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Added formulation property to ScatterMatrixXS

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This commit is contained in:
Will Boyd 2017-03-02 17:02:08 -05:00
parent 671a9cf693
commit 604bfbfbe1
14 changed files with 1663 additions and 1690 deletions
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314
openmc/mgxs/mgxs.py
View file

@ -482,12 +482,18 @@ class MGXS(object):
else:
domain_filter = filter_type(self.domain.id)
if isinstance(self.estimator, str):
estimators = [self.estimator] * len(self.scores)
else:
estimators = self.estimator
# Create each Tally needed to compute the multi group cross section
tally_metadata = zip(self.scores, self.tally_keys, self.filters)
for score, key, filters in tally_metadata:
tally_metadata = \
zip(self.scores, self.tally_keys, self.filters, estimators)
for score, key, filters, estimator in tally_metadata:
self._tallies[key] = openmc.Tally(name=self.name)
self._tallies[key].scores = [score]
self._tallies[key].estimator = self.estimator
self._tallies[key].estimator = estimator
self._tallies[key].filters = [domain_filter]
# If a tally trigger was specified, add it to each tally
@ -735,10 +741,11 @@ class MGXS(object):
mgxs = ScatterProbabilityMatrix(
domain, domain_type, energy_groups, nu=True)
elif mgxs_type == 'consistent scatter matrix':
mgxs = ConsistentScatterMatrixXS(domain, domain_type, energy_groups)
mgxs = ScatterMatrixXS(domain, domain_type, energy_groups)
mgxs.formulation = 'consistent'
elif mgxs_type == 'consistent nu-scatter matrix':
mgxs = ConsistentScatterMatrixXS(
domain, domain_type, energy_groups, nu=True)
mgxs = ScatterMatrixXS(domain, domain_type, energy_groups, nu=True)
mgxs.formulation = 'consistent'
elif mgxs_type == 'nu-fission matrix':
mgxs = NuFissionMatrixXS(domain, domain_type, energy_groups)
elif mgxs_type == 'chi':
@ -3545,6 +3552,8 @@ class ScatterMatrixXS(MatrixMGXS):
To incorporate the effect of neutron multiplication from (n,xn) reactions
in the above relation, the `nu` parameter can be set to `True`.
# FIXME: Add equations to reflect alternative formulation
Parameters
----------
domain : openmc.Material or openmc.Cell or openmc.Universe or openmc.Mesh
@ -3570,6 +3579,16 @@ class ScatterMatrixXS(MatrixMGXS):
Attributes
----------
formulation : 'simple' or 'consistent'
The calculation approach to use ('simple' by default). The 'simple'
formulation simply divides the group-to-group scattering rates by
the groupwise flux, each computed from analog tally estimators. The
'consistent' formulation multiplies the groupwise scattering rates
by the group-to-group scatter probability matrix, the former computed
from tracklength tallies and the latter computed from analog tallies.
The 'consistent' formulation is designed to better conserve reaction
rate balance with the total and absorption cross sections computed
using tracklength tally estimators.
correction : 'P0' or None
Apply the P0 correction to scattering matrices if set to 'P0'; this is
used only if :attr:`ScatterMatrixXS.scatter_format` is 'legendre'
@ -3655,6 +3674,7 @@ class ScatterMatrixXS(MatrixMGXS):
super(ScatterMatrixXS, self).__init__(domain, domain_type,
groups, by_nuclide, name,
num_polar, num_azimuthal)
self._formulation = 'simple'
self._correction = 'P0'
self._scatter_format = 'legendre'
self._legendre_order = 0
@ -3665,6 +3685,7 @@ class ScatterMatrixXS(MatrixMGXS):
def __deepcopy__(self, memo):
clone = super(ScatterMatrixXS, self).__deepcopy__(memo)
clone._formulation = self.formulation
clone._correction = self.correction
clone._scatter_format = self.scatter_format
clone._legendre_order = self.legendre_order
@ -3689,8 +3710,8 @@ class ScatterMatrixXS(MatrixMGXS):
return (1, 2)
@property
def nu(self):
return self._nu
def formulation(self):
return self._formulation
@property
def correction(self):
@ -3709,35 +3730,122 @@ class ScatterMatrixXS(MatrixMGXS):
return self._histogram_bins
@property
def scores(self):
scores = ['flux']
def nu(self):
return self._nu
if self.scatter_format == 'legendre':
if self.correction == 'P0' and self.legendre_order == 0:
scores += ['{}-0'.format(self.rxn_type),
'{}-1'.format(self.rxn_type)]
@property
def scores(self):
if self.formulation == 'simple':
scores = ['flux']
if self.scatter_format == 'legendre':
if self.legendre_order == 0:
scores.append('{}-0'.format(self.rxn_type))
if self.correction:
scores.append('{}-1'.format(self.rxn_type))
else:
scores.append('{}-P{}'.format(self.rxn_type, self.legendre_order))
elif self.scatter_format == 'histogram':
scores += [self.rxn_type]
else:
# Add scores for groupwise scattering cross section
scores = ['flux', 'scatter']
