Docs minus Keno

AMPXUtil.rst

+.. _11-1:
+
+AMPX Library Utility Modules
+============================
+
+*D. Wiarda, L. M. Petrie*
+
+Abstract
+
+The purpose of this section is to document selected AMPX modules that
+can benefit the analyst interested in editing, converting, or combining
+cross-section libraries normally used by the SCALE system modules. The
+input description for these codes is provided in the documentation of
+the AMPX nuclear data processing code system that is distributed with
+SCALE package.
+
+.. _11-1-1:
+
+Introduction
+------------
+
+AMPX is a modular system [1]_ that generates continuous energy (CE) and
+multigroup (MG) cross section data from evaluated nuclear data files
+such as ENDF/B. All the nuclear data libraries distributed with SCALE
+have been processed using AMPX. In addition to data processing modules,
+AMPX also includes a number of useful utility modules for checking,
+manipulating, and editing the libraries in SCALE. This section lists and
+briefly describes some of the AMPX utility codes that may be useful to
+SCALE users. Input instructions for these codes can be found the AMPX
+code documentation, which is distributed with the SCALE code package.
+Additional AMPX modules of interest may also found in the documentation.
+
+.. _11-1-2:
+
+AJAX: MODULE TO MERGE, COLLECT, ASSEMBLE, REORDER, JOIN, AND/OR COPY SELECTED DATA FROM AMPX MASTER LIBRARIES
+-------------------------------------------------------------------------------------------------------------
+
+AJAX (**A**\ utomatic **J**\ oining of **A**\ MPX **X**-Sections) is a
+module to combine data from different AMPX libraries. Options are
+provided to allow merging from any number of files.
+
+.. _11-1-3:
+
+ALPO: MODULE TO CONVERT AMPX LIBRARIES INTO ANISN FORMAT
+--------------------------------------------------------
+
+ALPO (**A**\ NISN **L**\ IBRARY **P**\ RODUCTION **O**\ PTION) is a
+module for converting AMPX working libraries into the library format
+used by the legacy discrete ordinates transport codes ANISN and
+DORT/TORT contained in the DOORS package. [2]_
+
+.. _11-1-4:
+
+CADILLAC: MODULE TO MERGE MULTIPLE COVARIANCE DATA FILES
+--------------------------------------------------------
+
+CADILLAC (**C**\ ombine **A**\ ll **D**\ ata **I**\ dentifiers
+**L**\ isted in **L**\ ogical **A**\ MPX **C**\ overx-format) is a
+module that can be used to combine multiple covariance data files in
+COVERX format into a single covariance data file. The material IDs can
+be changed as needed by the user.
+
+.. _11-1-5:
+
+COGNAC: MODULE TO CONVERT COVARIANCE DATA FILES IN COVERX FORMAT
+----------------------------------------------------------------
+
+COGNAC (**C**\ onversion **O**\ perations for **G**\ roup-dependent
+**N**\ uclides in **A**\ MPX **C**\ overx-format) is a module that can
+be used to convert a single COVERX-formatted data file from bcd format
+to binary. Also, COGNAC can be used to convert from binary to bcd,
+binary to binary, and bcd to bcd.
+
+.. _11-1-6:
+
+LAVA: MODULE TO MAKE AN AMPX WORKING LIBRARY FROM AN ANISN LIBRARY
+------------------------------------------------------------------
+
+LAVA (**L**\ et **A**\ NISN **V**\ isit **A**\ MPX) is a module that can
+convert an ANISN formatted library (neutron, gamma, or coupled
+neutron-gamma) to an AMPX working library that can be used in XSDRNPM.
+
+.. _11-1-7:
+
+MALOCS: MODULE TO COLLAPSE AMPX MASTER CROSS-SECTION LIBRARIES
+--------------------------------------------------------------
+
+MALOCS (**M**\ iniature **A**\ MPX **L**\ ibrary **O**\ f **C**\ ross
+**S**\ ections) is a module to collapse AMPX master cross-section
+libraries. The module can be used to collapse neutron, gamma-ray, or
+coupled neutron-gamma master libraries.
+
+.. _11-1-8:
+
+PALEALE: MODULE TO LIST INFORMATION FROM AMPX LIBRARIES
+--------------------------------------------------------
+
+PALEALE lists selected data by nuclide, reaction, data-type from AMPX
+master and working libraries.
+
+.. _11-1-9:
+
+RADE: MODULE TO CHECK AMPX CROSS-SECTION LIBRARIES
+--------------------------------------------------
+
+RADE (**R**\ ancid **A**\ MPX **D**\ ata **E**\ xposer) is provided to
+check AMPX- and ANISN-formatted multigroup libraries. It will check
+neutron, gamma, or coupled neutron-gamma libraries.
+
+.. _11-1-10:
+
+TOC: MODULE TO PRINT AN AMPX LIBRARY TABLE OF CONTENTS
+------------------------------------------------------
+
+Program TOC is a utility program to print a sorted table of contents of
+an AMPX cross section library. It is designed to be run interactively,
+with the cross section library specified as the argument.
+
+References
+~~~~~~~~~~
+
+.. [1]
+   D. Wiarda, M. L. Williams, C. Celik, and M. E. Dunn, “AMPX: A
+   Modern Cross Section Processing System For Generating Nuclear Data
+   Libraries,” *Proceedings of International Conference on Nuclear
+   Criticality Safety,* Charlotte, NC, Sept 13-17 2015.
+
+.. [2]
+   **“**\ \ DOORS3.2a:   One, Two- and Three-Dimensional Discrete
+   Ordinates Neutron/Photon Transport Code System”, Radiation Shielding
+   Information Center package CCC-650, Oak Ridge National Laboratory
+   (2003).

