh]h/
END BOUNDS}(hjUh jSubah}(h]h]h]h]h]uhh:h!j)hMh jPubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hEnergy group
boundariesh]h/Energy group
boundaries}(hjuh jsubah}(h]h]h]h]h]uhh:h!j)hMh jpubah}(h]h]h]h]h]uhj9h jmubj:)}(hhh]h;)}(hREAD ENERGYh]h/READ ENERGY}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jmubj:)}(hhh]h;)}(h-Enter
desired
neutron
energy group
boundariesh]h/-Enter
desired
neutron
energy group
boundaries}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jmubj:)}(hhh]h;)}(h
END ENERGYh]h/
END ENERGY}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jmubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hStart data
or initial
sourceh]h/Start data
or initial
source}(hjڶh jضubah}(h]h]h]h]h]uhh:h!j)hMh jնubah}(h]h]h]h]h]uhj9h jҶubj:)}(hhh]h;)}(h
READ STARTh]h/
READ START}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jҶubj:)}(hhh]h;)}(hEnter
desired
start datah]h/Enter
desired
start data}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jҶubj:)}(hhh]h;)}(h END STARTh]h/ END START}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jҶubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(h Plot datah]h/ Plot data}(hj?h j=ubah}(h]h]h]h]h]uhh:h!j)hMh j:ubah}(h]h]h]h]h]uhj9h j7ubj:)}(hhh]h;)}(h READ PLOTh]h/ READ PLOT}(hjVh jTubah}(h]h]h]h]h]uhh:h!j)hMh jQubah}(h]h]h]h]h]uhj9h j7ubj:)}(hhh]h;)}(hEnter
desired plot
datah]h/Enter
desired plot
data}(hjmh jkubah}(h]h]h]h]h]uhh:h!j)hMh jhubah}(h]h]h]h]h]uhj9h j7ubj:)}(hhh]h;)}(hEND PLOTh]h/END PLOT}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h j7ubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hGrid
geometry
datah]h/Grid
geometry
data}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h READ GRIDh]h/ READ GRID}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnter
desired mesh
datah]h/Enter
desired mesh
data}(hjҷh jзubah}(h]h]h]h]h]uhh:h!j)hMh jͷubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEND GRIDh]h/END GRID}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hReactionh]h/Reaction}(hj h jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
READ REACTIONh]h/
READ REACTION}(hj h jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h,Enter desire
reaction
tallies (CE
mode only)h]h/,Enter desire
reaction
tallies (CE
mode only)}(hj7h j5ubah}(h]h]h]h]h]uhh:h!j)hMh j2ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEND REACTIONh]h/END REACTION}(hjNh jLubah}(h]h]h]h]h]uhh:h!j)hMh jIubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hKENO V.a
data
terminush]h/KENO V.a
data
terminus}(hjnh jlubah}(h]h]h]h]h]uhh:h!j)hMh jiubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h;)}(hEND DATAh]h/END DATA}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]j)}(hhh](j)}(hEnter to
signal the
end of allh]h/Enter to
signal the
end of all}(hjh jubah}(h]h]h]h]h]uhhjőKh jh!j)hKubj)}(hKENO V.a
datah]h/KENO V.a
data}(hjh jubah}(h]h]h]h]h]uhhjőKh jh!j)hKubeh}(h]h]h]h]h]uhjh jubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h}(h]h]h]h]h]uhj9h jfubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(hSearch datah]h/Search data}(hjܸh jڸubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jԸubj:)}(hhh]h;)}(hREAD SEARCHh]h/READ SEARCH}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jԸubj:)}(hhh]h;)}(hEnter for
CSAS5h]h/Enter for
CSAS5}(hj
h jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jԸubj:)}(hhh]h;)}(h
END SEARCHh]h/
END SEARCH}(hj!h jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jԸubeh}(h]h]h]h]h]uhj4h jLubj5)}(hhh](j:)}(hhh]h;)}(h3\*Must precede
all other data
blocks in this
table.h]h/3*Must precede
all other data
blocks in this
table.}(h3\*Must precede
all other data
blocks in this
table.h j?ubah}(h]h]h]h]h]uhh:h!j)hMh j<ubah}(h]h]h]h]h]uhj9h j9ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j9ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j9ubj:)}(hhh]h}(h]h]h]h]h]uhj9h j9ubeh}(h]h]h]h]h]uhj4h jLubeh}(h]h]h]h]h]uhj/h j!ubeh}(h]h]h]h]h]colsKuhjh jubeh}(h](id74jeh]h]tab2-2ah]h]jcenteruhjh jhhh!j)hNj}jjsj}jjsubeh}(h]
keno-v-a-dataah]h]
keno v.a dataah]h]uhh#h jahhh!j)hMjubh$)}(hhh](h))}(hSearch datah]h/Search data}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hMubh;)}(hX}Search data must be entered for CSAS5S. The search data enable the code
to perform a search according to the instructions specified by the user.
The code begins reading search data when it encounters the words READ
SEARCH and continues reading search data until it encounters the words
END SEARCH. Search data consist of the search type specification and
auxiliary search commands.h]h/X}Search data must be entered for CSAS5S. The search data enable the code
to perform a search according to the instructions specified by the user.
The code begins reading search data when it encounters the words READ
SEARCH and continues reading search data until it encounters the words
END SEARCH. Search data consist of the search type specification and
auxiliary search commands.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMh jhhubh$)}(hhh](h))}(hSearch type specificationh]h/Search type specification}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hMubh;)}(hXThese data are used to define the type of search and to set the
parameters that provide limits for the search. The search type
specification data consist of (a) a search descriptor, (b) the search
type, and (c) optional search parameters as described below.h]h/XThese data are used to define the type of search and to set the
parameters that provide limits for the search. The search type
specification data consist of (a) a search descriptor, (b) the search
type, and (c) optional search parameters as described below.}(hjǹh jŹhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(h4SEARCH DESCRIPTOR is used to define the search mode.h]h/4SEARCH DESCRIPTOR is used to define the search mode.}(hjչh jӹhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMh jhhubj
)}(hhh](h;)}(hHUse OPTIMUM if the maximum value of *k*\ :sub:`eff` is to be determined.h](h/$Use OPTIMUM if the maximum value of }(h$Use OPTIMUM if the maximum value of h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/ is to be determined.}(h is to be determined.h jubeh}(h]h]h]h]h]uhh:h!j)hMh jubh;)}(hGUse CRITICAL if a specified value of *k*\ :sub:`eff` is to be obtained.h](h/%Use CRITICAL if a specified value of }(h%Use CRITICAL if a specified value of h jubh)}(h*k*h]h/k}(hhh j"ubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh j5ubah}(h]h]h]h]h]uhjh jubh/ is to be obtained.}(h is to be obtained.h jubeh}(h]h]h]h]h]uhh:h!j)hMh jubh;)}(hHUse MINIMUM if the minimum value of *k*\ :sub:`eff` is to be determined.h](h/$Use MINIMUM if the minimum value of }(h$Use MINIMUM if the minimum value of h jNubh)}(h*k*h]h/k}(hhh jWubah}(h]h]h]h]h]uhhh jNubh/ }(h\ h jNubj)}(h
:sub:`eff`h]h/eff}(hhh jjubah}(h]h]h]h]h]uhjh jNubh/ is to be determined.}(h is to be determined.h jNubeh}(h]h]h]h]h]uhh:h!j)hMh jubeh}(h]h]h]h]h]uhj h jhhh!j)hNubh;)}(h^SEARCH TYPE is used to specify the variable that is to be changed during the search procedure.h]h/^SEARCH TYPE is used to specify the variable that is to be changed during the search procedure.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMh jhhubj
)}(hhh]h;)}(hXkUse PITCH to alter the center-to-center spacing between the units at
the lowest array level. By default only the spacing in the X and
Y directions will be altered. Use DIMENSION to alter the dimensions
of one or more geometry regions in one or more units. Use
CONCENTRATION to alter the concentration of one or more standard
compositions in one or more mixtures.h]h/XkUse PITCH to alter the center-to-center spacing between the units at
the lowest array level. By default only the spacing in the X and
Y directions will be altered. Use DIMENSION to alter the dimensions
of one or more geometry regions in one or more units. Use
CONCENTRATION to alter the concentration of one or more standard
compositions in one or more mixtures.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj h jhhh!j)hNubh;)}(hX%The combination of the search descriptor and the search type defines the