# Add scores for group-to-group scattering probability matrix
if self.legendre_order == 0:
scores.append('scatter-0')
else:
scores += ['{}-P{}'.format(self.rxn_type, self.legendre_order)]
elif self.scatter_format == 'histogram':
scores += [self.rxn_type]
scores.append('scatter-P{}'.format(self.legendre_order))
# Add scores for multiplicity matrix
if self.nu:
scores.extend(['nu-scatter-0', 'scatter-0'])
# Add scores for transport correction
if self.correction == 'P0' and self.legendre_order == 0:
scores.extend(['{}-1'.format(self.rxn_type), 'flux'])
return scores
@property
def filters(self):
group_edges = self.energy_groups.group_edges
energy = openmc.EnergyFilter(group_edges)
energyout = openmc.EnergyoutFilter(group_edges)
def tally_keys(self):
if self.formulation == 'simple':
return super(ScatterMatrixXS, self).tally_keys
else:
# Add keys for groupwise scattering cross section
tally_keys = ['flux (tracklength)', 'scatter']
if self.scatter_format == 'legendre':
# Add keys for group-to-group scattering probability matrix
tally_keys.append('scatter-P{}'.format(self.legendre_order))
# Add keys for multiplicity matrix
if self.nu:
tally_keys.extend(['nu-scatter-0', 'scatter-0'])
# Add keys for transport correction
if self.correction == 'P0' and self.legendre_order == 0:
filters = [[energy], [energy, energyout], [energyout]]
else:
filters = [[energy], [energy, energyout]]
elif self.scatter_format == 'histogram':
bins = np.linspace(-1., 1., num=self.histogram_bins + 1,
endpoint=True)
filters = [[energy], [energy, energyout, openmc.MuFilter(bins)]]
tally_keys.extend(['{}-1'.format(self.rxn_type), 'flux (analog)'])
return tally_keys
@property
def estimator(self):
if self.formulation == 'simple':
return self._estimator
else:
# Add estimators for groupwise scattering cross section
estimators = ['tracklength', 'tracklength']
# Add estimators for group-to-group scattering probabilities
estimators.append('analog')
# Add estimators for multiplicity matrix
if self.nu:
estimators.extend(['analog', 'analog'])
# Add estimators for transport correction
if self.correction == 'P0' and self.legendre_order == 0:
estimators.extend(['analog', 'analog'])
return estimators
@property
def filters(self):
if self.formulation == 'simple':
group_edges = self.energy_groups.group_edges
energy = openmc.EnergyFilter(group_edges)
energyout = openmc.EnergyoutFilter(group_edges)
if self.scatter_format == 'legendre':
if self.correction == 'P0' and self.legendre_order == 0:
filters = [[energy], [energy, energyout], [energyout]]
else:
filters = [[energy], [energy, energyout]]
elif self.scatter_format == 'histogram':
bins = np.linspace(-1., 1., num=self.histogram_bins + 1,
endpoint=True)
filters = [[energy], [energy, energyout, openmc.MuFilter(bins)]]
else:
group_edges = self.energy_groups.group_edges
energy = openmc.EnergyFilter(group_edges)
energyout = openmc.EnergyoutFilter(group_edges)
# Groupwise scattering cross section
filters = [[energy], [energy]]
# Group-to-group scattering probability matrix
filters.extend([[energy, energyout], [energy, energyout]])
# Multiplicity matrix
if self.nu:
filters.append([energy, energyout])
# Add filters for transport correction
if self.correction == 'P0' and self.legendre_order == 0:
filters.append([[energyout]])
return self._add_angle_filters(filters)
@ -3745,39 +3853,128 @@ class ScatterMatrixXS(MatrixMGXS):
def rxn_rate_tally(self):
if self._rxn_rate_tally is None:
if self.scatter_format == 'legendre':
# If using P0 correction subtract scatter-1 from the diagonal
if self.correction == 'P0' and self.legendre_order == 0:
scatter_p0 = self.tallies['{}-0'.format(self.rxn_type)]
scatter_p1 = self.tallies['{}-1'.format(self.rxn_type)]
energy_filter = scatter_p0.find_filter(openmc.EnergyFilter)
energy_filter = copy.deepcopy(energy_filter)
scatter_p1 = scatter_p1.diagonalize_filter(energy_filter)
self._rxn_rate_tally = scatter_p0 - scatter_p1
# Extract scattering moment reaction rate Tally
else:
tally_key = '{}-P{}'.format(self.rxn_type,
self.legendre_order)
self._rxn_rate_tally = self.tallies[tally_key]
elif self.scatter_format == 'histogram':
# Extract scattering rate distribution tally
self._rxn_rate_tally = self.tallies[self.rxn_type]
if self.formulation == 'simple':
if self.scatter_format == 'legendre':
# If using P0 correction subtract scatter-1 from the diagonal
if self.correction == 'P0' and self.legendre_order == 0:
scatter_p0 = self.tallies['{}-0'.format(self.rxn_type)]
scatter_p1 = self.tallies['{}-1'.format(self.rxn_type)]
energy_filter = scatter_p0.find_filter(openmc.EnergyFilter)
energy_filter = copy.deepcopy(energy_filter)