CENTRM.rst

@@ -848,7 +848,7 @@ The limits on the above integral correspond to:
   \alpha_{\mathrm{L}}\left(\mathrm{E}^{\prime}, \mathrm{E}\right)=\alpha\left(\mathrm{E}^{\prime}, \mathrm{E}, \mu_{0}=-1\right) \quad \text { and } \quad \alpha_{\mathrm{H}}\left(\mathrm{E}^{\prime}, \mathrm{E}\right)=\alpha\left(\mathrm{E}^{\prime}, \mathrm{E}, \mu_{0}=1\right) .
 
 The alpha moments for n > 0 can be evaluated very efficiently using a
-recursive relation :cite:`illiams_submoment_2000`:
+recursive relation :cite:`williams_submoment_2000`:
 
 .. math::
 

COMPOZ.rst

+.. _11-3:
+
+COMPOZ Data Guide 
+=================
+
+*J. R. Knight* [1]_ *and L. M. Petrie* 
+
+ABSTRACT
+
+The COMPOZ program used to create the Standard Composition Library is
+described. Of particular importance is documentation of the COMPOZ input
+data file structure. Knowledge of the file structure allows users to
+edit the data file and subsequently create their own site-specific
+composition library.
+
+
+ACKNOWLEDGMENT
+
+This work was originally funded by the Office of Nuclear Material Safety
+and Safeguards of the U.S. Nuclear Regulatory Commission.
+
+.. _11-3-1:
+
+Introduction
+------------
+
+COMPOZ is the program that creates (writes) the SCALE Standard
+Composition Library. Data are input in free form. A text data file
+containing the input to COMPOZ (and the Standard Composition Library) is
+available with the SCALE system. Execution of COMPOZ using this data
+file creates the Standard Composition Library currently available with
+the SCALE package. This section provides documentation of the data file
+structure. Knowledge of the data file structure allows users to edit the
+data file and subsequently create their own site-specific or
+user-specific composition library.
+
+COMPOZ is intended to create or make *permanent* *changes* to and/or to
+print the composition library and should not be used for any other
+purpose. To avoid confusion with the Standard Composition Library
+provided with SCALE, it is strongly recommended that only *new* keywords
+and compositions be used in any site-specific or user-specific library.
+
+.. _11-3-2:
+
+Input Data Description
+----------------------
+
+COMPOZ input data are entered in free form. All data must be followed by
+at least one blank. The COMPOZ input data file contains *five* data
+records or blocks:
+
+1. COMPOZ mode flag selects whether a new standard composition library
+   will be created, or an old standard composition library will be
+   listed. Only if a new library is being created are the following data
+   records entered. A new library is created with a filename of
+   “xfile089”. If an old library is being dumped as an ASCII file, it
+   will be named “_sclN…N” where N…N is an 18 digit sequence number that
+   is incremented starting from 0 for each library dumped in the same
+   directory.
+
+2. The header record contains the library identification, a set of
+   parameters describing the size of the library, and library title with
+   80 characters per line.
+
+3. The standard composition table contains the name, theoretical
+   density, number of elements, and other information about each
+   standard composition. Individual nuclides, mixtures, and compounds
+   are all included in the table.
+
+4. The nuclide information table contains the nuclide identification
+   number, atomic mass, and resonance energy cross sections.
+
+5. The isotopic distribution table contains the nuclide identification
+   number and the atom percent of each isotope used in specifying the
+   default enrichment.
+
+.. note:: For executing COMPOZ via SCALE, an =COMPOZ is required in the
+  first eight columns of a record preceding the mode flag, and an END is
+  required in the first three columns of a record inserted after the last
+  data record. If debug output is desired, then use =COMPOZ PRINTDEBUG to
+  execute compoz.
+
+.. _11-3-2-1:
+
+COMPOZ mode selector
+~~~~~~~~~~~~~~~~~~~~
+
+1. LGEN =
+
+  0 – create a new library and list it
+
+  1 – list an existing library
+
+  >1 – list an existing library and write an ASCII input file.
+
+If LGEN is 0, then input the following data to create a new standard
+composition library.
+
+.. _11-3-2-2:
+
+Library heading information
+~~~~~~~~~~~~~~~~~~~~~~~~~~~
+
+1. IDT – library identification number
+
+2. TITLE – 1 line of 80 characters used to identify the library
+
+.. _11-3-2-3:
+
+Standard composition table
+~~~~~~~~~~~~~~~~~~~~~~~~~~
+
+1. SCID – Composition name, maximum of 12 characters.