search method. Each search type has a set of predefined defaults and the
ability to change the default settings and expand the scope of the
search. Only one SEARCH DESCRIPTOR and one SEARCH TYPE are allowed in a
problem.h]h/X%The combination of the search descriptor and the search type defines the
search method. Each search type has a set of predefined defaults and the
ability to change the default settings and expand the scope of the
search. Only one SEARCH DESCRIPTOR and one SEARCH TYPE are allowed in a
problem.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXvAn OPTIMUM PITCH search determines the pitch that gives the maximum
value of *k*\ :sub:`eff`.* By default the X spacing will be altered for slab
arrays, the X and Y spacing will be altered for arrays of cylinders, and
the X, Y, and Z spacing will be altered for spherical arrays. Auxiliary
search commands can be used to instruct the code to change any of these
defaults.h](h/MAn OPTIMUM PITCH search determines the pitch that gives the maximum
value of }(hMAn OPTIMUM PITCH search determines the pitch that gives the maximum
value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jźubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jغubah}(h]h]h]h]h]uhjh jubh/X.* By default the X spacing will be altered for slab
arrays, the X and Y spacing will be altered for arrays of cylinders, and
the X, Y, and Z spacing will be altered for spherical arrays. Auxiliary
search commands can be used to instruct the code to change any of these
defaults.}(hX.* By default the X spacing will be altered for slab
arrays, the X and Y spacing will be altered for arrays of cylinders, and
the X, Y, and Z spacing will be altered for spherical arrays. Auxiliary
search commands can be used to instruct the code to change any of these
defaults.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXAn OPTIMUM DIMENSION search determines the maximum value of *k*\ :sub:`eff` by
altering the dimensions of one or more geometry regions in one or more
units in accordance with the specified auxiliary search commands. Only
the dimensions specified in the search commands will be modified. The
relative variations in dimensions are determined by the search constants
specified for each dimension.h](h/ by
altering the dimensions of one or more geometry regions in one or more
units in accordance with the specified auxiliary search commands. Only
the dimensions specified in the search commands will be modified. The
relative variations in dimensions are determined by the search constants
specified for each dimension.}(hX> by
altering the dimensions of one or more geometry regions in one or more
units in accordance with the specified auxiliary search commands. Only
the dimensions specified in the search commands will be modified. The
relative variations in dimensions are determined by the search constants
specified for each dimension.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXxAn OPTIMUM CONCENTRATION search determines the maximum value of *k*\ :sub:`eff`
by altering the concentration of standard compositions in mixtures in
accordance with specified search commands. Only the standard
compositions in the materials specified are altered. The relative
variations in concentrations are determined by the search constants
specified for each composition.h](h/@An OPTIMUM CONCENTRATION search determines the maximum value of }(h@An OPTIMUM CONCENTRATION search determines the maximum value of h j&hhh!NhNubh)}(h*k*h]h/k}(hhh j/ubah}(h]h]h]h]h]uhhh j&ubh/ }(h\ h j&hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jBubah}(h]h]h]h]h]uhjh j&ubh/X)
by altering the concentration of standard compositions in mixtures in
accordance with specified search commands. Only the standard
compositions in the materials specified are altered. The relative
variations in concentrations are determined by the search constants
specified for each composition.}(hX)
by altering the concentration of standard compositions in mixtures in
accordance with specified search commands. Only the standard
compositions in the materials specified are altered. The relative
variations in concentrations are determined by the search constants
specified for each composition.h j&hhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXA CRITICAL PITCH search alters the spacing between units in the same
manner as an optimum pitch search to achieve the specified value of
*k*\ :sub:`eff`. By default the X spacing will be altered for slab arrays, the
X and Y spacing will be altered for arrays of cylinders, and the X, Y,
and Z spacing will be altered for spherical arrays. Auxiliary search
commands can be used to instruct the code to change any of these
defaults.h](h/A CRITICAL PITCH search alters the spacing between units in the same
manner as an optimum pitch search to achieve the specified value of
}(hA CRITICAL PITCH search alters the spacing between units in the same
manner as an optimum pitch search to achieve the specified value of
h j[hhh!NhNubh)}(h*k*h]h/k}(hhh jdubah}(h]h]h]h]h]uhhh j[ubh/ }(h\ h j[hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jwubah}(h]h]h]h]h]uhjh j[ubh/X. By default the X spacing will be altered for slab arrays, the
X and Y spacing will be altered for arrays of cylinders, and the X, Y,
and Z spacing will be altered for spherical arrays. Auxiliary search
commands can be used to instruct the code to change any of these
defaults.}(hX. By default the X spacing will be altered for slab arrays, the
X and Y spacing will be altered for arrays of cylinders, and the X, Y,
and Z spacing will be altered for spherical arrays. Auxiliary search
commands can be used to instruct the code to change any of these
defaults.h j[hhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXrA CRITICAL DIMENSION search alters the dimensions of one or more
geometry regions in accordance with the specified auxiliary search
commands to achieve the specified value of *k*\ :sub:`eff`.* Only the dimensions
specified in the search commands will be modified. The relative
variations in dimensions are determined by the search constants
specified for each dimension.h](h/A CRITICAL DIMENSION search alters the dimensions of one or more
geometry regions in accordance with the specified auxiliary search
commands to achieve the specified value of }(hA CRITICAL DIMENSION search alters the dimensions of one or more
geometry regions in accordance with the specified auxiliary search
commands to achieve the specified value of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/.* Only the dimensions
specified in the search commands will be modified. The relative
variations in dimensions are determined by the search constants
specified for each dimension.}(h.* Only the dimensions
specified in the search commands will be modified. The relative
variations in dimensions are determined by the search constants
specified for each dimension.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXA CRITICAL CONCENTRATION search alters the concentration of standard
compositions in mixtures in accordance with the specified auxiliary
search commands to achieve the specified value of *k*\ :sub:`eff`. Only the
standard compositions in the materials specified are altered. The
relative variations in concentrations are determined by the search
constants specified for each composition.h](h/A CRITICAL CONCENTRATION search alters the concentration of standard
compositions in mixtures in accordance with the specified auxiliary
search commands to achieve the specified value of }(hA CRITICAL CONCENTRATION search alters the concentration of standard
compositions in mixtures in accordance with the specified auxiliary
search commands to achieve the specified value of h jŻhhh!NhNubh)}(h*k*h]h/k}(hhh jλubah}(h]h]h]h]h]uhhh jŻubh/ }(h\ h jŻhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jŻubh/. Only the
standard compositions in the materials specified are altered. The
relative variations in concentrations are determined by the search
constants specified for each composition.}(h. Only the