scatter_p1 = scatter_p1.diagonalize_filter(energy_filter)
self._rxn_rate_tally = scatter_p0 - scatter_p1
self._rxn_rate_tally.sparse = self.sparse
# Extract scattering moment reaction rate Tally
elif self.legendre_order == 0:
tally_key = '{}-{}'.format(self.rxn_type,
self.legendre_order)
self._rxn_rate_tally = self.tallies[tally_key]
else:
tally_key = '{}-P{}'.format(self.rxn_type,
self.legendre_order)
self._rxn_rate_tally = self.tallies[tally_key]
elif self.scatter_format == 'histogram':
# Extract scattering rate distribution tally
self._rxn_rate_tally = self.tallies[self.rxn_type]
self._rxn_rate_tally.sparse = self.sparse
else:
msg = 'The reaction rate tally is poorly defined' \
' for the consistent formulation'
raise NotImplementedError(msg)
return self._rxn_rate_tally
@property
def xs_tally(self):
if self._xs_tally is None:
if self.tallies is None:
msg = 'Unable to get xs_tally since tallies have ' \
'not been loaded from a statepoint'
raise ValueError(msg)
# Use super class method
if self.formulation == 'simple':
self._xs_tally = MGXS.xs_tally.fget(self)
else:
# Compute groupwise scattering cross section
self._xs_tally = self.tallies['scatter'] / \
self.tallies['flux (tracklength)']
# Compute scattering probability matrix
energyout_bins = [self.energy_groups.get_group_bounds(i)
for i in range(self.num_groups, 0, -1)]
tally_key = 'scatter-P{}'.format(self.legendre_order)
norm = self.tallies[tally_key].get_slice(scores=['scatter-0'])
norm = norm.summation(
filter_type=openmc.EnergyoutFilter, filter_bins=energyout_bins)
# Remove the AggregateFilter summed across energyout bins
norm._filters = norm._filters[:2]
# Multiply by the group-to-group probability matrix
self._xs_tally *= (self.tallies[tally_key] / norm)
# Multiply by the multiplicity matrix
if self.nu:
numer = self.tallies['nu-scatter-0']
denom = self.tallies['scatter-0']
self._xs_tally *= (numer / denom)
# If using P0 correction subtract scatter-1 from the diagonal
if self.correction == 'P0' and self.legendre_order == 0:
flux = self.tallies['flux (analog)']
scatter_p1 = self.tallies['{}-1'.format(self.rxn_type)]
energy_filter = flux.find_filter(openmc.EnergyFilter)
energy_filter = copy.deepcopy(energy_filter)
scatter_p1 = scatter_p1.diagonalize_filter(energy_filter)
self._xs_tally -= (scatter_p1 / flux)
self._compute_xs()
return self._xs_tally
@nu.setter
def nu(self, nu):
cv.check_type('nu', nu, bool)
self._nu = nu
if not nu:
self._rxn_type = 'scatter'
self._hdf5_key = 'scatter matrix'
if self.formulation == 'simple':
if not nu:
self._rxn_type = 'scatter'
self._hdf5_key = 'scatter matrix'
else:
self._rxn_type = 'nu-scatter'
self._hdf5_key = 'nu-scatter matrix'
else:
self._rxn_type = 'nu-scatter'
self._hdf5_key = 'nu-scatter matrix'
if not nu:
self._rxn_type = 'scatter'
self._hdf5_key = 'consistent scatter matrix'
else:
self._rxn_type = 'nu-scatter'
self._hdf5_key = 'consistent nu-scatter matrix'
@formulation.setter
def formulation(self, formulation):
cv.check_value('formulation', formulation, ('simple', 'consistent'))
self._formulation = formulation
if self.formulation == 'simple':
self._valid_estimators = ['analog']
if not self.nu:
self._hdf5_key = 'scatter matrix'
else:
self._hdf5_key = 'nu-scatter matrix'
else:
self._valid_estimators = ['tracklength']
if not self.nu:
self._hdf5_key = 'consistent scatter matrix'
else:
self._hdf5_key = 'consistent nu-scatter matrix'
@correction.setter
def correction(self, correction):
@ -3862,11 +4059,12 @@ class ScatterMatrixXS(MatrixMGXS):
if self.scatter_format == 'legendre':
# Expand scores to match the format in the statepoint
# e.g., "scatter-P2" -> "scatter-0", "scatter-1", "scatter-2"
if self.correction != 'P0' or self.legendre_order != 0:
tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order)
self.tallies[tally_key].scores = \
[self.rxn_type + '-{}'.format(i)
for i in range(self.legendre_order + 1)]
for tally_key, tally in self.tallies.items():
if 'scatter-P' in tally.scores[0]:
score_prefix = tally.scores[0].split('P')[0]
self.tallies[tally_key].scores = \
[score_prefix + '{}'.format(i)
for i in range(self.legendre_order + 1)]
elif self.scatter_format == 'histogram':
self.tallies[self.rxn_type].scores = [self.rxn_type]
@ -4792,7 +4990,7 @@ class ScatterProbabilityMatrix(MatrixMGXS):
# Remove the AggregateFilter summed across energyout bins
norm._filters = norm._filters[:2]
# Compute the group-to-group probailities
# Compute the group-to-group probabilities
tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order)
self._xs_tally = self.tallies[tally_key] / norm
super(ScatterProbabilityMatrix, self)._compute_xs()

