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Update MGXS tests with consistent scattering matrices

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This commit is contained in:
Will Boyd 2017-02-20 12:53:05 -05:00
parent 0ace8c59aa
commit 6753e3a140
14 changed files with 3188 additions and 1752 deletions
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3
openmc/mgxs/library.py
View file

@ -526,7 +526,8 @@ class Library(object):
mgxs.tally_trigger = self.tally_trigger
# Specify whether to use a transport ('P0') correction
if isinstance(mgxs, openmc.mgxs.ScatterMatrixXS):
if isinstance(mgxs, openmc.mgxs.ScatterMatrixXS) and not \
isinstance(mgxs, openmc.mgxs.ConsistentScatterMatrixXS):
mgxs.correction = self.correction
mgxs.scatter_format = self.scatter_format
mgxs.legendre_order = self.legendre_order

15
openmc/mgxs/mgxs.py
View file

@ -3623,7 +3623,6 @@ class ScatterXS(MGXS):
num_azimuthal)
self._rxn_type = 'scatter'
class NuScatterXS(MGXS):
r"""A scattering neutron production multi-group cross section.
@ -5845,10 +5844,9 @@ class ConsistentScatterMatrixXS(ConvolvedMGXS, ScatterMatrixXS):
def get_subdomain_avg_xs(self, subdomains='all'):
avg_xs = \
super(ConsistentScatterMatrixXS, self).get_subdomain_avg_xs(subdomains)
avg_xs._tallies = None
for i, mgxs in enumerate(avg_xs._mgxs):
self._mgxs[i] = mgxs.get_subdomain_avg_xs(subdomains)
avg_xs._mgxs[i] = mgxs.get_subdomain_avg_xs(subdomains)
return avg_xs
@ -5860,11 +5858,12 @@ class ConsistentNuScatterMatrixXS(ConsistentScatterMatrixXS):
This class is a variation of the :class:`NuScatterMatrixXS` which computes
the scattering-production matrix as the convolution product of
:class:`NuScatterXS` and :class:`NuScatterProbabilityMatrix`. Unlike the
:class:`NuScatterMatrixXS`, this scattering-production matrix is computed
from the scattering-production cross section which uses a tracklength
estimator. This ensures that reaction rate balance is exactly preserved
with a :class:`TotalXS` computed using a tracklength estimator.
:class:`ScatterXS`, :class:`NuScatterProbabilityMatrix` and
:class:`MultiplicityMatrixXS`. Unlike the :class:`NuScatterMatrixXS`, this
scattering-production matrix is computed from the scattering cross section
which uses a tracklength estimator. This ensures that reaction rate balance
is exactly preserved with a :class:`TotalXS` computed using a tracklength
estimator.
This class can be used for both OpenMC input generation and tally data
post-processing to compute spatially-homogenized and energy-integrated

1176
tests/test_mgxs_library_condense/inputs_true.dat
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File diff suppressed because it is too large Load diff

24
tests/test_mgxs_library_condense/results_true.dat
View file

@ -32,6 +32,14 @@
0 10000 1 1 total 1.0 0.066111
material group in group out nuclide mean std. dev.
0 10000 1 1 total 0.085835 0.005592
material group in group out nuclide mean std. dev.
0 10000 1 1 total 1.0 0.066111
material group in group out nuclide mean std. dev.
0 10000 1 1 total 1.0 0.066111
material group in group out nuclide mean std. dev.
0 10000 1 1 total 0.341361 0.031842
material group in group out nuclide mean std. dev.
0 10000 1 1 total 0.341361 0.040919
material group out nuclide mean std. dev.
0 10000 1 total 1.0 0.046071
material group out nuclide mean std. dev.
@ -111,6 +119,14 @@
0 10001 1 1 total 1.0 0.095039
material group in group out nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 10001 1 1 total 1.0 0.095039
material group in group out nuclide mean std. dev.
0 10001 1 1 total 1.0 0.095039
material group in group out nuclide mean std. dev.
0 10001 1 1 total 0.276654 0.033287
material group in group out nuclide mean std. dev.
0 10001 1 1 total 0.276654 0.044414
material group out nuclide mean std. dev.
0 10001 1 total 0.0 0.0
material group out nuclide mean std. dev.
@ -190,6 +206,14 @@
0 10002 1 1 total 1.0 0.056867
material group in group out nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 10002 1 1 total 1.0 0.056867
material group in group out nuclide mean std. dev.
0 10002 1 1 total 1.0 0.056867
material group in group out nuclide mean std. dev.
0 10002 1 1 total 0.489924 0.069059
material group in group out nuclide mean std. dev.
0 10002 1 1 total 0.489924 0.08592
material group out nuclide mean std. dev.
0 10002 1 total 0.0 0.0
material group out nuclide mean std. dev.