standard compositions in the materials specified are altered. The
relative variations in concentrations are determined by the search
constants specified for each composition.h jŻhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXtA MINIMUM PITCH search determines the pitch that gives the minimum value
of *k*\ :sub:`eff`. By default the X spacing will be altered for slab arrays,
the X and Y spacing will be altered for arrays of cylinders, and the X,
Y, and Z spacing will be altered for spherical arrays. Auxiliary search
commands can be used to instruct the code to change any of these
defaults.h](h/LA MINIMUM PITCH search determines the pitch that gives the minimum value
of }(hLA MINIMUM PITCH search determines the pitch that gives the minimum value
of h jhhh!NhNubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/X. By default the X spacing will be altered for slab arrays,
the X and Y spacing will be altered for arrays of cylinders, and the X,
Y, and Z spacing will be altered for spherical arrays. Auxiliary search
commands can be used to instruct the code to change any of these
defaults.}(hX. By default the X spacing will be altered for slab arrays,
the X and Y spacing will be altered for arrays of cylinders, and the X,
Y, and Z spacing will be altered for spherical arrays. Auxiliary search
commands can be used to instruct the code to change any of these
defaults.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXA MINIMUM DIMENSION search determines the minimum value of *k*\ :sub:`eff` by
altering the dimensions of one or more geometry regions in one or more
units in accordance with the specified auxiliary search commands. Only
the dimensions specified in the search commands will be modified. The
relative variations in dimensions are determined by the search constants
specified for each dimension.h](h/;A MINIMUM DIMENSION search determines the minimum value of }(h;A MINIMUM DIMENSION search determines the minimum value of h j/hhh!NhNubh)}(h*k*h]h/k}(hhh j8ubah}(h]h]h]h]h]uhhh j/ubh/ }(h\ h j/hhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jKubah}(h]h]h]h]h]uhjh j/ubh/X> by
altering the dimensions of one or more geometry regions in one or more
units in accordance with the specified auxiliary search commands. Only
the dimensions specified in the search commands will be modified. The
relative variations in dimensions are determined by the search constants
specified for each dimension.}(hX> by
altering the dimensions of one or more geometry regions in one or more
units in accordance with the specified auxiliary search commands. Only
the dimensions specified in the search commands will be modified. The
relative variations in dimensions are determined by the search constants
specified for each dimension.h j/hhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXwA MINIMUM CONCENTRATION search determines the minimum value of *k*\ :sub:`eff`
by altering the concentration of standard compositions in mixtures in
accordance with specified search commands. Only the standard
compositions in the materials specified are altered. The relative
variations in concentrations are determined by the search constants
specified for each composition.h](h/?A MINIMUM CONCENTRATION search determines the minimum value of }(h?A MINIMUM CONCENTRATION search determines the minimum value of h jdhhh!NhNubh)}(h*k*h]h/k}(hhh jmubah}(h]h]h]h]h]uhhh jdubh/ }(h\ h jdhhh!NhNubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jdubh/X)
by altering the concentration of standard compositions in mixtures in
accordance with specified search commands. Only the standard
compositions in the materials specified are altered. The relative
variations in concentrations are determined by the search constants
specified for each composition.}(hX)
by altering the concentration of standard compositions in mixtures in
accordance with specified search commands. Only the standard
compositions in the materials specified are altered. The relative
variations in concentrations are determined by the search constants
specified for each composition.h jdhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXOPTIONAL SEARCH PARAMETERS are entered after the SEARCH DESCRIPTOR AND
SEARCH TYPE and are used to alter the default values of the optional
search parameters. Only one set of optional search parameters can be
entered for a problem. The optional search parameters are listed below.h]h/XOPTIONAL SEARCH PARAMETERS are entered after the SEARCH DESCRIPTOR AND
SEARCH TYPE and are used to alter the default values of the optional
search parameters. Only one set of optional search parameters can be
entered for a problem. The optional search parameters are listed below.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hM#h jhhubjl)}(hhh](jl)}(hXPAS=nn
is used to set the maximum number of times the search will
calculate *k*\ :sub:`eff`.* The first pass calculates the *k*\ :sub:`eff` corresponding
to the initial geometry dimensions. The second pass calculates the
*k*\ :sub:`eff` corresponding to one of the constraints, and the third pass
often corresponds to the other constraint. After the third pass, the
search dimensions or concentrations are changed based on a fit to a
quadratic or cubic equation. The default value of nn is 10.
h](jl)}(hPAS=nnh]h/PAS=nn}(hjh jubah}(h]h]h]h]h]uhjlh!j)hM/h jubjl)}(hhh]h;)}(hXis used to set the maximum number of times the search will
calculate *k*\ :sub:`eff`.* The first pass calculates the *k*\ :sub:`eff` corresponding
to the initial geometry dimensions. The second pass calculates the
*k*\ :sub:`eff` corresponding to one of the constraints, and the third pass
often corresponds to the other constraint. After the third pass, the
search dimensions or concentrations are changed based on a fit to a
quadratic or cubic equation. The default value of nn is 10.h](h/Eis used to set the maximum number of times the search will
calculate }(hEis used to set the maximum number of times the search will
calculate h jubh)}(h*k*h]h/k}(hhh jȼubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jۼubah}(h]h]h]h]h]uhjh jubh/!.* The first pass calculates the }(h!.* The first pass calculates the h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/R corresponding
to the initial geometry dimensions. The second pass calculates the
}(hR corresponding
to the initial geometry dimensions. The second pass calculates the
h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(hjڼh jubj)}(h
:sub:`eff`h]h/eff}(hhh j&ubah}(h]h]h]h]h]uhjh jubh/X corresponding to one of the constraints, and the third pass
often corresponds to the other constraint. After the third pass, the
search dimensions or concentrations are changed based on a fit to a
quadratic or cubic equation. The default value of nn is 10.}(hX corresponding to one of the constraints, and the third pass
often corresponds to the other constraint. After the third pass, the
search dimensions or concentrations are changed based on a fit to a
quadratic or cubic equation. The default value of nn is 10.h jubeh}(h]h]h]h]h]uhh:h!j)hM)h jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hM/h jubjl)}(hrNPM=nn
is used to set the number of search parameters. The default value
of nn is 1 and should not be overridden.
h](jl)}(hNPM=nnh]h/NPM=nn}(hjQh jOubah}(h]h]h]h]h]uhjlh!j)hM3h jKubjl)}(hhh]h;)}(hjis used to set the number of search parameters. The default value
of nn is 1 and should not be overridden.h]h/jis used to set the number of search parameters. The default value
of nn is 1 and should not be overridden.}(hjbh j`ubah}(h]h]h]h]h]uhh:h!j)hM2h j]ubah}(h]h]h]h]h]uhjlh jKubeh}(h]h]h]h]h]uhjlh!j)hM3h jhhubjl)}(hXEPS=ff
is used to set the search convergence tolerance (the amount by
which *k*\ :sub:`eff` is allowed to vary from the desired *k*\ :sub:`eff`)\ *.* An
optimum or minimum search is terminated when the calculated *k*\ :sub:`eff` is
within EPS of the optimum or minimum value as indicated by the
mathematical fit to the calculated points. A critical search is
terminated when the calculated *k*\ :sub:`eff` is within EPS of the specified
*k*\ :sub:`eff`. The default value of ff is 0.005.