+
+2. ROTH – Theoretical density, gm/cm\ :sup:`3`.
+
+3. ICP –
+
+  0 for a mixture,
+
+  1 for a compound.
+
+4. NCZA – Element or nuclide ID
+
+5. ATPM – Weight percent if ICP = 0. Number of atoms per molecule if ICP = 1.
+
+6. END – Keyword END to terminate this standard composition.
+
+For each composition, items 4 and 5 are repeated until all components of
+the composition are described. Items 1 through 6 are entered in a
+similar fashion for all compositions. After all the standard
+compositions are read, terminate the table with an END [label], where
+[label] represents an optional label.
+
+.. _11-3-2-4:
+
+Nuclide information table
+~~~~~~~~~~~~~~~~~~~~~~~~~
+
+1. NZA – Nuclide ID. This should be the mass number + 1000 \* the atomic
+number.
+
+2. AM – Atomic mass, C-12 scale.
+
+3. SIGS – Resonance energy scattering cross section, barns.
+
+4. SIGT – Resonance energy total cross section, barns.
+
+5. NU*SIGF – Resonance energy nu*sigf cross section, barns.
+
+The resonance energy cross sections are averaged over the appropriate
+energy range for the nuclide. Items 1–5 are repeated for all nuclides.
+After all nuclides are entered, terminate the nuclide table with an END
+[label].
+
+.. _11-3-2-5:
+
+Isotopic distribution table
+~~~~~~~~~~~~~~~~~~~~~~~~~~~
+
+1. NZN – 1000 \* atomic number of variable isotope elements.
+
+2. ISZA – Isotope ID.
+
+3. ABWP – Default abundance, atom percent.
+
+4. END – Keyword END to terminate this isotopic specification.
+
+The default abundance is generally the naturally occurring abundance.
+For each element, items 2 and 3 are repeated until 100% total abundance
+is described, making a set for this element. The next element is
+described in the same fashion in the next set, etc. After all isotopic
+distributions are entered, terminate the isotopic distribution table
+with an END [label].
+
+.. _11-3-3:
+
+Sample Problem
+--------------
+
+The following sample problem first lists the SCALE standard composition
+library, then creates a new, short standard composition library, then
+lists and outputs an ASCII copy of this new library, and finally copies
+this new copy back to the output directory.
+
+.. code:: scale
+  :class: long
+
+    =compoz
+  '  print the current standard composition library
+      1
+  end
+  =compoz
+  '  create a new standard composition library
+      0
+  '  library identification number
+    101
+  '  library title
+  scale-X standard composition library
+  '  standard composition table
+  '  all nuclide IDs here must be in the nuclide table
+      h               1.0000    0        1001 100.0000 end
+      o               1.0000    0        8016 100.0000 end
+      u              19.0500    0       92000 100.0000 end
+      h2o             0.9982    1        1001    2
+                                         8016    1 end
+      uo2            10.9600    1       92000    1
+                                         8016    2 end
+  '  end of standard composition table
+     end stdcmp
+  '  nuclide table
+  '    ID       AWR     SigmaS      SigmaT      nuSigmaF
+     1001   1.00783    20.38087    20.38782     0.00000
+     1002   2.01410     3.39486     3.39487     0.00000
+     8016  15.99491     3.88696     3.88696     0.00000
+     8017  16.99913     3.74000     3.74501     0.00000
+     8018  17.99916     3.79000     3.79000     0.00000
+    92233 233.03964    12.46693    37.62292   100.78482
+    92234 234.04095    12.18716    16.09542     2.66969
+    92235 235.04393    11.90249    35.22383    90.23152
+    92236 236.04556    12.27302    14.93351     1.33334
+    92237 237.04874    14.24581    24.68619     1.93695
+    92238 238.05080    12.32636    14.62708     0.65970
+  '  end of nuclide table
+     end nuclides
+  '  isotope distribution table
+  '  all nuclide IDs here must be in the nuclide table
+     1000   1001  99.9885
+            1002   0.0115 end
+     8000   8016  99.7570
+            8017   0.0380
+            8018   0.2050 end
+    92000  92234   0.0054
+           92235   0.7204
+           92238  99.2742 end
+  '  end of isotope distribution table
+      end isotopes
+  '  end of compoz input
+  end
+  =compoz
+  '  print and create an ASCII copy of the current standard composition library
+  '  (created in the previous step)
+    2
+  end
+  =shell
+   # copy the ASCII copy back to the output directory
+    copy_file _scl000000000000000000 ${OUTBASE}.stdcmplib
+  end
+
+.. [1]
+   Formerly with Oak Ridge National Laboratory.

