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<div class="section" id="scale-nuclear-data-covariance-library">
<span id="id1"></span><h1>SCALE Nuclear Data Covariance Library<a class="headerlink" href="#scale-nuclear-data-covariance-library" title="Permalink to this headline"></a></h1>
<p><em>M. L. Williams, D. Wiarda, G. Arbanas, and B. L. Broadhead</em></p>
<p>ABSTRACT</p>
<p>An updated cross section covariance library has been created for use
with the sensitivity and uncertainty modules in SCALE 6.2. The data has
been assembled from a variety sources, including high-fidelity
covariance evaluations from ENDF/B-VII.1 as well as approximate
uncertainties obtained from a collaborative project performed by
Brookhaven National Laboratory, Los Alamos National Laboratory, and Oak
Ridge National Laboratory. This document describes the assumptions in
generating the data, the library contents, and processing procedure for
the SCALE 56-group and 252-group covariance libraries. The SCALE
44-group covariance library distributed with SCALE 6.0 and SCALE 6.1 is
retained for backwards compatibility.</p>
<p>ACKNOWLEDGMENT</p>
<p>We gratefully acknowledge the sponsorship of the US Department of Energy
Nuclear Criticality Safety Program in the development of the SCALE 6.2
covariance libraries.</p>
<div class="section" id="introduction">
<span id="id2"></span><h2>Introduction<a class="headerlink" href="#introduction" title="Permalink to this headline"></a></h2>
<p>The SCALE 6.2 covariance library is based on available ENDF/B-VII.1 <a class="bibtex reference internal" href="XSLib.html#chadwick-endfb-vii-2011" id="id3">[CHO+11]</a>
data for 187 nuclides, combined with the previous SCALE 6.1 covariance
data are retained for the ~215 nuclides not available in ENDF/B‑VII.1.
The ENDF/B-VII.1 uncertainties were modified for a few nuclides, as
described in <a class="reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#id47"><span class="std std-ref">Modifications to covariance data</span></a>. In addition, the covariance library now has
a 56-group structure for broad group analysis, as well as the 252-group
structure for fine-group analysis. These covariance libraries were
generated for compatibility with the ENDF/B-VII.1 cross section
libraries distributed with SCALE 6.2, and they may also be applied for
the 238-group ENDF/B-VII.0 library. The previous SCALE 6.0 and SCALE 6.1
44‑group library (44groupcov) was based on older covariance data and is
retained in SCALE 6.2 for backwards compatibility. However, the 56- and
252-group covariance libraries (56groupcov7.1 and 252groupcov7.1) are
now recommended for all applications. The 56-group library—which is
default for SCALE uncertainty analysis—and the 252 fine-group library
generally produce similar results, except for some threshold reactions
such as (n,2n). The 252-group library may be used to improve uncertainty
estimates from these types of data, but it typically takes more
execution time than the default 56-group library. Because the 56- and
252-group covariance data in many cases are based on newer uncertainty
evaluations than the previous 44-group library, some differences will
occur between these sets of results.</p>
<p>The covariance data correspond to relative uncertainties assembled from
a variety of sources, including evaluations from ENDF/B-VII.1,
ENDF/B-VI, and approximated uncertainties from a collaborative project
performed by Brookhaven National Laboratory (BNL), Los Alamos National
Laboratory (LANL), and Oak Ridge National Laboratory (ORNL). Because
SCALE uncertainty data come from several different sources, the
application of a single generic covariance library to all multigroup
cross section libraries raises questions about consistency with any
given data evaluation. In reality, much of the approximate uncertainty
data in the library is based on simplifying approximations that do not
depend on specific ENDF evaluations and thus can be applied to all cross
section libraries within the limitations of the assumed methodology. In
other cases in which a covariance evaluation has been taken from a
specific nuclear data file (e.g., ENDF/B-VII.1, ENDF/B-VI, or JENDL), it
is assumed that the same <em>relative</em> (rather than <em>absolute</em>)
uncertainties can be applied to all cross section libraries, even if
these are not strictly consistent with the nuclear data evaluations. The
assumption is partially justified by the fact that different evaluations
often use many of the same experimental measurements since there is a
limited amount of this information available. In some cases, older data