h](jl)}(hEPS=ffh]h/EPS=ff}(hjh j~ubah}(h]h]h]h]h]uhjlh!j)hM<h jzubjl)}(hhh]h;)}(hXis used to set the search convergence tolerance (the amount by
which *k*\ :sub:`eff` is allowed to vary from the desired *k*\ :sub:`eff`)\ *.* An
optimum or minimum search is terminated when the calculated *k*\ :sub:`eff` is
within EPS of the optimum or minimum value as indicated by the
mathematical fit to the calculated points. A critical search is
terminated when the calculated *k*\ :sub:`eff` is within EPS of the specified
*k*\ :sub:`eff`. The default value of ff is 0.005.h](h/Eis used to set the search convergence tolerance (the amount by
which }(hEis used to set the search convergence tolerance (the amount by
which h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jubah}(h]h]h]h]h]uhjh jubh/% is allowed to vary from the desired }(h% is allowed to vary from the desired h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh jѽubah}(h]h]h]h]h]uhjh jubh/) }(h)\ h jubh)}(h*.*h]h/.}(hhh jubah}(h]h]h]h]h]uhhh jubh/@ An
optimum or minimum search is terminated when the calculated }(h@ An
optimum or minimum search is terminated when the calculated h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh j
ubah}(h]h]h]h]h]uhjh jubh/ is
within EPS of the optimum or minimum value as indicated by the
mathematical fit to the calculated points. A critical search is
terminated when the calculated }(h is
within EPS of the optimum or minimum value as indicated by the
mathematical fit to the calculated points. A critical search is
terminated when the calculated h jubh)}(h*k*h]h/k}(hhh jubah}(h]h]h]h]h]uhhh jubh/ }(h\ h jubj)}(h
:sub:`eff`h]h/eff}(hhh j0ubah}(h]h]h]h]h]uhjh jubh/ is within EPS of the specified
}(h is within EPS of the specified
h jubh)}(h*k*h]h/k}(hhh jCubah}(h]h]h]h]h]uhhh jubh/ }(hjh jubj)}(h
:sub:`eff`h]h/eff}(hhh jUubah}(h]h]h]h]h]uhjh jubh/#. The default value of ff is 0.005.}(h#. The default value of ff is 0.005.h jubeh}(h]h]h]h]h]uhh:h!j)hM6h jubah}(h]h]h]h]h]uhjlh jzubeh}(h]h]h]h]h]uhjlh!j)hM<h jhhubjl)}(hMKEF=ff
is used only for a CRITICAL search. The default value of ff is
1.000.
h](jl)}(hKEF=ffh]h/KEF=ff}(hjh j~ubah}(h]h]h]h]h]uhjlh!j)hM@h jzubjl)}(hhh]h;)}(hEis used only for a CRITICAL search. The default value of ff is
1.000.h]h/Eis used only for a CRITICAL search. The default value of ff is
1.000.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM?h jubah}(h]h]h]h]h]uhjlh jzubeh}(h]h]h]h]h]uhjlh!j)hM@h jhhubjl)}(hXDMINPITCH=ff
is allowed ONLY for a PITCH search. It is used to specify
the minimum allowed pitch (center-to-center spacing in the X; X,Y; or
X,Y,Z directions depending on array type) between the units in an array.
The search will terminate if the pitch becomes smaller than the
specified minimum pitch. The default value of ff is the pitch at which
the region immediately inside the outer most region of the unit touches
the same region in an adjacent unit. It is much easier to specify the
minimum allowed pitch than to calculate the appropriate value of the
minimum constraint.
h](jl)}(hMINPITCH=ffh]h/MINPITCH=ff}(hjh jubah}(h]h]h]h]h]uhjlh!j)hMKh jubjl)}(hhh]h;)}(hX7is allowed ONLY for a PITCH search. It is used to specify
the minimum allowed pitch (center-to-center spacing in the X; X,Y; or
X,Y,Z directions depending on array type) between the units in an array.
The search will terminate if the pitch becomes smaller than the
specified minimum pitch. The default value of ff is the pitch at which
the region immediately inside the outer most region of the unit touches
the same region in an adjacent unit. It is much easier to specify the
minimum allowed pitch than to calculate the appropriate value of the
minimum constraint.h]h/X7is allowed ONLY for a PITCH search. It is used to specify
the minimum allowed pitch (center-to-center spacing in the X; X,Y; or
X,Y,Z directions depending on array type) between the units in an array.
The search will terminate if the pitch becomes smaller than the
specified minimum pitch. The default value of ff is the pitch at which
the region immediately inside the outer most region of the unit touches
the same region in an adjacent unit. It is much easier to specify the
minimum allowed pitch than to calculate the appropriate value of the
minimum constraint.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMCh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hMKh jhhubjl)}(hXMAXPITCH=ff
is allowed ONLY for a PITCH search. It is used to specify
the maximum allowed pitch (center-to-center spacing in the X; X, Y; or
X, Y, Z directions depending on array type) between units in an array.
The search will terminate if the specified pitch is exceeded. The
default value of ff is the pitch corresponding to −5 times the parameter
that corresponds to the minimum pitch. It is much easier to specify a
maximum allowed pitch than to calculate the appropriate value of the
maximum constraint.
h](jl)}(hMAXPITCH=ffh]h/MAXPITCH=ff}(hjh jܾubah}(h]h]h]h]h]uhjlh!j)hMUh jؾubjl)}(hhh]h;)}(hXis allowed ONLY for a PITCH search. It is used to specify
the maximum allowed pitch (center-to-center spacing in the X; X, Y; or
X, Y, Z directions depending on array type) between units in an array.
The search will terminate if the specified pitch is exceeded. The
default value of ff is the pitch corresponding to −5 times the parameter
that corresponds to the minimum pitch. It is much easier to specify a
maximum allowed pitch than to calculate the appropriate value of the
maximum constraint.h]h/Xis allowed ONLY for a PITCH search. It is used to specify
the maximum allowed pitch (center-to-center spacing in the X; X, Y; or
X, Y, Z directions depending on array type) between units in an array.
The search will terminate if the specified pitch is exceeded. The
default value of ff is the pitch corresponding to −5 times the parameter
that corresponds to the minimum pitch. It is much easier to specify a
maximum allowed pitch than to calculate the appropriate value of the
maximum constraint.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMNh jubah}(h]h]h]h]h]uhjlh jؾubeh}(h]h]h]h]h]uhjlh!j)hMUh jhhubjl)}(hXMORE
is used to terminate the optional search parameters and initiate
the auxiliary search commands. Do not enter MORE unless auxiliary search
commands are to be entered. This command may only be entered once,
immediately prior to the auxiliary search commands.
h](jl)}(hMOREh]h/MORE}(hj
h jubah}(h]h]h]h]h]uhjlh!j)hM[h jubjl)}(hhh]h;)}(hXis used to terminate the optional search parameters and initiate
the auxiliary search commands. Do not enter MORE unless auxiliary search
commands are to be entered. This command may only be entered once,
immediately prior to the auxiliary search commands.h]h/Xis used to terminate the optional search parameters and initiate
the auxiliary search commands. Do not enter MORE unless auxiliary search
commands are to be entered. This command may only be entered once,
immediately prior to the auxiliary search commands.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMXh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hM[h jhhubeh}(h]h]h]h]h]uhjlh jhhh!j)hNubh)}(h.. _tab2-3:h]h}(h]h]h]h]h]htab2-3uhh
hMh jhhh!j)ubj)}(hhh](h))}(h$Outline of search type specificationh]h/$Outline of search type specification}(hjLh jJubah}(h]h]h]h]h]uhh(h!j)hM^h jGubj)}(hhh](j$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jXubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jXubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jXubj$)}(hhh]h}(h]h]h]h]h]colwidthKuhj#h jXubj0)}(hhh](j5)}(hhh](j:)}(hhh](h;)}(h **Entry**h]hA)}(hjh]h/Entry}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!j)hMbh jubh;)}(h**No.**h]hA)}(hjh]h/No.}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!j)hMdh jubeh}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h**Type of
data**h]hA)}(hjſh]h/Type of
data}(hhh jǿubah}(h]h]h]h]h]uhh@h jÿubah}(h]h]h]h]h]uhh:h!j)hMbh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h**Data entry**h]hA)}(hjh]h/
