added mdgxs tallies to mgxs tests and addressed other PR comments

This commit is contained in:
Sam Shaner 2016-08-05 08:37:57 -04:00
parent ab96c3d874
commit 469c7ff38e
19 changed files with 493 additions and 67 deletions

View file

@ -376,9 +376,10 @@ class DelayedGroups(object):
# Check that the groups are within [1, MAX_DELAYED_GROUPS]
for group in groups:
cv.check_greater_than('delayed group', group, 0)
cv.check_less_than('delayed group', group, MAX_DELAYED_GROUPS + 1)
cv.check_less_than('delayed group', group, MAX_DELAYED_GROUPS,
equality=True)
self._groups = np.array(groups, dtype=int)
self._groups = np.asarray(groups, dtype=int)
def can_merge(self, other):
"""Determine if delayed groups can be merged with another.
@ -395,10 +396,7 @@ class DelayedGroups(object):
"""
if not isinstance(other, DelayedGroups):
return False
else:
return True
return isinstance(other, DelayedGroups)
def merge(self, other):
"""Merge this delayed groups with another.
@ -424,7 +422,7 @@ class DelayedGroups(object):
# Merge unique filter bins
groups = np.concatenate((self.groups, other.groups))
groups = np.unique(groups)
groups = sorted(groups)
groups.sort()
# Assign groups to merged groups
merged_groups.groups = list(groups)

View file

@ -255,8 +255,7 @@ class Library(object):
@mgxs_types.setter
def mgxs_types(self, mgxs_types):
all_mgxs_types = np.append(openmc.mgxs.MGXS_TYPES,
openmc.mgxs.MDGXS_TYPES)
all_mgxs_types = openmc.mgxs.MGXS_TYPES + openmc.mgxs.MDGXS_TYPES
if mgxs_types == 'all':
self._mgxs_types = all_mgxs_types
else:
@ -270,7 +269,7 @@ class Library(object):
cv.check_type('by_nuclide', by_nuclide, bool)
if by_nuclide == True and self.domain_type == 'mesh':
raise ValueError('Unable to create MGXS library by nuclide with ' +
raise ValueError('Unable to create MGXS library by nuclide with '
'mesh domain')
self._by_nuclide = by_nuclide
@ -280,7 +279,7 @@ class Library(object):
cv.check_value('domain type', domain_type, openmc.mgxs.DOMAIN_TYPES)
if self.by_nuclide == True and domain_type == 'mesh':
raise ValueError('Unable to create MGXS library by nuclide with ' +
raise ValueError('Unable to create MGXS library by nuclide with '
'mesh domain')
self._domain_type = domain_type

View file

@ -254,7 +254,7 @@ contains
! Right surface
if (i < nx) then
matching_bins(i_filter_mesh) = mesh_indices_to_bin(m, &
(/ i+1, j, k /) )
(/ i+1, j, k /) )
matching_bins(i_filter_surf) = OUT_LEFT
score_index = sum((matching_bins(1:size(t % filters)) - 1) &
* t % stride) + 1 ! incoming

View file

@ -1 +1 @@
e2cdca7ea5b3532050af5b12fac26d7ef212d2696bb1b73cdd00929b2243c40d100ad02438c7b090555b49815d0de6c48cf1b4ebf437a48bc80c2d2b4bad292e
08c5f1c783dd88c5fed51c054718ca09fc4e99aa4560a6f928b3902991948f3a878d055ac46c07548904285c2c5f22dc2a3d8c1bb82b8e73d76dd790820117df

View file

@ -40,6 +40,27 @@
0 10000 1 total 4.996730e-07 3.650635e-08
material group in nuclide mean std. dev.
0 10000 1 total 0.090004 0.006367
material delayedgroup group in nuclide mean std. dev.
0 10000 1 1 total 0.000021 0.000001
1 10000 2 1 total 0.000110 0.000008
2 10000 3 1 total 0.000107 0.000007
3 10000 4 1 total 0.000249 0.000017
4 10000 5 1 total 0.000112 0.000007
5 10000 6 1 total 0.000046 0.000003
material delayedgroup group out nuclide mean std. dev.
0 10000 1 1 total 0.0 0.000000
1 10000 2 1 total 1.0 0.869128
2 10000 3 1 total 1.0 1.414214
3 10000 4 1 total 1.0 0.360359
4 10000 5 1 total 0.0 0.000000
5 10000 6 1 total 0.0 0.000000
material delayedgroup group in nuclide mean std. dev.
0 10000 1 1 total 0.000227 0.000020
1 10000 2 1 total 0.001214 0.000108
2 10000 3 1 total 0.001184 0.000104
3 10000 4 1 total 0.002752 0.000240
4 10000 5 1 total 0.001231 0.000105
5 10000 6 1 total 0.000512 0.000044
material group in nuclide mean std. dev.
0 10001 1 total 0.311594 0.013793
material group in nuclide mean std. dev.
@ -82,6 +103,27 @@
0 10001 1 total 5.454760e-07 4.949800e-08
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
material delayedgroup group out nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.904999 0.043964
material group in nuclide mean std. dev.
@ -124,3 +166,24 @@
0 10002 1 total 5.773006e-07 5.322132e-08
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0
material delayedgroup group out nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0