evaluations have been carried over into the newer ENDF versions. Also,
because many important nuclear data are now known rather well, newer
evaluations in many instances correspond to rather modest variations
from previous ones and are expected to lie within the earlier
uncertainties. As shown by plots in <span class="xref std std-ref">11-3a</span>, the nuclear data
evaluations from ENDF/B-VII, ENDF/B-VI, JEF-3.1, and JENDL-3.3 tend to
agree well for many types of cross sections, so it is reasonable to
assume that the uncertainties in these data are similar.</p>
<p>No inherently “true” uncertainty can be defined for nuclear data. For
example, in theory, two independent evaluations could produce similar
nuclear data with very different uncertainties. Differences in nuclear
data evaluations directly impact calculations that can be affirmed by
comparisons with benchmark experiments; but there is no established
procedure to quantify the reliability of uncertainty estimates. In
general, the SCALE covariance library should be viewed as a
best-estimate assessment of data uncertainties based upon the specific
methodology described in the following section. While this methodology
is not unique and other approaches could have been used, the SCALE
covariance library is a reasonable representation of the nuclear data
uncertainties for most applications given the current lack of
information. Furthermore, it is the only available comprehensive library
that has been created in a well-defined, systematic manner.</p>
</div>
<div class="section" id="covariance-data-description">
<span id="id4"></span><h2>Covariance Data Description<a class="headerlink" href="#covariance-data-description" title="Permalink to this headline"></a></h2>
<div class="section" id="evaluated-covariances-from-nuclear-data-files">
<span id="id5"></span><h3>Evaluated covariances from nuclear data files<a class="headerlink" href="#evaluated-covariances-from-nuclear-data-files" title="Permalink to this headline"></a></h3>
<p>A rigorous, modern evaluation of nuclear data typically uses a
regression algorithm that adjusts parameters in a nuclear physics model
(e.g., Reich-Moore resonance formula, optical model, etc.), to fit a set
of differential experimental measurements that have various sources of
statistical and systematic uncertainties <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#larson-systematic-2006" id="id6">[LLD+06]</a>. Information from the
regression analysis of the model parameters can be propagated to
uncertainties and correlations in the evaluated differential data. In
this manner, the differential nuclear data and covariances are
consistent and are coupled together by evaluation processes.
Unfortunately, only a limited number of cross section evaluations have
produced high-fidelity covariances in this rigorous manner. All other
nuclear data uncertainties must be estimated from approximations in
which the uncertainty assessment is decoupled from the original
evaluation procedure.</p>
<p>The SCALE covariance library is based on several different uncertainty
approximations with varying degrees of fidelity relative to the actual
nuclear data evaluation. The library includes high-fidelity evaluated
covariances obtained from ENDF/B-VII.1, and ENDF/B-VI whenever
available. As discussed in <a class="reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#id31"><span class="std std-ref">Introduction</span></a>, it is assumed that covariances
taken from one data evaluation, such as ENDF/B-VI, can also be applied
to other evaluations of the same data, such as ENDF/B-VII.1. If this is
done judiciously for cases in which the nuclear data evaluations are
similar, then the covariances taken from one source should be a
reasonable representation of uncertainties for the other evaluations.</p>
</div>
<div class="section" id="approximate-covariance-data">
<span id="id7"></span><h3>Approximate covariance data<a class="headerlink" href="#approximate-covariance-data" title="Permalink to this headline"></a></h3>
<p>At the other end of the spectrum from high fidelity data, low-fidelity
(lo-fi) covariances are defined to be those estimated independently of a
specific data evaluation. The approximate covariance data in SCALE are
based on results from a collaborative project funded by the US
Department of Energy Nuclear Criticality Safety Program to generate
lo-fi covariances over the energy range from 10<sup>-5</sup> eV to 20 MeV
for materials without covariances in ENDF/B-VII.1. Nuclear data experts
at BNL, LANL, and ORNL devised simple procedures to estimate data
uncertainties in the absence of high fidelity covariance evaluations.