Data entry}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!j)hMbh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h**Comments**h]hA)}(hjh]h/Comments}(hhh jubah}(h]h]h]h]h]uhh@h jubah}(h]h]h]h]h]uhh:h!j)hMbh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hjzh]h/1}(hjzh j,ubah}(h]h]h]h]h]uhh:h!j)hMfh j)ubah}(h]h]h]h]h]uhj9h j&ubj:)}(hhh]h;)}(hSearch
descriptorh]h/Search
descriptor}(hjDh jBubah}(h]h]h]h]h]uhh:h!j)hMfh j?ubah}(h]h]h]h]h]uhj9h j&ubj:)}(hhh]h;)}(hOPTIMUMh]h/OPTIMUM}(hj[h jYubah}(h]h]h]h]h]uhh:h!j)hMfh jVubah}(h]h]h]h]h]uhj9h j&ubj:)}(hhh]h;)}(h5Initiates a
search for the
maximum value
of *k\ eff*.h](h/,Initiates a
search for the
maximum value
of }(h,Initiates a
search for the
maximum value
of h jpubh)}(h*k\ eff*h]h/k eff}(hhh jyubah}(h]h]h]h]h]uhhh jpubh/.}(hjh jpubeh}(h]h]h]h]h]uhh:h!j)hMfh jmubah}(h]h]h]h]h]uhj9h j&ubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hCRITICALh]h/CRITICAL}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMkh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h5Initiates a
search for a
specified value
of *k\ eff*.h](h/,Initiates a
search for a
specified value
of }(h,Initiates a
search for a
specified value
of h jubh)}(h*k\ eff*h]h/k eff}(hhh jubah}(h]h]h]h]h]uhhh jubh/.}(hjh jubeh}(h]h]h]h]h]uhh:h!j)hMkh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hMINIMUMh]h/MINIMUM}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMph jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h5Initiates a
search for the
minimum value
of *k\ eff*.h](h/,Initiates a
search for the
minimum value
of }(h,Initiates a
search for the
minimum value
of h j(ubh)}(h*k\ eff*h]h/k eff}(hhh j1ubah}(h]h]h]h]h]uhhh j(ubh/.}(hjh j(ubeh}(h]h]h]h]h]uhh:h!j)hMph j%ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hj+h]h/2}(hj+h j[ubah}(h]h]h]h]h]uhh:h!j)hMuh jXubah}(h]h]h]h]h]uhj9h jUubj:)}(hhh]h;)}(hSearch typeh]h/Search type}(hjsh jqubah}(h]h]h]h]h]uhh:h!j)hMuh jnubah}(h]h]h]h]h]uhj9h jUubj:)}(hhh]h;)}(hPITCHh]h/PITCH}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMuh jubah}(h]h]h]h]h]uhj9h jUubj:)}(hhh]h;)}(hVary the pitch
of an array.h]h/Vary the pitch
of an array.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMuh jubah}(h]h]h]h]h]uhj9h jUubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h DIMENSIONh]h/ DIMENSION}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMxh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hHVary one or
more dimensions
in one or more
regions of one
or more units.h]h/HVary one or
more dimensions
in one or more
regions of one
or more units.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMxh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h
CONCENTRATIONh]h/
CONCENTRATION}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM~h jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hTVary the
concentration
of one or more
standard
compositions in
one or more
mixtures.h]h/TVary the
concentration
of one or more
standard
compositions in
one or more
mixtures.}(hj3h j1ubah}(h]h]h]h]h]uhh:h!j)hM~h j.ubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hjh]h/3}(hjh jQubah}(h]h]h]h]h]uhh:h!j)hMh jNubah}(h]h]h]h]h]uhj9h jKubj:)}(hhh]h;)}(hOptional search
parametersh]h/Optional search
parameters}(hjih jgubah}(h]h]h]h]h]uhh:h!j)hMh jdubah}(h]h]h]h]h]uhj9h jKubj:)}(hhh]h}(h]h]h]h]h]uhj9h jKubj:)}(hhh]h;)}(haOptional search
parameters
allow changing
default values.
Any or all may
be entered in
any order.h]h/aOptional search
parameters
allow changing
default values.
Any or all may
be entered in
any order.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jKubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h3ah]h/3a}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hNo. of search
passesh]h/No. of search
passes}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hPAS=h]h/PAS=}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hSEnter the
keyword PAS=
followed by the
desired number
of search
passes.
Default=10.h]h/SEnter the
keyword PAS=
followed by the
desired number
of search
passes.
Default=10.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h3bh]h/3b}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh j ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hNo. of search
parametersh]h/No. of search
parameters}(hj%h j#ubah}(h]h]h]h]h]uhh:h!j)hMh j ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hNPM=h]h/NPM=}(hj<h j:ubah}(h]h]h]h]h]uhh:h!j)hMh j7ubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hgEnter the
keyword NPM=
followed by the
number of
search
parameters.
Present
capability is
limited to 1.h]h/gEnter the
keyword NPM=
followed by the
number of
search
parameters.
Present
capability is
limited to 1.}(hjSh jQubah}(h]h]h]h]h]uhh:h!j)hMh jNubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h3ch]h/3c}(hjsh jqubah}(h]h]h]h]h]uhh:h!j)hMh jnubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(hSearch
convergence
toleranceh]h/Search
convergence
tolerance}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(hEPS=h]h/EPS=}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jkubj:)}(hhh]h;)}(hTEnter the
keyword EPS=
followed by the
desired
convergence
tolerance.
Default=0.005.h]h/TEnter the
keyword EPS=
followed by the
desired
convergence
tolerance.
Default=0.005.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jkubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h3dh]h/3d}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hDesired value
of *k\ eff*h](h/Desired value
of }(hDesired value
of h jubh)}(h*k\ eff*h]h/k eff}(hhh jubah}(h]h]h]h]h]uhhh jubeh}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hKEF=h]h/KEF=}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh](h;)}(h]Enter the
keyword KEF=
followed by the
desired value
of *k\ eff*.
The default
value is 1.000.h](h/8Enter the
keyword KEF=
followed by the
desired value
of }(h8Enter the
keyword KEF=
followed by the
desired value
of h j*ubh)}(h*k\ eff*h]h/k eff}(hhh j3ubah}(h]h]h]h]h]uhhh j*ubh/.
The default
value is 1.000.}(h.
The default
value is 1.000.h j*ubeh}(h]h]h]h]h]uhh:h!j)hMh j'ubh;)}(h-DO NOT ENTER
FOR OPTIMUM OR
MINIMUM
SEARCHES.h]h/-DO NOT ENTER
FOR OPTIMUM OR
MINIMUM
SEARCHES.}(hjNh jLubah}(h]h]h]h]h]uhh:h!j)hMh j'ubeh}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h3eh]h/3e}(hjnh jlubah}(h]h]h]h]h]uhh:h!j)hMh jiubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h;)}(hMaximum allowed
pitchh]h/Maximum allowed
pitch}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h;)}(h MAXPITCH=h]h/ MAXPITCH=}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jfubj:)}(hhh]h;)}(hEnter the
keyword
MAXPITCH=
followed by the
maximum allowed
pitch for a
search whose
search type,
entry 2 above,
is PITCH. The
default value
is the pitch
corresponding
to −5.0 times
the parameter
at the minimum
possible pitch.h]h/Enter the
keyword
MAXPITCH=
followed by the
maximum allowed
pitch for a
search whose
search type,
entry 2 above,
is PITCH. The
default value
is the pitch
corresponding
to −5.0 times
the parameter
at the minimum
possible pitch.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jfubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(h3fh]h/3f}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hMinimum allowed
pitchh]h/Minimum allowed
pitch}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(h MINPITCH=h]h/ MINPITCH=}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubj:)}(hhh]h;)}(hEnter the
keyword
MINPITCH=
followed by the
minimum allowed
pitch for a
search whose
search type,
entry 2 above,
is PITCH. The
default value
is the minimum
possible pitch
(i.e., the
pitch at which
the shapes in
the array
touch).h]h/Enter the
keyword
MINPITCH=
followed by the
minimum allowed
pitch for a
search whose
search type,
entry 2 above,
is PITCH. The
default value
is the minimum
possible pitch
(i.e., the
pitch at which
the shapes in
the array
touch).}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhj9h jubeh}(h]h]h]h]h]uhj4h jubj5)}(hhh](j:)}(hhh]h;)}(hjm,h]h/4}(hjm,h j6ubah}(h]h]h]h]h]uhh:h!j)hMh j3ubah}(h]h]h]h]h]uhj9h j0ubj:)}(hhh]h;)}(hAdditional
search datah]h/Additional
search data}(hjNh jLubah}(h]h]h]h]h]uhh:h!j)hMh jIubah}(h]h]h]h]h]uhj9h j0ubj:)}(hhh]h;)}(hMOREh]h/MORE}(hjeh jcubah}(h]h]h]h]h]uhh:h!j)hMh j`ubah}(h]h]h]h]h]uhj9h j0ubj:)}(hhh]h;)}(hEnter the
delimiter MORE.