1
openmc/statepoint.py
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@ -1,4 +1,3 @@
import sys
import re
import os
import warnings

678
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
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@ -42,10 +42,10 @@
2 10000 1 1 total P2 0.017957 0.003039
3 10000 1 1 total P3 0.006618 0.002480
material group in group out nuclide moment mean std. dev.
0 10000 1 1 total P0 0.389304 0.043096
1 10000 1 1 total P1 0.046224 0.007316
2 10000 1 1 total P2 0.017984 0.003336
3 10000 1 1 total P3 0.006628 0.002534
0 10000 1 1 total P0 0.388721 0.040482
1 10000 1 1 total P1 0.046155 0.007097
2 10000 1 1 total P2 0.017957 0.003262
3 10000 1 1 total P3 0.006618 0.002518
material group out nuclide mean std. dev.
0 10000 1 total 1.0 0.046071
material group out nuclide mean std. dev.
@ -135,10 +135,10 @@
2 10001 1 1 total P2 0.018997 0.004420
3 10001 1 1 total P3 0.006263 0.003364
material group in group out nuclide moment mean std. dev.
0 10001 1 1 total P0 0.307987 0.050720
1 10001 1 1 total P1 0.030617 0.008524
2 10001 1 1 total P2 0.018911 0.005015
3 10001 1 1 total P3 0.006235 0.003442
0 10001 1 1 total P0 0.309384 0.043735
1 10001 1 1 total P1 0.030756 0.008159
2 10001 1 1 total P2 0.018997 0.004775
3 10001 1 1 total P3 0.006263 0.003417
material group out nuclide mean std. dev.
0 10001 1 total 0.0 0.0
material group out nuclide mean std. dev.
@ -228,10 +228,10 @@
2 10002 1 1 total P2 0.142591 0.010824
3 10002 1 1 total P3 0.008696 0.003588
material group in group out nuclide moment mean std. dev.
0 10002 1 1 total P0 0.903415 0.084918
1 10002 1 1 total P1 0.410417 0.036718
2 10002 1 1 total P2 0.143301 0.013612
3 10002 1 1 total P3 0.008739 0.003640
0 10002 1 1 total P0 0.898938 0.084369
1 10002 1 1 total P1 0.408384 0.036475
2 10002 1 1 total P2 0.142591 0.013525
3 10002 1 1 total P3 0.008696 0.003622
material group out nuclide mean std. dev.
0 10002 1 total 0.0 0.0
material group out nuclide mean std. dev.