The result of this project is a set of covariance data in ENDF/B file 33
format that can be processed into multigroup covariances <a class="bibtex reference internal" href="Sensitivity%20and%20Uncertainty%20Analysis%20Overview.html#little-low-fidelity-2008" id="id8">[LKH+08]</a>. Some of
these data were later revised and included in ENDF/B‑VII.1, while others
were carried over from SCALE 6.1 to the SCALE 6.2 library. In this
documentation, these data are known as BLO (BNL-LANL-ORNL) uncertainty
data, which were generated as described below.</p>
<p>ORNL used uncertainties in integral experiment measurements of thermal
cross sections, resonance integrals, and potential cross sections to
approximate the standard deviations of capture, fission, and elastic
scattering reactions for the thermal (&lt;0.5 eV) and resonance ranges (0.5
eV- 5 keV). Full energy correlation was assumed for the covariances
within each of these respective ranges <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#williams-approximate-2007" id="id9">[WBDR07]</a><a class="bibtex reference internal" href="Sensitivity%20and%20Uncertainty%20Analysis%20Overview.html#id366" id="id10">[WR08]</a> This
procedure was originally introduced for the approximate uncertainty data
in SCALE 5.1. However, the current version includes updated integral
measurement uncertainties, using the more recent values tabulated by
Mughabghab in the <em>Atlas of Neutron Resonances</em> <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#mughabghab-atlas-2006" id="id11">[Mug06]</a>. The lo-fi relative
uncertainty is computed as the absolute uncertainty in the integral
parameter (i.e., thermal cross section or resonance integral) taken from
the <em>Atlas</em>, divided by the average of the measured parameter and the
calculated value computed from ENDF/B-VII differential data:</p>
<div class="math notranslate nohighlight" id="equation-eq10-2-1">
<span class="eqno">()<a class="headerlink" href="#equation-eq10-2-1" title="Permalink to this equation"></a></span>\[\mathrm{U}=\frac{\Delta_{\mathrm{I}}}{0.5 \times\left(\mathrm{X}_{\mathrm{I}}+\mathrm{X}_{\mathrm{D}}\right)} ,\]</div>
<p>where:</p>
<blockquote>
<div><p>U is the relative lo-fi uncertainty included in SCALE,</p>
<p>Δ<sub>I</sub> is the absolute uncertainty in the integral measurement
(obtained from Mughabghab), and</p>
<p>X<sub>I</sub> and X<sub>D</sub> are the measured and computed (from
ENDF/B differential data) integral parameter values, respectively.</p>
</div></blockquote>
<p>In some cases the integral measurement value from the Mughabghab
<em>Atlas</em><sup>6</sup> and the corresponding value computed from the
ENDF/B-VII differential evaluation are inconsistent—defined here as
having a difference greater than two standard deviations in the measured
and computed integral parameters. In these cases, the lo-fi relative
standard deviation is defined as half the difference relative to the
average of the measured and calculated values:</p>
<div class="math notranslate nohighlight" id="equation-eq10-2-2">
<span class="eqno">()<a class="headerlink" href="#equation-eq10-2-2" title="Permalink to this equation"></a></span>\[\mathrm{U}=\frac{\left|\mathrm{X}_{\mathrm{I}}-\mathrm{X}_{\mathrm{D}}\right|}{\mathrm{X}_{\mathrm{I}}+\mathrm{X}_{\mathrm{D}}} ; \text { for }\left|\mathrm{X}_{\mathrm{I}}-\mathrm{X}_{\mathrm{D}}\right|&gt;2 \Delta_{\mathrm{I}} .\]</div>
<p>In some instances this expression may exceed 100%. For these cases, a
100% uncertainty was assigned. Also, the <em>Atlas</em> does not include
uncertainties in integral measurements for several isotopes, which
typically are not of great interest for most applications. In this case
the integral uncertainty was defined as a +/-5 in the least significant
digit for these materials; e.g., 1.23 is assign an uncertainty of +/-
5E-3.</p>
<p>BNL and LANL provided estimates in the fast energy range from 5 keV to
20 MeV for covariances of capture, fission, elastic, inelastic, (n,2n)
cross sections, and prompt nubar. BNL used optical model calculations
with estimated uncertainties in model parameters to compute covariances
in the fast range for about 300 structural isotopes, fission products,
and non-fissionable heavy nuclei. Estimated uncertainties in model
parameters were based on previous work and expert judgment <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#pigni-extensive-2009" id="id12">[PHO09]</a>.