This delimiter
ends the
optional search
commands and
initiates the
auxiliary
search commands
found in
Table 2.1.4.h]h/Enter the
delimiter MORE.
This delimiter
ends the
optional search
commands and
initiates the
auxiliary
search commands
found in
Table 2.1.4.}(hj|h jzubah}(h]h]h]h]h]uhh:h!j)hMh jwubah}(h]h]h]h]h]uhj9h j0ubeh}(h]h]h]h]h]uhj4h jubeh}(h]h]h]h]h]uhj/h jXubeh}(h]h]h]h]h]colsKuhjh jGubeh}(h](id75jFeh]h]tab2-3ah]h]jcenteruhjh jhhh!j)hNj}jj<sj}jFj<subeh}(h]search-type-specificationah]h]search type specificationah]h]uhh#h jhhh!j)hMubh$)}(hhh](h))}(h)Auxiliary search commands and constraintsh]h/)Auxiliary search commands and constraints}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh(h jhhh!j)hMubh;)}(hXAuxiliary search commands are entered **only** if MORE, item 4, of the
search type specification data is entered (see :numref`tab2-3`). Individual
search commands are used to specify search constraints and to
communicate to the search program. Searches can alter geometric
dimensions (PITCH or DIMENSION Search) or alter standard composition
number densities (CONCENTRATION Search).h](h/&Auxiliary search commands are entered }(h&Auxiliary search commands are entered h jhhh!NhNubhA)}(h**only**h]h/only}(hhh jubah}(h]h]h]h]h]uhh@h jubh/XQ if MORE, item 4, of the
search type specification data is entered (see :numref`tab2-3`). Individual
search commands are used to specify search constraints and to
communicate to the search program. Searches can alter geometric
dimensions (PITCH or DIMENSION Search) or alter standard composition
number densities (CONCENTRATION Search).}(hXQ if MORE, item 4, of the
search type specification data is entered (see :numref`tab2-3`). Individual
search commands are used to specify search constraints and to
communicate to the search program. Searches can alter geometric
dimensions (PITCH or DIMENSION Search) or alter standard composition
number densities (CONCENTRATION Search).h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXA PITCH or DIMENSION search may require the user to specify the units
that will be altered, the regions that will be altered within those
units, and the faces or surfaces of those regions that will be altered.
For a PITCH search, the program automatically assigns the units in the
arrays to a unit cell if possible. If multiple units are contained in
the array, each unit could be assigned a unit cell if the data in the
unit cells match the geometry data of the units in the array. This data
may be overridden in the MORE section of the search data. For a
DIMENSION search, if the user wishes to tie a unit to unit cell this
must be explicitly done in the MORE section of the search data. Several
examples of search problems are provided in :ref:`2-1`.h](h/XA PITCH or DIMENSION search may require the user to specify the units
that will be altered, the regions that will be altered within those
units, and the faces or surfaces of those regions that will be altered.
For a PITCH search, the program automatically assigns the units in the
arrays to a unit cell if possible. If multiple units are contained in
the array, each unit could be assigned a unit cell if the data in the
unit cells match the geometry data of the units in the array. This data
may be overridden in the MORE section of the search data. For a
DIMENSION search, if the user wishes to tie a unit to unit cell this
must be explicitly done in the MORE section of the search data. Several
examples of search problems are provided in }(hXA PITCH or DIMENSION search may require the user to specify the units
that will be altered, the regions that will be altered within those
units, and the faces or surfaces of those regions that will be altered.
For a PITCH search, the program automatically assigns the units in the
arrays to a unit cell if possible. If multiple units are contained in
the array, each unit could be assigned a unit cell if the data in the
unit cells match the geometry data of the units in the array. This data
may be overridden in the MORE section of the search data. For a
DIMENSION search, if the user wishes to tie a unit to unit cell this
must be explicitly done in the MORE section of the search data. Several
examples of search problems are provided in h jhhh!NhNubh_)}(h
:ref:`2-1`h]he)}(hjh]h/2-1}(hhh jubah}(h]h](jstdstd-refeh]h]h]uhhdh jubah}(h]h]h]h]h]refdocj refdomainjreftyperefrefexplicitrefwarnj2-1uhh^h!j)hMh jubh/.}(hjh jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXA CONCENTRATION search requires the user to specify the mixture,
standard composition name, and the search constant for the component
being altered. For a CONCENTRATION search, the program automatically
assigns the material being changed to a unit cell. This data may be
overridden in the MORE section of the search data. Several examples of
search problems are provided in :ref:`2-1.h](h/X{A CONCENTRATION search requires the user to specify the mixture,
standard composition name, and the search constant for the component
being altered. For a CONCENTRATION search, the program automatically
assigns the material being changed to a unit cell. This data may be
overridden in the MORE section of the search data. Several examples of
search problems are provided in :ref:}(hX{A CONCENTRATION search requires the user to specify the mixture,
standard composition name, and the search constant for the component
being altered. For a CONCENTRATION search, the program automatically
assigns the material being changed to a unit cell. This data may be
overridden in the MORE section of the search data. Several examples of
search problems are provided in :ref:h jhhh!NhNubjr)}(h`h]h/`}(hhh j#ubah}(h]id13ah]h]h]h]refidid12uhjqh jubh/2-1.}(h2-1.h jhhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubh;)}(hXThe data comprising the auxiliary search commands are listed in
:numref:`tab2-4`. All data except items 1a, 1b, and 1c are keyworded (i.e.,
the data are entered by specifying a keyword, followed by a value).
An explanation of each individual search command follows the table.h](h/@The data comprising the auxiliary search commands are listed in
}(h@The data comprising the auxiliary search commands are listed in
h j?hhh!NhNubh_)}(h:numref:`tab2-4`h]j)}(hjJh]h/tab2-4}(hhh jLubah}(h]h](jstd
std-numrefeh]h]h]uhjh jHubah}(h]h]h]h]h]refdocj refdomainjVreftypenumrefrefexplicitrefwarnjtab2-4uhh^h!j)hMh j?ubh/. All data except items 1a, 1b, and 1c are keyworded (i.e.,
the data are entered by specifying a keyword, followed by a value).
An explanation of each individual search command follows the table.}(h. All data except items 1a, 1b, and 1c are keyworded (i.e.,
the data are entered by specifying a keyword, followed by a value).
An explanation of each individual search command follows the table.h j?hhh!NhNubeh}(h]h]h]h]h]uhh:h!j)hMh jhhubjl)}(hhh](jl)}(h1 Command Definition
A command definition tells the code what action is to be taken. A new search command is
initiated whenever an item 1a through 1c is encountered. The code will vary the geometry
according to subsequent commands.
h](jl)}(h1 Command Definitionh]h/1 Command Definition}(hj|h jzubah}(h]h]h]h]h]uhjlh!j)hMh jvubjl)}(hhh]h;)}(hA command definition tells the code what action is to be taken. A new search command is
initiated whenever an item 1a through 1c is encountered. The code will vary the geometry
according to subsequent commands.h]h/A command definition tells the code what action is to be taken. A new search command is
initiated whenever an item 1a through 1c is encountered. The code will vary the geometry
according to subsequent commands.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM
h jubah}(h]h]h]h]h]uhjlh jvubeh}(h]h]h]h]h]uhjlh!j)hMh jsubjl)}(h1a. ALTER CHANGE MODIFY
Alter geometry regions. These words specify that modifications will be made to the geometry
according to subsequent commands.
h](jl)}(h1a. ALTER CHANGE MODIFYh]h/1a. ALTER CHANGE MODIFY}(hjh jubah}(h]h]h]h]h]uhjlh!j)hMh jubjl)}(hhh]h;)}(h}Alter geometry regions. These words specify that modifications will be made to the geometry
according to subsequent commands.h]h/}Alter geometry regions. These words specify that modifications will be made to the geometry
according to subsequent commands.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hMh jshhubjl)}(hX41b. MAINTAIN
Maintain the thickness. The thickness of the specified geometry region(s) will be maintained
when the interior regions grow or shrink (i.e., the specified region will grow or shrink in
conjunction with the interior region in such a way as to maintain the original distance between the two regions).