COVLIBAppA.rst

+.. _10-2a:
+
+COVLIB Appendix A: Cross section plots for U, Pu, TH, B, H, He, and Gd Nuclides
+===============================================================================
+
+Plots of cross section differences between various evaluations are shown
+below. The legend below applies to all plots shown in this appendix.
+
+.. image:: figs/COVLIBAppA/img1.png
+  :align: center
+  :width: 500
+
+.. _fig10-2a-1:
+.. figure:: figs/COVLIBAppA/fig1.png
+  :align: center
+  :width: 600
+
+  :sup:`239`\ Pu fission and capture comparison between ENDF/B-VI,
+  JENDL 3.3, and JEF 3.1.
+
+.. _fig10-2a-2:
+.. figure:: figs/COVLIBAppA/fig2.png
+  :align: center
+  :width: 600
+
+  :sup:`240`\ Pu fission and capture comparison between ENDF/B-VI,
+  JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-3:
+.. figure:: figs/COVLIBAppA/fig3.png
+  :align: center
+  :width: 600
+
+  :sup:`241` fission and capture comparison between ENDF/B-VI,
+  JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-4:
+.. figure:: figs/COVLIBAppA/fig4.png
+  :align: center
+  :width: 600
+
+  :sup:`233` fission and capture comparison between ENDF/B-VI,
+  JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-5:
+.. figure:: figs/COVLIBAppA/fig5.png
+  :align: center
+  :width: 600
+
+  :sup:`235` fission and capture comparison between ENDF/B-VI,
+  JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-6:
+.. figure:: figs/COVLIBAppA/fig6.png
+  :align: center
+  :width: 600
+
+  :sup:`238`\ U capture comparison between ENDF/B-VI, JENDL 3.3
+  and JEF 3.1.
+
+.. _fig10-2a-7:
+.. figure:: figs/COVLIBAppA/fig7.png
+  :align: center
+  :width: 600
+
+  :sup:`232`\ Th capture comparison between ENDF/B-VII
+  (beta2), ENDF/B‑VI, JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-8:
+.. figure:: figs/COVLIBAppA/fig8.png
+  :align: center
+  :width: 600
+
+  :sup:`10`\ B capture and :sup:`3`\ He elastic comparison
+  between ENDF/B-VII (beta2), ENDF/B-VI, JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-9:
+.. figure:: figs/COVLIBAppA/fig9.png
+  :align: center
+  :width: 600
+
+  :sup:`1`\ H and :sup:`2`\ H elastic comparison between
+  ENDF/B-VII (beta2), ENDF/B-VI, JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-10:
+.. figure:: figs/COVLIBAppA/fig10.png
+  :align: center
+  :width: 600
+
+  :sup:`152`\ Gd and :sup:`154`\ Gd capture comparison
+  between ENDF/B-VII (beta2), ENDF/B-VI, JENDL 3.3 and JEF 3.1.
+
+.. _fig10-2a-11:
+.. figure:: figs/COVLIBAppA/fig11.png
+  :align: center
+  :width: 500
+
+  :sup:`155`\ Gd capture comparison between ENDF/B-VII
+  (beta2), ENDF/B-VI, JENDL 3.3 and JEF 3.1.