162
tests/test_mgxs_library_distribcell/inputs_true.dat
View file

@ -302,44 +302,47 @@
<tally id="10031">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10032">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10033">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10034">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energyout" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10035">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10036">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10037">
<filter bins="10000" type="distribcell" />
@ -352,14 +355,15 @@
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10039">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>flux</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
@ -367,69 +371,64 @@
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10041">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10042">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10043">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10045">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10046">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10047">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10048">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10049">
@ -437,9 +436,100 @@
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
<estimator>tracklength</estimator>
</tally>
<tally id="10050">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10051">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10052">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10053">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10054">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10055">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10056">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10057">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10058">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10059">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10060">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10061">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10062">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />

8
tests/test_mgxs_library_distribcell/results_true.dat
View file

@ -32,6 +32,14 @@
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 1.000834 0.037242
sum(distribcell) group in group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 0.094516 0.0059
sum(distribcell) group in group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 1.0 0.037213
sum(distribcell) group in group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 1.0 0.037213
sum(distribcell) group in group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 0.342636 0.017656
sum(distribcell) group in group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 0.342954 0.022894
sum(distribcell) group out nuclide mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 total 1.0 0.080455
sum(distribcell) group out nuclide mean std. dev.

1176
tests/test_mgxs_library_hdf5/inputs_true.dat
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File diff suppressed because it is too large Load diff

60
tests/test_mgxs_library_hdf5/results_true.dat
View file

@ -60,6 +60,26 @@ domain=10000 type=nu-fission matrix
[4.54366342e-01 0.00000000e+00]]
[[3.14909051e-03 0.00000000e+00]
[2.74255162e-02 0.00000000e+00]]
domain=10000 type=scatter probability matrix
[[9.97432606e-01 2.56739409e-03]
[2.24215247e-03 9.97757848e-01]]
[[7.82243018e-02 1.25560869e-03]
[2.24310192e-03 4.10531468e-02]]
domain=10000 type=nu-scatter probability matrix
[[9.97432606e-01 2.56739409e-03]
[2.24215247e-03 9.97757848e-01]]
[[7.82243018e-02 1.25560869e-03]
[2.24310192e-03 4.10531468e-02]]
domain=10000 type=consistent scatter matrix
[[3.32987194e-01 9.94653712e-04]
[8.87128136e-04 3.79756741e-01]]
[[3.73090623e-02 4.89318749e-04]
[8.89289900e-04 3.01139605e-02]]
domain=10000 type=consistent nu-scatter matrix
[[3.32987194e-01 9.94653712e-04]
[8.87128136e-04 3.79756741e-01]]
[[4.80886244e-02 8.40606499e-04]
[1.53780011e-03 3.42124888e-02]]
domain=10000 type=chi
[1.00000000e+00 0.00000000e+00]
[4.60705493e-02 0.00000000e+00]
@ -226,6 +246,26 @@ domain=10001 type=nu-fission matrix
[0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10001 type=scatter probability matrix
[[1.00000000e+00 0.00000000e+00]
[0.00000000e+00 1.00000000e+00]]
[[1.08778697e-01 0.00000000e+00]
[0.00000000e+00 1.42427173e-01]]
domain=10001 type=nu-scatter probability matrix
[[1.00000000e+00 0.00000000e+00]
[0.00000000e+00 1.00000000e+00]]
[[1.08778697e-01 0.00000000e+00]
[0.00000000e+00 1.42427173e-01]]
domain=10001 type=consistent scatter matrix
[[2.70706971e-01 0.00000000e+00]
[0.00000000e+00 3.06542088e-01]]
[[3.82655052e-02 0.00000000e+00]
[0.00000000e+00 5.27278829e-02]]
domain=10001 type=consistent nu-scatter matrix
[[2.70706971e-01 0.00000000e+00]
[0.00000000e+00 3.06542088e-01]]
[[5.11595827e-02 0.00000000e+00]
[0.00000000e+00 6.74582654e-02]]
domain=10001 type=chi
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -392,6 +432,26 @@ domain=10002 type=nu-fission matrix
[0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10002 type=scatter probability matrix
[[9.53271028e-01 4.67289720e-02]
[2.17817469e-04 9.99782183e-01]]
[[3.60184962e-02 2.54736726e-03]
[2.18820864e-04 1.35884974e-01]]
domain=10002 type=nu-scatter probability matrix
[[9.53271028e-01 4.67289720e-02]
[2.17817469e-04 9.99782183e-01]]
[[3.60184962e-02 2.54736726e-03]
[2.18820864e-04 1.35884974e-01]]
domain=10002 type=consistent scatter matrix
[[2.51505773e-01 3.10225138e-02]
[4.40143026e-04 1.47923453e+00]]
[[4.18067487e-02 2.23201039e-03]
[4.44773843e-04 3.55391574e-01]]
domain=10002 type=consistent nu-scatter matrix
[[2.51505773e-01 3.10225138e-02]
[4.40143026e-04 1.47923453e+00]]
[[4.84234821e-02 3.06407542e-03]
[7.65033031e-04 4.49126759e-01]]
domain=10002 type=chi
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]