This means that the original thickness of the region is preserved. For instance, the inner radius of a pipe
can be altered and the wall thickness can be preserved by applying the MAINTAIN command to the region defining
the outer radius of the pipe.
h](jl)}(h1b. MAINTAINh]h/1b. MAINTAIN}(hjh jubah}(h]h]h]h]h]uhjlh!j)hMh jubjl)}(hhh]h;)}(hX&Maintain the thickness. The thickness of the specified geometry region(s) will be maintained
when the interior regions grow or shrink (i.e., the specified region will grow or shrink in
conjunction with the interior region in such a way as to maintain the original distance between the two regions).
This means that the original thickness of the region is preserved. For instance, the inner radius of a pipe
can be altered and the wall thickness can be preserved by applying the MAINTAIN command to the region defining
the outer radius of the pipe.h]h/X&Maintain the thickness. The thickness of the specified geometry region(s) will be maintained
when the interior regions grow or shrink (i.e., the specified region will grow or shrink in
conjunction with the interior region in such a way as to maintain the original distance between the two regions).
This means that the original thickness of the region is preserved. For instance, the inner radius of a pipe
can be altered and the wall thickness can be preserved by applying the MAINTAIN command to the region defining
the outer radius of the pipe.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hMh jshhubjl)}(h1c. KEEP HOLD
Keep the original specification. This command causes the specified geometry region(s)
to be reset to their original input value for every search pass. Therefore they go
through the entire search process unchanged.
h](jl)}(h
1c. KEEP HOLDh]h/
1c. KEEP HOLD}(hj h jubah}(h]h]h]h]h]uhjlh!j)hM h jubjl)}(hhh]h;)}(hKeep the original specification. This command causes the specified geometry region(s)
to be reset to their original input value for every search pass. Therefore they go
through the entire search process unchanged.h]h/Keep the original specification. This command causes the specified geometry region(s)
to be reset to their original input value for every search pass. Therefore they go
through the entire search process unchanged.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hM h jshhubjl)}(h2 PAR=
Parameter number. The search parameter number is not functional. The default number is 1 and should not be overridden.
h](jl)}(h2 PAR=h]h/2 PAR=}(hj8h j6ubah}(h]h]h]h]h]uhjlh!j)hM#h j2ubjl)}(hhh]h;)}(hxParameter number. The search parameter number is not functional. The default number is 1 and should not be overridden.h]h/xParameter number. The search parameter number is not functional. The default number is 1 and should not be overridden.}(hjIh jGubah}(h]h]h]h]h]uhh:h!j)hM#h jDubah}(h]h]h]h]h]uhjlh j2ubeh}(h]h]h]h]h]uhjlh!j)hM#h jshhubjl)}(hX3 +CON=
Maximum constraint. Enter the maximum value you wish to allow the search parameter to obtain.
The maximum constraint must be larger than the minimum constraint. For a DIMENSION or PITCH
search the default value of the maximum constraint is 1011. For a CONCENTRATION search the default
value of the maximum constraint is as follows:
+CON= min(−1/FACTOR ), if any FACTOR < 0
+CON= −5*(−CON ), if all FACTOR > 0
h](jl)}(h3 +CON=h]h/3 +CON=}(hjgh jeubah}(h]h]h]h]h]uhjlh!j)hM-h jaubjl)}(hhh](h;)}(hXNMaximum constraint. Enter the maximum value you wish to allow the search parameter to obtain.
The maximum constraint must be larger than the minimum constraint. For a DIMENSION or PITCH
search the default value of the maximum constraint is 1011. For a CONCENTRATION search the default
value of the maximum constraint is as follows:h]h/XNMaximum constraint. Enter the maximum value you wish to allow the search parameter to obtain.
The maximum constraint must be larger than the minimum constraint. For a DIMENSION or PITCH
search the default value of the maximum constraint is 1011. For a CONCENTRATION search the default
value of the maximum constraint is as follows:}(hjxh jvubah}(h]h]h]h]h]uhh:h!j)hM&h jsubj
)}(hhh](h;)}(h*+CON= min(−1/FACTOR ), if any FACTOR < 0h]h/*+CON= min(−1/FACTOR ), if any FACTOR < 0}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM+h jubh;)}(h'+CON= −5*(−CON ), if all FACTOR > 0h]h/'+CON= −5*(−CON ), if all FACTOR > 0}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM-h jubeh}(h]h]h]h]h]uhj h jsubeh}(h]h]h]h]h]uhjlh jaubeh}(h]h]h]h]h]uhjlh!j)hM-h jshhubeh}(h]h]h]h]h]uhjlh jhhh!j)hNubjz)}(hXFor a PITCH search, the maximum constraint is redefined and is calculated from the data entered for MAXPITCH.
+CON should not be entered if a value was entered for MAXPITCH. If constraints, +CON= and/or −CON= are
not entered as data, the code computes the minimum constraint corresponding to the pins touching,
and the maximum constraint is then negative five times the magnitude of the minimum constraint.h]h;)}(hXFor a PITCH search, the maximum constraint is redefined and is calculated from the data entered for MAXPITCH.
+CON should not be entered if a value was entered for MAXPITCH. If constraints, +CON= and/or −CON= are
not entered as data, the code computes the minimum constraint corresponding to the pins touching,
and the maximum constraint is then negative five times the magnitude of the minimum constraint.h]h/XFor a PITCH search, the maximum constraint is redefined and is calculated from the data entered for MAXPITCH.
+CON should not be entered if a value was entered for MAXPITCH. If constraints, +CON= and/or −CON= are
not entered as data, the code computes the minimum constraint corresponding to the pins touching,
and the maximum constraint is then negative five times the magnitude of the minimum constraint.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM0h jubah}(h]h]h]h]h]uhjyh jhhh!j)hNubjl)}(hhh](jl)}(hXN4 −CON=
Minimum constraint. Enter the minimum value you wish to allow the search parameter to obtain.
The minimum constraint must be smaller than the maximum constraint but need not be a negative number.
The default value of the minimum constraint for a dimension search is −1011.
The default value of the minimum constraint for a pitch search is redefined to correspond to the pins
in the lattice touching. For a CONCENTRATION search the default value of the minimum constraint is as follows:
−CON= −5(+CON ), if all FACTOR < 0
−CON= max(−1/FACTOR ), if any FACTOR > 0
h](jl)}(h 4 −CON=h]h/ 4 −CON=}(hjh jubah}(h]h]h]h]h]uhjlh!j)hM>h jubjl)}(hhh](h;)}(hXMinimum constraint. Enter the minimum value you wish to allow the search parameter to obtain.
The minimum constraint must be smaller than the maximum constraint but need not be a negative number.
The default value of the minimum constraint for a dimension search is −1011.
The default value of the minimum constraint for a pitch search is redefined to correspond to the pins
in the lattice touching. For a CONCENTRATION search the default value of the minimum constraint is as follows:h]h/XMinimum constraint. Enter the minimum value you wish to allow the search parameter to obtain.
The minimum constraint must be smaller than the maximum constraint but need not be a negative number.
The default value of the minimum constraint for a dimension search is −1011.