CRAWDAD.rst

@@ -10,7 +10,7 @@ ACKNOWLEDGMENTS
 The authors would like to acknowledge the important contributions to
 CRAWDAD made by former ORNL staff N. M. Greene and D. F. Hollenbach.
 
-.. _7-1:
+.. _7-7-1:
 
 Introduction
 ------------

Depletion, Activation, and Spent Fuel Source Terms Overview.rst

+.. _5-0:
+
+Depletion, Activation, and Spent Fuel Source Terms Overview
+===========================================================
+
+*Introduction by W. A. Wieselquist*
+
+SCALE’s general depletion, activation, and spent fuel source terms analysis
+capabilities are enabled through a family of modules related to the main ORIGEN
+depletion/irradiation/decay solver. The nuclide tracking in ORIGEN is based on
+the principle of explicitly modeling all available nuclides and transitions in
+the current fundamental nuclear data for decay and neutron-induced transmutation
+and relies on fundamental cross section and decay data in ENDF/B VII. Cross
+section data for materials and reaction processes not available in ENDF/B-VII
+are obtained from the JEFF-3.0/A special purpose European activation library
+containing 774 materials and 23 reaction channels with 12,617 neutron-induced
+reactions below 20 MeV. Resonance cross section corrections in the resolved and
+unresolved range are performed using a continuous-energy treatment by data
+modules in SCALE. All nuclear decay data, fission product yields, and gamma-ray
+emission data are developed from ENDF/B-VII.1 evaluations. Decay data include
+all ground and metastable state nuclides with half-lives greater than 1
+millisecond. Using these data sources, ORIGEN currently tracks 174 actinides,
+1149 fission products, and 974 activation products. The purpose of this chapter
+is to describe the stand-alone capabilities and underlying methodology of
+ORIGEN—as opposed to the integrated depletion capability it provides in all
+coupled neutron transport/depletion sequences in SCALE, as described in other
+chapters. Through the stand-alone capabilities, there is generality to handle
+arbitrary systems (e.g., fast reactor fuel depletion or structural activation)
+by providing arbitrary flux spectra and arbitrary one-group cross sections to
+the module COUPLE, which in turn creates ORIGEN library (.f33) files containing
+the problem-dependent, one-group reaction coefficients required to solve the
+actual equations governing depletion/decay. These libraries are required input
+for the ORIGEN module, along with the initial isotopics and irradiation history,
+in terms of either a time-dependent power or flux level. Two high-performance
+equation solvers are available: the hybrid linear chains and matrix exponential
+method and a new Chebyshev Rational Approximation Method (CRAM). Typical
+execution times are on the order of a few seconds for a multi-step solution,
+with each individual solution (step) taking approximately 10 milliseconds.
+ORIGEN also includes capabilities for continuous feed and removal by element.
+Output capabilities include isotopics (moles or grams), source spectra (alpha,
+beta, gamma, and neutron), activity (becquerels or curies), decay heat (total
+watts or gamma only), and radiological hazard factors (maximum permissible
+concentrations in air or water). These results can be displayed in the output
+file (.out extension) and/or archived in an ORIGEN binary results file (.f71
+extension). The use of current, fundamental data resources is a key feature of
+ORIGEN, including nuclear decay data, multigroup neutron reaction cross
+sections, neutron-induced fission product yields, and decay emission data for
+photons, neutrons, alpha particles, and beta particles. The nuclear decay data
+are based primarily on ENDF/B-VII.1 evaluations. The multigroup nuclear reaction
+cross section libraries now include evaluations from the JEFF 3.0/A neutron
+activation file containing data for 774 target nuclides, more than 12,000
+neutron-induced reactions, and more than 20 different reaction types below 20
+MeV, provided in various energy group structures. Energy-dependent
+ENDF/B-VII.0-based fission product yields are available for 30 fissionable
+actinides. Gamma-ray and x-ray emission data libraries are based on
+ENDF/B-VII.1. The photon libraries contain discrete photon line energy and
+intensity data for decay gamma-ray and x-rays emission for 1,132 radionuclides,
+prompt and delayed continuum spectra for spontaneous fission, (α,n) reactions in
+oxide fuel, and bremsstrahlung from decay beta (electron and positron) particles
+slowing down in either a UO2 fuel or water matrix. Methods and data libraries
+used to calculate the neutron yields and energy spectra for spontaneous fission,
+(α,n) reactions, and delayed neutron emission are adopted from the SOURCES4C
+code. Capabilities to calculate the beta and alpha particle emission source and
+spectra have also been added.
+
+The ORIGEN reactor libraries distributed with SCALE include a set of
+pre-calculated ORIGEN libraries (with TRITON) for a variety of fuel assembly
+designs:
+
+  -	BWR 7×7, 8×8-1, 8×8-2, 9×9-2, 9×9-9, 10×10-9, 10×10-8, SVEA-64,
+    SVEA-96, and SVEA-100;
+
+  -	PWR 14×14, 15×15, 16×16, 17×17, 18×18;
+
+  -	CANDU reactor (19-, 28-, and 37-element bundle designs);
+
+  -	Magnox graphite reactor;
+
+  -	Advanced Gas-Cooled Reactor (AGR);
+
+  -	VVER 440 and VVER 1000;
+
+  -	RBMK;
+
+  -	IRT;
+
+  -	MOX BWR 7×7, 8×8-1, 8×8-2, 9×9-2, 9×9-9, 10×10-9, 10×10-8, SVEA-64, SVEA-96, and
+    SVEA-100;
+
+  -	MOX PWR 14×14, 15×15, 16×16, 17×17, 18×18.
+
+These libraries may be
+used to rapidly assess spent fuel isotopics and source terms in these systems
+for arbitrary burnups and decay times. For UO2-based assembly isotopics, the new
+ORIGAMI sequence provides a very convenient, easy-to-use interface. The most
+general capability, and requiring more user input, is available using the ARP
+interpolator module in conjunction with the ORIGEN solver module. Finally, with
+regards to user interfaces, ORIGEN has a new keyword-based input in SCALE 6.2
+but also maintains the ability to read SCALE 6.1 input. Both ORIGEN and ORIGAMI
+are tightly integrated with the SCALE graphical user interface, Fulcrum, which
+includes syntax highlighting, input checking with immediate feedback, and (.f71)
+output viewing. Additionally, Fulcrum provides an ORIGAMI Automator project
+interface to characterize the fuel inventory for an entire reactor site and
+generate data needed for severe accident analysis. ORIGAMI Automator is not
+documented in this chapter, but a primer is available with step by step
+instructions on its use.