162
tests/test_mgxs_library_mesh/inputs_true.dat
View file

@ -539,44 +539,47 @@
<tally id="10031">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10032">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10033">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10034">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energyout" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10035">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10036">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10037">
<filter bins="1" type="mesh" />
@ -589,14 +592,15 @@
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10039">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>flux</scores>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
@ -604,69 +608,64 @@
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10041">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10042">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10043">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10045">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10046">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10047">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10048">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10049">
@ -674,9 +673,100 @@
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
<estimator>tracklength</estimator>
</tally>
<tally id="10050">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10051">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10052">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10053">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10054">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10055">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10056">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10057">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10058">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10059">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10060">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10061">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10062">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />

24
tests/test_mgxs_library_mesh/results_true.dat
View file

@ -106,6 +106,30 @@
1 1 2 1 1 1 total 0.017348 0.008786
2 2 1 1 1 1 total 0.020409 0.003354
3 2 2 1 1 1 total 0.011105 0.003806
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.153265
1 1 2 1 1 1 total 1.0 0.454973
2 2 1 1 1 1 total 1.0 0.146747
3 2 2 1 1 1 total 1.0 0.141824
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.153265
1 1 2 1 1 1 total 1.0 0.454973
2 2 1 1 1 1 total 1.0 0.146747
3 2 2 1 1 1 total 1.0 0.141824
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.385281 0.140163
1 1 2 1 1 1 total 0.381031 0.407858
2 2 1 1 1 1 total 0.429729 0.130705
3 2 2 1 1 1 total 0.373069 0.127649
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.385281 0.170507
1 1 2 1 1 1 total 0.381031 0.495567
2 2 1 1 1 1 total 0.429729 0.164992
3 2 2 1 1 1 total 0.373069 0.154944
mesh 1 group out nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.0 0.135958

1176
tests/test_mgxs_library_no_nuclides/inputs_true.dat
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60
tests/test_mgxs_library_no_nuclides/results_true.dat
View file