View file

@ -23,12 +23,18 @@ class MGXSTestHarness(PyAPITestHarness):
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize a six-delayed-group structure
delayed_groups = openmc.mgxs.DelayedGroups(range(1,7))
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()

View file

@ -1 +1 @@
2d948f3b12293294eaeca231a3df9d51195379e8bb38dd3e68d3bc512a7d08ed52a1109054ca381684ec127268710f6d6e9210ac8154c9b379608e996627624a
5e4bd179eeb955f61e01dc2a486e3fefd2cef7859390f12a817cd5412359766d7bfe0bf3f8553e8d28af0844ee04a4ebaad6510ec6157ee836d631a2a2b3baec

View file

@ -1,42 +1,63 @@
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 1.145934 0.553822
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.718919 0.520644
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.019762 0.010629
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.019762 0.010629
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 1.126172 0.54344
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 1.142547 0.570131
avg(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 1.142547 0.570131
1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 0.216322
2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 0.066504
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 0.024621
avg(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 1.142547 0.570131
1 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P1 0.447381 0.216322
2 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P2 0.141202 0.066504
3 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 1 total P3 0.039228 0.024621
avg(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 0.529717
avg(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 0.0 0.0
avg(distribcell) group out nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group out nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.000001 6.946255e-07
avg(distribcell) group in nuclide mean std. dev.
0 (0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13,... 1 total 0.0 0.0
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.453624 0.02261
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.400852 0.024589
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.400852 0.024589
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.064903 0.004684
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.028048 0.004982
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.036855 0.002749
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.090649 0.006763
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 7.137955 0.532092
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.388721 0.018415
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.389304 0.023619
avg(distribcell) group in group out nuclide moment mean std. dev.
0 (0,) 1 1 total P0 0.389304 0.023619
1 (0,) 1 1 total P1 0.046224 0.005672
2 (0,) 1 1 total P2 0.017984 0.002178
3 (0,) 1 1 total P3 0.006628 0.001620
avg(distribcell) group in group out nuclide moment mean std. dev.
0 (0,) 1 1 total P0 0.389304 0.023619
1 (0,) 1 1 total P1 0.046224 0.005672
2 (0,) 1 1 total P2 0.017984 0.002178
3 (0,) 1 1 total P3 0.006628 0.001620
avg(distribcell) group in group out nuclide mean std. dev.
0 (0,) 1 1 total 1.0 0.066327
avg(distribcell) group in group out nuclide mean std. dev.
0 (0,) 1 1 total 0.085835 0.004328
avg(distribcell) group out nuclide mean std. dev.
0 (0,) 1 total 1.0 0.046071
avg(distribcell) group out nuclide mean std. dev.
0 (0,) 1 total 1.0 0.051471
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 4.996730e-07 3.741595e-08
avg(distribcell) group in nuclide mean std. dev.
0 (0,) 1 total 0.090004 0.006717
avg(distribcell) delayedgroup group in nuclide mean std. dev.
0 (0,) 1 1 total 0.000021 0.000002
1 (0,) 2 1 total 0.000110 0.000008
2 (0,) 3 1 total 0.000107 0.000008
3 (0,) 4 1 total 0.000249 0.000018
4 (0,) 5 1 total 0.000112 0.000008
5 (0,) 6 1 total 0.000046 0.000003
avg(distribcell) delayedgroup group out nuclide mean std. dev.
0 (0,) 1 1 total 0.0 0.000000
1 (0,) 2 1 total 1.0 0.869128
2 (0,) 3 1 total 1.0 1.414214
3 (0,) 4 1 total 1.0 0.360359
4 (0,) 5 1 total 0.0 0.000000
5 (0,) 6 1 total 0.0 0.000000
avg(distribcell) delayedgroup group in nuclide mean std. dev.
0 (0,) 1 1 total 0.000227 0.000022
1 (0,) 2 1 total 0.001214 0.000115
2 (0,) 3 1 total 0.001184 0.000111
3 (0,) 4 1 total 0.002752 0.000257
4 (0,) 5 1 total 0.001231 0.000113
5 (0,) 6 1 total 0.000512 0.000047