110
tests/test_mgxs_library_distribcell/inputs_true.dat
View file

@ -340,31 +340,31 @@
<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>nu-scatter</scores>
<estimator>analog</estimator>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10037">
<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>scatter</scores>
<estimator>analog</estimator>
<estimator>tracklength</estimator>
</tally>
<tally id="10038">
<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-P3</scores>
<estimator>analog</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>nu-scatter</scores>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
@ -372,52 +372,50 @@
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<scores>scatter-0</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>nu-scatter</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10042">
<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>scatter</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10043">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>prompt-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>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10046">
<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>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10047">
<filter bins="10000" type="distribcell" />
@ -430,7 +428,7 @@
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10049">
@ -438,54 +436,40 @@
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
<estimator>analog</estimator>
</tally>
<tally id="10050">
<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>tracklength</estimator>
<estimator>analog</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>
<estimator>tracklength</estimator>
</tally>
<tally id="10052">
<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>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10053">
<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>flux</scores>
<estimator>tracklength</estimator>
<scores>delayed-nu-fission</scores>
<estimator>analog</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" />
@ -493,30 +477,30 @@
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10057">
<tally id="10055">
<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="10056">
<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="10057">
<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="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" />
@ -524,14 +508,14 @@
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10061">
<tally id="10059">
<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">
<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" />

8
tests/test_mgxs_library_distribcell/results_true.dat
View file

@ -42,10 +42,10 @@
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P2 0.015866 0.003708
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P3 0.005430 0.003170
sum(distribcell) group in group out nuclide moment mean std. dev.
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P0 0.387654 0.024885
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P1 0.047226 0.005527
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P2 0.015740 0.003750
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P3 0.005392 0.003157
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P0 0.391123 0.022356
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P1 0.047680 0.005395
2 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P2 0.015880 0.003758
3 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P3 0.005435 0.003179
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.