@ -72,6 +72,26 @@
2 10000 1 2 total 0.000000 0.000000
1 10000 2 1 total 0.454366 0.027426
0 10000 2 2 total 0.000000 0.000000
material group in group out nuclide mean std. dev.
3 10000 1 1 total 0.997433 0.078224
2 10000 1 2 total 0.002567 0.001256
1 10000 2 1 total 0.002242 0.002243
0 10000 2 2 total 0.997758 0.041053
material group in group out nuclide mean std. dev.
3 10000 1 1 total 0.997433 0.078224
2 10000 1 2 total 0.002567 0.001256
1 10000 2 1 total 0.002242 0.002243
0 10000 2 2 total 0.997758 0.041053
material group in group out nuclide mean std. dev.
3 10000 1 1 total 0.332987 0.037309
2 10000 1 2 total 0.000995 0.000489
1 10000 2 1 total 0.000887 0.000889
0 10000 2 2 total 0.379757 0.030114
material group in group out nuclide mean std. dev.
3 10000 1 1 total 0.332987 0.048089
2 10000 1 2 total 0.000995 0.000841
1 10000 2 1 total 0.000887 0.001538
0 10000 2 2 total 0.379757 0.034212
material group out nuclide mean std. dev.
1 10000 1 total 1.0 0.046071
0 10000 2 total 0.0 0.000000
@ -240,6 +260,26 @@
2 10001 1 2 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
0 10001 2 2 total 0.0 0.0
material group in group out nuclide mean std. dev.
3 10001 1 1 total 1.0 0.108779
2 10001 1 2 total 0.0 0.000000
1 10001 2 1 total 0.0 0.000000
0 10001 2 2 total 1.0 0.142427
material group in group out nuclide mean std. dev.
3 10001 1 1 total 1.0 0.108779
2 10001 1 2 total 0.0 0.000000
1 10001 2 1 total 0.0 0.000000
0 10001 2 2 total 1.0 0.142427
material group in group out nuclide mean std. dev.
3 10001 1 1 total 0.270707 0.038266
2 10001 1 2 total 0.000000 0.000000
1 10001 2 1 total 0.000000 0.000000
0 10001 2 2 total 0.306542 0.052728
material group in group out nuclide mean std. dev.
3 10001 1 1 total 0.270707 0.051160
2 10001 1 2 total 0.000000 0.000000
1 10001 2 1 total 0.000000 0.000000
0 10001 2 2 total 0.306542 0.067458
material group out nuclide mean std. dev.
1 10001 1 total 0.0 0.0
0 10001 2 total 0.0 0.0
@ -408,6 +448,26 @@
2 10002 1 2 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
0 10002 2 2 total 0.0 0.0
material group in group out nuclide mean std. dev.
3 10002 1 1 total 0.953271 0.036018
2 10002 1 2 total 0.046729 0.002547
1 10002 2 1 total 0.000218 0.000219
0 10002 2 2 total 0.999782 0.135885
material group in group out nuclide mean std. dev.
3 10002 1 1 total 0.953271 0.036018
2 10002 1 2 total 0.046729 0.002547
1 10002 2 1 total 0.000218 0.000219
0 10002 2 2 total 0.999782 0.135885
material group in group out nuclide mean std. dev.
3 10002 1 1 total 0.251506 0.041807
2 10002 1 2 total 0.031023 0.002232
1 10002 2 1 total 0.000440 0.000445
0 10002 2 2 total 1.479235 0.355392
material group in group out nuclide mean std. dev.
3 10002 1 1 total 0.251506 0.048423
2 10002 1 2 total 0.031023 0.003064
1 10002 2 1 total 0.000440 0.000765
0 10002 2 2 total 1.479235 0.449127
material group out nuclide mean std. dev.
1 10002 1 total 0.0 0.0
0 10002 2 total 0.0 0.0

892
tests/test_mgxs_library_nuclides/inputs_true.dat
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2
tests/test_mgxs_library_nuclides/results_true.dat
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@ -1 +1 @@
b91cd851e23046bed070866f56e03cb95d92025dbaf4d7e12dad553fc391cd812c2c6cb7584e9a10af113d728631dd10a079717418eefd57b676b847c3261c80
830113ee8be5f5a9941a2e1b97d8fc0049dbde0a7860c2ebf3aadfa4811ca58663fefbfea5f01e8793b1bfe52ac060b3631cafd959203d158d20af94ed318743