View file

@ -6,29 +6,39 @@ import glob
import hashlib
sys.path.insert(0, os.pardir)
from testing_harness import PyAPITestHarness
from input_set import PinCellInputSet
import openmc
import openmc.mgxs
class MGXSTestHarness(PyAPITestHarness):
def _build_inputs(self):
# Set the input set to use the pincell model
self._input_set = PinCellInputSet()
# Generate inputs using parent class routine
super(MGXSTestHarness, self)._build_inputs()
# Initialize a one-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 20.])
# Initialize a six-delayed-group structure
delayed_groups = openmc.mgxs.DelayedGroups(range(1,7))
# Initialize MGXS Library for a few cross section types
# for one material-filled cell in the geometry
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'distribcell'
material_cells = self.mgxs_lib.openmc_geometry.get_all_material_cells()
self.mgxs_lib.domains = [material_cells[-1]]
cells = self.mgxs_lib.openmc_geometry.get_all_material_cells()
self.mgxs_lib.domains = [c for c in cells if c.name == 'cell 1']
self.mgxs_lib.build_library()
# Initialize a tallies file

View file

@ -1 +1 @@
e2cdca7ea5b3532050af5b12fac26d7ef212d2696bb1b73cdd00929b2243c40d100ad02438c7b090555b49815d0de6c48cf1b4ebf437a48bc80c2d2b4bad292e
08c5f1c783dd88c5fed51c054718ca09fc4e99aa4560a6f928b3902991948f3a878d055ac46c07548904285c2c5f22dc2a3d8c1bb82b8e73d76dd790820117df

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@ -72,6 +72,45 @@ domain=10000 type=inverse-velocity
domain=10000 type=prompt-nu-fission
[ 0.01923922 0.46671903]
[ 0.00130951 0.04141087]
domain=10000 type=delayed-nu-fission
[[ 2.29808234e-05 1.06974158e-04]
[ 1.43606337e-04 5.52167907e-04]
[ 1.51382216e-04 5.27147681e-04]
[ 7.42603178e-05 2.22018043e-04]
[ 4.14908454e-05 9.10244403e-05]
[ 1.70016000e-05 3.81298119e-05]]
[[ 1.66363133e-06 9.49156242e-06]
[ 1.05907806e-05 4.89925426e-05]
[ 1.12671238e-05 4.67725567e-05]
[ 5.22610273e-06 1.87563195e-05]
[ 2.99830766e-06 7.68984041e-06]
[ 1.22654684e-06 3.22124663e-06]]
domain=10000 type=chi-delayed
[[ 0. 0.]
[ 1. 0.]
[ 1. 0.]
[ 1. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0. ]
[ 0.86912776 0. ]
[ 1.41421356 0. ]
[ 0.36035904 0. ]
[ 0. 0. ]
[ 0. 0. ]]
domain=10000 type=beta
[[ 4.89188107e-05 2.27713711e-04]
[ 3.05691886e-04 1.17538858e-03]
[ 3.22244241e-04 1.12212853e-03]
[ 3.82159891e-03 1.14255357e-02]
[ 2.13520995e-03 4.68431744e-03]
[ 8.74939644e-04 1.96224379e-03]]
[[ 4.67388620e-06 2.46946810e-05]
[ 2.95223877e-05 1.27466393e-04]
[ 3.12885004e-05 1.21690543e-04]
[ 3.21434855e-04 1.09939816e-03]
[ 1.82980497e-04 4.50738567e-04]
[ 7.48899920e-05 1.88812772e-04]]
domain=10001 type=total
[ 0.31373767 0.3008214 ]
[ 0.0155819 0.02805245]
@ -146,6 +185,45 @@ domain=10001 type=inverse-velocity
domain=10001 type=prompt-nu-fission
[ 0. 0.]
[ 0. 0.]
domain=10001 type=delayed-nu-fission
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
domain=10001 type=chi-delayed
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
domain=10001 type=beta
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
domain=10002 type=total
[ 0.66457226 2.05238401]
[ 0.03121475 0.22434291]
@ -220,3 +298,42 @@ domain=10002 type=inverse-velocity
domain=10002 type=prompt-nu-fission
[ 0. 0.]
[ 0. 0.]
domain=10002 type=delayed-nu-fission
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
domain=10002 type=chi-delayed
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
domain=10002 type=beta
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]
[[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]
[ 0. 0.]]