Deterministic Transport Intro.rst

+Deterministic Transport Overview
+================================
+
+*Introduction by S. M. Bowman*
+
+SCALE deterministic transport capabilities enable criticality safety,
+depletion, sensitivity, and uncertainty analysis, as well as hybrid
+approaches to Monte Carlo analysis. SCALE provides a one-dimensional
+(1D) transport solver for eigenvalue neutronics and fixed source
+neutron-gamma analysis with XSDRN, two-dimensional (2D) eigenvalue
+neutronics with NEWT, and a three-dimensional (3D) transport solver for
+hybrid acceleration of Monte Carlo fixed source and eigenvalue
+calculations with Denovo. Generally, the use of these transport solvers
+in SCALE is best accessed through the capability specific sequences:
+CSAS and Sourcerer for criticality safety, TRITON for 1D and 2D
+depletion, TSUNAMI‑1D and TSUNAMI-2D for sensitivity and uncertainty
+analysis, and MAVRIC for 3D fixed source hybrid Monte Carlo analysis.
+
+XSDRN
+-----
+
+XSDRN is a multigroup discrete-ordinates code that solves the 1D
+Boltzmann equation in slab, cylindrical, or spherical coordinates.
+Alternatively, the user can select P1 diffusion theory, infinite medium
+theory, or Bn theory. A variety of calculational types is available,
+including fixed source, eigenvalue, or search calculations. In SCALE,
+XSDRN is used for several purposes: eigenvalue (*k*\ :sub:`eff`) determination;
+cross section collapsing; and computation of fundamental-mode or
+generalized adjoint functions for sensitivity analysis.
+
+NEWT
+----
+
+NEWT (New ESC-based Weighting Transport code) is a multigroup
+discrete-ordinates radiation transport computer code with flexible
+meshing capabilities that allow 2D neutron transport calculations using