678
tests/test_mgxs_library_hdf5/inputs_true.dat
View file

File diff suppressed because it is too large Load diff

40
tests/test_mgxs_library_hdf5/results_true.dat
View file

@ -82,16 +82,16 @@ domain=10000 type=consistent scatter matrix
[[8.89289900e-04 7.38354757e-04 4.74910776e-04 1.64940700e-04]
[2.98710064e-02 4.44330993e-03 1.01307463e-02 1.00367467e-02]]]
domain=10000 type=consistent nu-scatter matrix
[[[3.84199430e-01 5.18702806e-02 2.00688439e-02 9.47771503e-03]
[9.88930322e-04 -2.07234582e-04 -1.03366173e-04 2.34290606e-04]]
[[[3.86422967e-01 5.21704775e-02 2.01849914e-02 9.53256688e-03]
[9.94653712e-04 -2.08433942e-04 -1.03964400e-04 2.35646553e-04]]
[[9.24639842e-04 -7.67704913e-04 4.93788836e-04 -1.71497217e-04]
[4.11464730e-01 1.64817268e-02 6.37149004e-03 -1.04991213e-02]]]
[[[5.04005137e-02 9.04259889e-03 3.61169756e-03 2.46795126e-03]
[8.36973463e-04 2.06752354e-04 1.97694759e-04 2.06602832e-04]]
[[8.87128136e-04 -7.36559899e-04 4.73756321e-04 -1.64539748e-04]
[3.94772020e-01 1.58130798e-02 6.11300510e-03 -1.00731826e-02]]]
[[[4.75627021e-02 8.78140568e-03 3.51522200e-03 2.44425169e-03]
[8.40606499e-04 2.07733706e-04 1.98782933e-04 2.07523215e-04]]
[[1.60212263e-03 1.33020162e-03 8.55587476e-04 2.97153075e-04]
[2.84588375e-02 4.60349295e-03 1.05573088e-02 1.04561824e-02]]]
[[1.53780011e-03 1.27679627e-03 8.21237084e-04 2.85222881e-04]
[3.39988352e-02 4.49065920e-03 1.01338659e-02 1.00452944e-02]]]
domain=10000 type=chi
[1.00000000e+00 0.00000000e+00]
[4.60705493e-02 0.00000000e+00]
@ -280,16 +280,16 @@ domain=10001 type=consistent scatter matrix
[[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[5.02358893e-02 1.61616720e-02 1.14951123e-02 7.31312479e-03]]]
domain=10001 type=consistent nu-scatter matrix
[[[3.10120713e-01 3.82295876e-02 2.07449405e-02 7.96429620e-03]
[[[3.12162675e-01 3.84813069e-02 2.08815337e-02 8.01673640e-03]
[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[2.96264249e-01 -1.12136353e-02 8.83656566e-03 -3.27006707e-03]]]
[[[5.84608636e-02 1.03230576e-02 5.67743887e-03 3.92760936e-03]
[2.95421002e-01 -1.11817183e-02 8.81141444e-03 -3.26075959e-03]]]
[[[5.04070427e-02 9.69345877e-03 5.34169555e-03 3.87580585e-03]
[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[7.40187611e-02 1.63372534e-02 1.16408402e-02 7.35838382e-03]]]
[6.55288678e-02 1.62399493e-02 1.15634161e-02 7.32785650e-03]]]
domain=10001 type=chi
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -478,16 +478,16 @@ domain=10002 type=consistent scatter matrix
[[4.44773843e-04 4.01251123e-04 3.20593966e-04 2.14537073e-04]
[3.52193929e-01 7.91402819e-02 1.84875925e-02 8.77085752e-03]]]
domain=10002 type=consistent nu-scatter matrix
[[[6.39901439e-01 3.81167422e-01 1.52391887e-01 9.14802163e-03]
[3.13677176e-02 8.75772258e-03 -2.56790088e-03 -3.78480261e-03]]
[[[6.32859281e-01 3.76972649e-01 1.50714804e-01 9.04734705e-03]
[3.10225138e-02 8.66134326e-03 -2.53964096e-03 -3.74315061e-03]]
[[4.43343102e-04 3.99960386e-04 3.19562684e-04 2.13846954e-04]
[2.03494484e+00 5.09940477e-01 1.11174601e-01 2.49884339e-02]]]
[[[4.26392749e-02 2.63117825e-02 1.16194647e-02 3.92016710e-03]
[2.98774961e-03 1.14887360e-03 1.03342895e-03 8.68386243e-04]]
[[4.40143026e-04 3.97073448e-04 3.17256062e-04 2.12303394e-04]
[2.02025649e+00 5.06259696e-01 1.10372136e-01 2.48080660e-02]]]
[[[4.52974133e-02 2.78247077e-02 1.21478698e-02 3.88422859e-03]
[3.06407542e-03 1.15855775e-03 1.02420876e-03 8.64382873e-04]]
[[7.71125112e-04 6.95667747e-04 5.55828678e-04 3.71952908e-04]
[4.68587349e-01 1.10634806e-01 2.50303502e-02 9.60120658e-03]]]
[[7.65033031e-04 6.90171798e-04 5.51437493e-04 3.69014387e-04]
[4.46600759e-01 1.04874946e-01 2.38091367e-02 9.39676938e-03]]]
domain=10002 type=chi
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]

110
tests/test_mgxs_library_mesh/inputs_true.dat
View file

@ -577,31 +577,31 @@
<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>nu-scatter</scores>
<estimator>analog</estimator>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10037">
<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>scatter</scores>
<estimator>analog</estimator>
<estimator>tracklength</estimator>
</tally>
<tally id="10038">
<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-P3</scores>
<estimator>analog</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>nu-scatter</scores>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
@ -609,52 +609,50 @@
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<scores>scatter-0</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>nu-scatter</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10042">
<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>scatter</scores>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10043">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<scores>prompt-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>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10046">
<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>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10047">
<filter bins="1" type="mesh" />
@ -667,7 +665,7 @@
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10049">
@ -675,54 +673,40 @@
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
<estimator>analog</estimator>
</tally>
<tally id="10050">
<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>tracklength</estimator>
<estimator>analog</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>
<estimator>tracklength</estimator>
</tally>
<tally id="10052">
<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>prompt-nu-fission</scores>
<estimator>analog</estimator>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10053">
<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>flux</scores>
<estimator>tracklength</estimator>
<scores>delayed-nu-fission</scores>
<estimator>analog</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" />
@ -730,30 +714,30 @@
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10057">
<tally id="10055">
<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="10056">
<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="10057">
<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="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" />
@ -761,14 +745,14 @@
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10061">
<tally id="10059">
<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">
<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" />