Covariances for 14 actinide isotopes were obtained from earlier work
performed by BNL for Subgroup-26 (SG-26) <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#rochman-preliminary-2007" id="id13">[RHOM07]</a>. The SG-26 actinide
covariances cover the full energy range, including thermal, resonance,
and fast regions. If the thermal data uncertainties estimated by the
SG-26 approach exceed the thermal uncertainty given in reference 6, the
thermal data covariances are represented by ORNL’s integral uncertainty
technique.</p>
<p>LANL produced covariances in the fast range for an additional 47
actinide materials. The LANL actinide covariances were based on
empirical estimates of nuclear reaction models <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#kawano-evaluation-2008" id="id14">[KTY+08]</a>. Full energy range
covariances were also produced by LANL for 16 light isotopes ranging
from hydrogen to fluorine <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#hale-covariances-2008" id="id15">[Hal08]</a>. These included high fidelity
covariances from R-matrix analyses for <sup>1</sup>H, <sup>6</sup>Li, and
<sup>10</sup>B, along with lo-fi uncertainties for the other materials,
based on approximations such as least-squares fitting to experimental
data, statistical model calculations at higher energies, or sometimes
simply best-judgment estimation <a class="bibtex reference internal" href="Sensitivity%20and%20Uncertainty%20Analysis%20Overview.html#little-low-fidelity-2008" id="id16">[LKH+08]</a>.</p>
</div>
<div class="section" id="modifications-to-covariance-data">
<span id="id17"></span><h3>Modifications to covariance data<a class="headerlink" href="#modifications-to-covariance-data" title="Permalink to this headline"></a></h3>
<p>In generating earlier covariance libraries, some omissions or
inconsistencies were identified and corrected in the current covariance
library:</p>
<ul class="simple">
<li><p>If the absolute correlation is larger than 1, it is set to 1.</p></li>
<li><p>If a relative uncertainty is larger than 1, it is set to 1.</p></li>
<li><p>If cross section data exist but covariance data do not span the
entire range, then the diagonal element for the higher energy groups
is repeated for the lower energy groups.</p></li>
<li><p>If total inelastic scattering covariance is not supplied, it is
calculated from the uncertainties in the discrete level inelastic
data.</p></li>
<li><p>If total nubar covariance is not supplied, it is calculated from the
the prompt and delayed nubar uncertainties</p></li>
</ul>
<p>A few inconsistencies were found in the ENDF/B-VII.1 uncertainty data,
and these were modified for the SCALE 6.2 covariance library <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#williams-applications-2014" id="id18">[WIMR14]</a>. The
corrections were also conveyed to the National Nuclear Data Center,
where they were added to the ENDF/A file for possible inclusion in the
future release of ENDF/B-VII.2. These modifications are summarized
below:</p>
<ol class="loweralpha simple">
<li><p><sup>235</sup>U thermal nubar: standard deviation was decreased from
0.7% to 0.3% in energy range from 0.0 to 0.5 eV, consistent with
JENDL-3.3.</p></li>
<li><p><sup>239</sup>Pu thermal nubar: standard deviation was increased from
0.01% to 0.15% in energy range from 0.0 to 0.01 eV, consistent with
ENDF/B-VII.1 uncertainty at 0.01 eV.</p></li>
<li><p>H thermal capture: standard deviation reduced from 2.5% to 0.2%,
consistent with Williams and Rearden 2008 <a class="bibtex reference internal" href="Sensitivity%20and%20Uncertainty%20Analysis%20Overview.html#id366" id="id19">[WR08]</a>,</p></li>
</ol>
<p>(d) <sup>103</sup>Rh thermal capture: reduced from ~4% to 1.04%,
consistent with Williams and Rearden 2008 <a class="bibtex reference internal" href="Sensitivity%20and%20Uncertainty%20Analysis%20Overview.html#id366" id="id20">[WR08]</a>.</p>
<p>(e) <sup>151</sup>Sm thermal capture: modified to ~1.8%, consistent with
Williams and Rearden 2008 <a class="bibtex reference internal" href="Sensitivity%20and%20Uncertainty%20Analysis%20Overview.html#id366" id="id21">[WR08]</a>.</p>
<p>(f) <sup>147</sup>Pm: standard deviation was reduced from 24% to 5% in the
energy range 0.5–5000 eV, consistent with the quoted resonance integral
uncertainty in Williams and Rearden 2008 <a class="bibtex reference internal" href="Sensitivity%20and%20Uncertainty%20Analysis%20Overview.html#id366" id="id22">[WR08]</a>.</p>
<p>Several modifications were also made to the uncertainties obtained from
the original BLO data used in SCALE 6.1. The energy boundary between the
thermal and resonance covariance blocks was modified from 0.5 to 0.625
eV in order to coincide with a 56-group boundary. The BLO lo-fi data do
not include thermal or resonance range uncertainties for isotope
reactions that do not have integral uncertainties given in the
Mughabghab text <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#mughabghab-atlas-2006" id="id23">[Mug06]</a>. These occur mainly for relatively unimportant
data such as elastic cross sections of several fission products.