The default value of the minimum constraint for a pitch search is redefined to correspond to the pins
in the lattice touching. For a CONCENTRATION search the default value of the minimum constraint is as follows:}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM6h jubj
)}(hhh](h;)}(h&−CON= −5(+CON ), if all FACTOR < 0h]h/&−CON= −5(+CON ), if all FACTOR < 0}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM<h jubh;)}(h,−CON= max(−1/FACTOR ), if any FACTOR > 0h]h/,−CON= max(−1/FACTOR ), if any FACTOR > 0}(hjh j
ubah}(h]h]h]h]h]uhh:h!j)hM>h jubeh}(h]h]h]h]h]uhj h jubeh}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hM>h jubjl)}(hXM5 CELL=
Unit Cell Number. This is the unit cell to which the unit or mixture will be tied.
It needs to follow either the UNIT= or MIX= keyword data. Tying a unit cell to a unit or mixture
ensures the unit cell data gets changed as the geometry or mixture data gets changed thus ensuring the
cross sections are properly processed.
h](jl)}(h5 CELL=h]h/5 CELL=}(hj0h j.ubah}(h]h]h]h]h]uhjlh!j)hMDh j*ubjl)}(hhh]h;)}(hXDUnit Cell Number. This is the unit cell to which the unit or mixture will be tied.
It needs to follow either the UNIT= or MIX= keyword data. Tying a unit cell to a unit or mixture
ensures the unit cell data gets changed as the geometry or mixture data gets changed thus ensuring the
cross sections are properly processed.h]h/XDUnit Cell Number. This is the unit cell to which the unit or mixture will be tied.
It needs to follow either the UNIT= or MIX= keyword data. Tying a unit cell to a unit or mixture
ensures the unit cell data gets changed as the geometry or mixture data gets changed thus ensuring the
cross sections are properly processed.}(hjAh j?ubah}(h]h]h]h]h]uhh:h!j)hMAh j<ubah}(h]h]h]h]h]uhjlh j*ubeh}(h]h]h]h]h]uhjlh!j)hMDh jhhubjl)}(h6 UNIT=
Geometry unit number. This is the geometry unit to which the previously entered command definition
(item 1a, 1b, or 1c) is applied. Items 7, 8, and 9 specify the region(s) within the unit and the surfaces of
the region(s) to be altered.
h](jl)}(h6 UNIT=h]h/6 UNIT=}(hj_h j]ubah}(h]h]h]h]h]uhjlh!j)hMIh jYubjl)}(hhh]h;)}(hGeometry unit number. This is the geometry unit to which the previously entered command definition
(item 1a, 1b, or 1c) is applied. Items 7, 8, and 9 specify the region(s) within the unit and the surfaces of
the region(s) to be altered.h]h/Geometry unit number. This is the geometry unit to which the previously entered command definition
(item 1a, 1b, or 1c) is applied. Items 7, 8, and 9 specify the region(s) within the unit and the surfaces of
the region(s) to be altered.}(hjph jnubah}(h]h]h]h]h]uhh:h!j)hMGh jkubah}(h]h]h]h]h]uhjlh jYubeh}(h]h]h]h]h]uhjlh!j)hMIh jhhubjl)}(hX%7 REGION=
First region to be altered. This is used to specify the first or only region in the unit (specified by item 6)
that is to be altered according to the search command (item 1a, 1b, or 1c). The region(s) are altered according
to the search constants (items 9a, 9b, 9c, and/or 9d).
h](jl)}(h 7 REGION=h]h/ 7 REGION=}(hjh jubah}(h]h]h]h]h]uhjlh!j)hMNh jubjl)}(hhh]h;)}(hXFirst region to be altered. This is used to specify the first or only region in the unit (specified by item 6)
that is to be altered according to the search command (item 1a, 1b, or 1c). The region(s) are altered according
to the search constants (items 9a, 9b, 9c, and/or 9d).h]h/XFirst region to be altered. This is used to specify the first or only region in the unit (specified by item 6)
that is to be altered according to the search command (item 1a, 1b, or 1c). The region(s) are altered according
to the search constants (items 9a, 9b, 9c, and/or 9d).}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMLh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hMNh jhhubjl)}(hXO8 TO
Last region to be altered. This item is entered to specify the last region to be altered,
starting with the region specified by REG=. For example, assume unit 3 contains eight regions and you
wish to make changes to regions 4, 5, 6, 7, and 8. These regions are identified by entering the following data.
UNIT=3 REG=4 TO 8.
h](jl)}(h8 TOh]h/8 TO}(hjh jubah}(h]h]h]h]h]uhjlh!j)hMTh jubjl)}(hhh]h;)}(hXILast region to be altered. This item is entered to specify the last region to be altered,
starting with the region specified by REG=. For example, assume unit 3 contains eight regions and you
wish to make changes to regions 4, 5, 6, 7, and 8. These regions are identified by entering the following data.
UNIT=3 REG=4 TO 8.h]h/XILast region to be altered. This item is entered to specify the last region to be altered,
starting with the region specified by REG=. For example, assume unit 3 contains eight regions and you
wish to make changes to regions 4, 5, 6, 7, and 8. These regions are identified by entering the following data.
UNIT=3 REG=4 TO 8.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hMQh jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hMTh jhhubeh}(h]h]h]h]h]uhjlh jhhh!j)hNubh;)}(hXGeometric search constants. A search constant is the proportionality factor utilized to alter a geometry region.
A search constant must be entered for each surface of a region that is to be altered.
A nonzero search constant will cause the region dimension for that surface to be changed.
A search constant of 0.0 will cause the region dimension to remain unchanged.
The default value of the search constant is 0.0.h]h/XGeometric search constants. A search constant is the proportionality factor utilized to alter a geometry region.
A search constant must be entered for each surface of a region that is to be altered.
A nonzero search constant will cause the region dimension for that surface to be changed.
A search constant of 0.0 will cause the region dimension to remain unchanged.
The default value of the search constant is 0.0.}(hjh jhhh!NhNubah}(h]h]h]h]h]uhh:h!j)hMVh jhhubjl)}(hhh](jl)}(h9 ALL=
Search constant for all surfaces. All of the surfaces in a region are altered simultaneously by using this search command.
h](jl)}(h9 ALL=h]h/9 ALL=}(hjh jubah}(h]h]h]h]h]uhjlh!j)hM]h jubjl)}(hhh]h;)}(h{Search constant for all surfaces. All of the surfaces in a region are altered simultaneously by using this search command.h]h/{Search constant for all surfaces. All of the surfaces in a region are altered simultaneously by using this search command.}(hjh jubah}(h]h]h]h]h]uhh:h!j)hM]h jubah}(h]h]h]h]h]uhjlh jubeh}(h]h]h]h]h]uhjlh!j)hM]h jubjl)}(h9a. +X=
Search constant for +X face. This parameter is used to specify the value of the search constant for the +X face of a cuboid.
h](jl)}(h9a. +X=h]h/9a. +X=}(hj2h j0ubah}(h]h]h]h]h]uhjlh!j)hM`h j,ubjl)}(hhh]h;)}(hSearch constant for +X face. This parameter is used to specify the value of the search constant for the +X face of a cuboid.h]h/Search constant for +X face. This parameter is used to specify the value of the search constant for the +X face of a cuboid.}(hjCh jAubah}(h]h]h]h]h]uhh:h!j)hM`h j>ubah}(h]h]h]h]h]uhjlh j,ubeh}(h]h]h]h]h]uhjlh!j)hM`h jhhubjl)}(h9a. -X=
Search constant for −X face. This parameter is used to specify the value of the search constant for the −X face of a cuboid.
h](jl)}(h9a. -X=h]h/9a. -X=}(hjah j_ubah}(h]h]h]h]h]uhjlh!j)hMch j[ubjl)}(hhh]h;)}(hSearch constant for