32
tests/test_mgxs_library_mesh/results_true.dat
View file

@ -138,22 +138,22 @@
15 2 2 1 1 1 total P3 0.019785 0.014168
mesh 1 group in group out nuclide moment mean std. dev.
x y z
0 1 1 1 1 1 total P0 0.638348 0.169129
1 1 1 1 1 1 total P1 0.247099 0.064297
2 1 1 1 1 1 total P2 0.092195 0.022758
3 1 1 1 1 1 total P3 0.013224 0.005359
4 1 2 1 1 1 total P0 0.588378 0.462704
5 1 2 1 1 1 total P1 0.221552 0.175616
6 1 2 1 1 1 total P2 0.069798 0.056753
7 1 2 1 1 1 total P3 -0.003039 0.009829
8 2 1 1 1 1 total P0 0.698373 0.171880
9 2 1 1 1 1 total P1 0.261835 0.064773
10 2 1 1 1 1 total P2 0.096206 0.024355
11 2 1 1 1 1 total P3 0.016973 0.005960
12 2 2 1 1 1 total P0 0.625643 0.146236
13 2 2 1 1 1 total P1 0.244646 0.056797
14 2 2 1 1 1 total P2 0.088580 0.021648
15 2 2 1 1 1 total P3 0.019989 0.014515
0 1 1 1 1 1 total P0 0.633490 0.166706
1 1 1 1 1 1 total P1 0.245219 0.063359
2 1 1 1 1 1 total P2 0.091493 0.022409
3 1 1 1 1 1 total P3 0.013124 0.005303
4 1 2 1 1 1 total P0 0.618705 0.483237
5 1 2 1 1 1 total P1 0.232972 0.183428
6 1 2 1 1 1 total P2 0.073396 0.059298
7 1 2 1 1 1 total P3 -0.003195 0.010332
8 2 1 1 1 1 total P0 0.686150 0.161742
9 2 1 1 1 1 total P1 0.257252 0.060980
10 2 1 1 1 1 total P2 0.094522 0.022975
11 2 1 1 1 1 total P3 0.016676 0.005736
12 2 2 1 1 1 total P0 0.619269 0.152000
13 2 2 1 1 1 total P1 0.242153 0.059073
14 2 2 1 1 1 total P2 0.087677 0.022412
15 2 2 1 1 1 total P3 0.019785 0.014443
mesh 1 group out nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.0 0.135958