Therefore in these cases the uncertainties were estimated using
different approaches. For example, the thermal data uncertainty was
sometimes used to represent the epithermal uncertainty if it was not
available in the Mughabghab tabulation, and sometimes the high-energy
uncertainty was extended to lower energies. The uncertainty in the
<sup>149</sup>Sm resonance capture integral is not provided in the 2006
edition of Mughabghab’s text, so it was set to the value of 5.7%, which
was obtained from an earlier tabulation by Mughabghab <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#mughabghab-thermal-2003" id="id24">[Mug03]</a>.</p>
</div>
<div class="section" id="covariance-data-for-fission-spectra">
<span id="id25"></span><h3>Covariance data for fission spectra<a class="headerlink" href="#covariance-data-for-fission-spectra" title="Permalink to this headline"></a></h3>
<p>As of ENDF/B-VII.1, covariance matrices are now provided for the fission
exit energy distribution. The data are given as a function of incident
energy. The incident energy grid is very broad, and the exit energy
distribution is constant over a given incident energy group. Since the
COVERX library file only allows one multigroup fission spectrum (χ)
covariance matrix per nuclide, the exit energy spectrum is used for the
average energy of fission. If ν is nubar, <em>f</em> is fission, and <em>w</em> is the
appropriate flux, then the average energy of fission is calculated as:</p>
<div class="math notranslate nohighlight" id="equation-eq10-2-3">
<span class="eqno">()<a class="headerlink" href="#equation-eq10-2-3" title="Permalink to this equation"></a></span>\[10^{7}exp\left( - \frac{\sum_{}^{}{\text{vfw}\frac{1}{2}\left( \log\left( \frac{10^{7}}{E_{g1}} \right) + log\left( \frac{10^{7}}{E_{g2}} \right) \right)}}{\sum_{}^{}\text{νfw}} \right) ,\]</div>
<p>where the sum is over all groups and E<sub>g1</sub> and E<sub>g2</sub> are
the group boundaries for group g. ENDF/B-VII.1 provides covariance data
for exit energy distributions for 64 nuclides. This includes all
nuclides for which fission spectrum (χ) covariance matrices where
provided in the previous covariance library. Some additional
χ-covariance matrices were taken from JENDL-4.0. The new 56-group and
252-group fission spectrum covariances are more complete and
significantly improved compared to the earlier 44-group chi uncertainty
data, which were based on the Watt fission spectrum in ENDF/B-V. (see
<a class="reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#id59"><span class="std std-ref">SCALE 6.1 44-group covariance library</span></a>).</p>
</div>
</div>
<div class="section" id="multigroup-covariance-processing">
<span id="id26"></span><h2>Multigroup Covariance Processing<a class="headerlink" href="#multigroup-covariance-processing" title="Permalink to this headline"></a></h2>
<p>Covariance data were processed with the AMPX code PUFF-IV. PUFF-IV has
major improvements in the treatment of the resolved and unresolved
resonance parameter uncertainties over previous code versions <a class="bibtex reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#wiarda-recent-2008" id="id27">[WALD08]</a>. All
nuclides with resonance parameter uncertainty files were processed with
the full sensitivity option in PUFF-IV.</p>
</div>
<div class="section" id="contents-of-the-scale-6-2-covariance-library">
<span id="id28"></span><h2>Contents of the SCALE 6.2 Covariance Library<a class="headerlink" href="#contents-of-the-scale-6-2-covariance-library" title="Permalink to this headline"></a></h2>
<p>The SCALE covariance library provides uncertainty data in 56- and
252-group formats for a total of 456 materials, including some
duplication for materials with multiple thermal scattering kernels.
<a class="reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#tab10-2-1"><span class="std std-numref">Table 9.21</span></a> describes the contents of the library using the following
nomenclature:</p>
<ol class="arabic simple">
<li><p>ENDF/B-VII.1: evaluated covariance data released with ENDF/B-VII.1</p></li>
<li><p>ENDF/B-VII.2-prelim: recently evaluated data proposed for future
release of ENDF/B-VII.2</p></li>
<li><p>ENDF/B-VI: evaluated covariance data released with ENDF/B-VI</p></li>
<li><p>BLO approximate data: lo-fi covariances from BLO project</p></li>
<li><p>SG-26: approximate covariances from WPEC Subgroup-26</p></li>
<li><p>JENDL-4.0: evaluated covariance data released with JENDL-4.0</p></li>
</ol>
<p>Several covariance evaluations include cross correlations between
reactions. These are summarized in <a class="reference internal" href="Nuclear%20Data%20Libraries%20Overview.html#tab10-2-2"><span class="std std-numref">Table 9.22</span></a>.</p>
<span id="tab10-2-1"></span><table class="longtable docutils align-center" id="id36">
<caption><span class="caption-text">Contents of SCALE 6.2 covariance libraries.</span><a class="headerlink" href="#id36" title="Permalink to this table"></a></caption>
<colgroup>
<col style="width: 25%" />
<col style="width: 25%" />
<col style="width: 25%" />
<col style="width: 25%" />
</colgroup>
<thead>
<tr class="row-odd"><th class="head"><p><strong>SCALE name</strong></p></th>
<th class="head"><p><strong>SCALE ID</strong></p></th>
<th class="head"><p><strong>Data source</strong></p></th>
<th class="head"><p><strong>Comment</strong></p></th>
</tr>
</thead>
<tbody>
<tr class="row-even"><td><p>ac-225</p></td>
<td><p>89225</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ac-226</p></td>
<td><p>89226</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ac-227</p></td>
<td><p>89227</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ag-107</p></td>
<td><p>47107</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ag-109</p></td>
<td><p>47109</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ag-110m</p></td>
<td><p>1047110</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ag-111</p></td>
<td><p>47111</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>al-27</p></td>
<td><p>13027</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>albound</p></td>
<td><p>1013027</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td><p>Duplicate of
al-27</p></td>
</tr>
<tr class="row-odd"><td><p>am-240</p></td>
<td><p>95240</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>am-241</p></td>
<td><p>95241</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-odd"><td></td>
<td></td>
<td><p>χ covariance
JENDL-4.0</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>am-242</p></td>
<td><p>95242</p></td>
<td><p>SG-26</p></td>
<td><p>Thermal
uncertainty
replaced by
Mughabghab
value</p></td>
</tr>
<tr class="row-odd"><td></td>
<td></td>
<td><p>χ covariance
JENDL-4.0</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>am-242m</p></td>
<td><p>1095242</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>am-243</p></td>
<td><p>95243</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-even"><td></td>
<td></td>
<td><p>χ covariance
JENDL-4.0</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>am-244</p></td>
<td><p>95244</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td></td>
<td></td>
<td><p>χ covariance
JENDL-4.0</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>am-244m</p></td>
<td><p>1095244</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ar-36</p></td>
<td><p>18036</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ar-38</p></td>
<td><p>18038</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ar-40</p></td>
<td><p>18040</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>as-74</p></td>
<td><p>33074</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>as-75</p></td>
<td><p>33075</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>au-197</p></td>
<td><p>79197</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>b-10</p></td>
<td><p>5010</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>b-11</p></td>
<td><p>5011</p></td>
<td><p>ENDF/B-VII.1</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ba-130</p></td>
<td><p>56130</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ba-132</p></td>
<td><p>56132</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ba-133</p></td>
<td><p>56133</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ba-134</p></td>
<td><p>56134</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ba-135</p></td>
<td><p>56135</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ba-136</p></td>
<td><p>56136</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ba-137</p></td>
<td><p>56137</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-odd"><td><p>ba-138</p></td>
<td><p>56138</p></td>
<td><p>BLO
approximation
data</p></td>
<td></td>
</tr>
<tr class="row-even"><td><p>ba-140</p></td>
<td><p>56140</p></td>
<td><p>BLO
approximation
data</p></td>