678
tests/test_mgxs_library_no_nuclides/inputs_true.dat
View file

File diff suppressed because it is too large Load diff

80
tests/test_mgxs_library_no_nuclides/results_true.dat
View file

@ -100,22 +100,22 @@
2 10000 2 2 total P2 0.006113 0.010131
3 10000 2 2 total P3 -0.010073 0.010037
material group in group out nuclide moment mean std. dev.
12 10000 1 1 total P0 0.384199 0.050401
13 10000 1 1 total P1 0.051870 0.009043
14 10000 1 1 total P2 0.020069 0.003612
15 10000 1 1 total P3 0.009478 0.002468
8 10000 1 2 total P0 0.000989 0.000837
9 10000 1 2 total P1 -0.000207 0.000207
10 10000 1 2 total P2 -0.000103 0.000198
11 10000 1 2 total P3 0.000234 0.000207
4 10000 2 1 total P0 0.000925 0.001602
5 10000 2 1 total P1 -0.000768 0.001330
6 10000 2 1 total P2 0.000494 0.000856
7 10000 2 1 total P3 -0.000171 0.000297
0 10000 2 2 total P0 0.411465 0.028459
1 10000 2 2 total P1 0.016482 0.004603
2 10000 2 2 total P2 0.006371 0.010557
3 10000 2 2 total P3 -0.010499 0.010456
12 10000 1 1 total P0 0.386423 0.047563
13 10000 1 1 total P1 0.052170 0.008781
14 10000 1 1 total P2 0.020185 0.003515
15 10000 1 1 total P3 0.009533 0.002444
8 10000 1 2 total P0 0.000995 0.000841
9 10000 1 2 total P1 -0.000208 0.000208
10 10000 1 2 total P2 -0.000104 0.000199
11 10000 1 2 total P3 0.000236 0.000208
4 10000 2 1 total P0 0.000887 0.001538
5 10000 2 1 total P1 -0.000737 0.001277
6 10000 2 1 total P2 0.000474 0.000821
7 10000 2 1 total P3 -0.000165 0.000285
0 10000 2 2 total P0 0.394772 0.033999
1 10000 2 2 total P1 0.015813 0.004491
2 10000 2 2 total P2 0.006113 0.010134
3 10000 2 2 total P3 -0.010073 0.010045
material group out nuclide mean std. dev.
1 10000 1 total 1.0 0.046071
0 10000 2 total 0.0 0.000000
@ -312,10 +312,10 @@
2 10001 2 2 total P2 0.008811 0.011495
3 10001 2 2 total P3 -0.003261 0.007313
material group in group out nuclide moment mean std. dev.
12 10001 1 1 total P0 0.310121 0.058461
13 10001 1 1 total P1 0.038230 0.010323
14 10001 1 1 total P2 0.020745 0.005677
15 10001 1 1 total P3 0.007964 0.003928
12 10001 1 1 total P0 0.312163 0.050407
13 10001 1 1 total P1 0.038481 0.009693
14 10001 1 1 total P2 0.020882 0.005342
15 10001 1 1 total P3 0.008017 0.003876
8 10001 1 2 total P0 0.000000 0.000000
9 10001 1 2 total P1 0.000000 0.000000
10 10001 1 2 total P2 0.000000 0.000000
@ -324,10 +324,10 @@
5 10001 2 1 total P1 0.000000 0.000000
6 10001 2 1 total P2 0.000000 0.000000
7 10001 2 1 total P3 0.000000 0.000000
0 10001 2 2 total P0 0.296264 0.074019
1 10001 2 2 total P1 -0.011214 0.016337
2 10001 2 2 total P2 0.008837 0.011641
3 10001 2 2 total P3 -0.003270 0.007358
0 10001 2 2 total P0 0.295421 0.065529
1 10001 2 2 total P1 -0.011182 0.016240
2 10001 2 2 total P2 0.008811 0.011563
3 10001 2 2 total P3 -0.003261 0.007328
material group out nuclide mean std. dev.
1 10001 1 total 0.0 0.0
0 10001 2 total 0.0 0.0
@ -524,22 +524,22 @@
2 10002 2 2 total P2 0.110372 0.018488
3 10002 2 2 total P3 0.024808 0.008771
material group in group out nuclide moment mean std. dev.
12 10002 1 1 total P0 0.639901 0.042639
13 10002 1 1 total P1 0.381167 0.026312
14 10002 1 1 total P2 0.152392 0.011619
15 10002 1 1 total P3 0.009148 0.003920
8 10002 1 2 total P0 0.031368 0.002988
9 10002 1 2 total P1 0.008758 0.001149
10 10002 1 2 total P2 -0.002568 0.001033
11 10002 1 2 total P3 -0.003785 0.000868
4 10002 2 1 total P0 0.000443 0.000771
5 10002 2 1 total P1 0.000400 0.000696
6 10002 2 1 total P2 0.000320 0.000556
7 10002 2 1 total P3 0.000214 0.000372
0 10002 2 2 total P0 2.034945 0.468587
1 10002 2 2 total P1 0.509940 0.110635
2 10002 2 2 total P2 0.111175 0.025030
3 10002 2 2 total P3 0.024988 0.009601
12 10002 1 1 total P0 0.632859 0.045297
13 10002 1 1 total P1 0.376973 0.027825
14 10002 1 1 total P2 0.150715 0.012148
15 10002 1 1 total P3 0.009047 0.003884
8 10002 1 2 total P0 0.031023 0.003064
9 10002 1 2 total P1 0.008661 0.001159
10 10002 1 2 total P2 -0.002540 0.001024
11 10002 1 2 total P3 -0.003743 0.000864
4 10002 2 1 total P0 0.000440 0.000765
5 10002 2 1 total P1 0.000397 0.000690
6 10002 2 1 total P2 0.000317 0.000551
7 10002 2 1 total P3 0.000212 0.000369
0 10002 2 2 total P0 2.020256 0.446601
1 10002 2 2 total P1 0.506260 0.104875
2 10002 2 2 total P2 0.110372 0.023809
3 10002 2 2 total P3 0.024808 0.009397
material group out nuclide mean std. dev.
1 10002 1 total 0.0 0.0
0 10002 2 total 0.0 0.0

598
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 @@
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