View file

@ -24,12 +24,18 @@ class MGXSTestHarness(PyAPITestHarness):
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize a six-delayed-group structure
delayed_groups = openmc.mgxs.DelayedGroups(range(1,7))
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()

View file

@ -1 +1 @@
a4cd030bea212e45fdb159e75a7fb3d1947e9bf3d0384ac5d37a72298d67dcfdd1b9eb5c6af8ac6e5983bd5b47de9c17a2ea472b467b7222a4909ee070bf1ca3
5f167bdd4d6ae5873d48483e85aceaec8a934239ed5a50ef6f6500ce204f5851ae330621a5007f3b3d6bdab49f2cd627d011c1f6e6983fec958a6984eb9cb7ca

View file

@ -130,3 +130,81 @@
1 1 2 1 1 total 0.028922 0.006394
2 2 1 1 1 total 0.022467 0.004039
3 2 2 1 1 total 0.024923 0.009632
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.000004 4.432732e-07
1 1 1 1 2 1 total 0.000026 2.653319e-06
2 1 1 1 3 1 total 0.000024 2.402270e-06
3 1 1 1 4 1 total 0.000054 5.464055e-06
4 1 1 1 5 1 total 0.000026 2.663025e-06
5 1 1 1 6 1 total 0.000010 1.038005e-06
6 1 2 1 1 1 total 0.000005 1.098837e-06
7 1 2 1 2 1 total 0.000029 6.436855e-06
8 1 2 1 3 1 total 0.000027 5.926286e-06
9 1 2 1 4 1 total 0.000061 1.359391e-05
10 1 2 1 5 1 total 0.000029 6.489015e-06
11 1 2 1 6 1 total 0.000011 2.574270e-06
12 2 1 1 1 1 total 0.000004 6.987770e-07
13 2 1 1 2 1 total 0.000023 4.115234e-06
14 2 1 1 3 1 total 0.000021 3.816392e-06
15 2 1 1 4 1 total 0.000049 8.885822e-06
16 2 1 1 5 1 total 0.000024 4.378290e-06
17 2 1 1 6 1 total 0.000009 1.745695e-06
18 2 2 1 1 1 total 0.000004 1.660497e-06
19 2 2 1 2 1 total 0.000025 9.701974e-06
20 2 2 1 3 1 total 0.000023 9.005217e-06
21 2 2 1 4 1 total 0.000054 2.084107e-05
22 2 2 1 5 1 total 0.000026 9.981045e-06
23 2 2 1 6 1 total 0.000010 3.987979e-06
mesh 1 delayedgroup group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.0 0.000000
1 1 1 1 2 1 total 0.0 0.000000
2 1 1 1 3 1 total 0.0 0.000000
3 1 1 1 4 1 total 1.0 1.414214
4 1 1 1 5 1 total 0.0 0.000000
5 1 1 1 6 1 total 0.0 0.000000
6 1 2 1 1 1 total 0.0 0.000000
7 1 2 1 2 1 total 0.0 0.000000
8 1 2 1 3 1 total 0.0 0.000000
9 1 2 1 4 1 total 0.0 0.000000
10 1 2 1 5 1 total 0.0 0.000000
11 1 2 1 6 1 total 0.0 0.000000
12 2 1 1 1 1 total 0.0 0.000000
13 2 1 1 2 1 total 0.0 0.000000
14 2 1 1 3 1 total 0.0 0.000000
15 2 1 1 4 1 total 0.0 0.000000
16 2 1 1 5 1 total 0.0 0.000000
17 2 1 1 6 1 total 0.0 0.000000
18 2 2 1 1 1 total 0.0 0.000000
19 2 2 1 2 1 total 0.0 0.000000
20 2 2 1 3 1 total 0.0 0.000000
21 2 2 1 4 1 total 0.0 0.000000
22 2 2 1 5 1 total 0.0 0.000000
23 2 2 1 6 1 total 0.0 0.000000
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.000166 0.000023
1 1 1 1 2 1 total 0.000989 0.000136
2 1 1 1 3 1 total 0.000907 0.000123
3 1 1 1 4 1 total 0.002087 0.000282
4 1 1 1 5 1 total 0.001014 0.000137
5 1 1 1 6 1 total 0.000400 0.000054
6 1 2 1 1 1 total 0.000171 0.000039
7 1 2 1 2 1 total 0.001003 0.000226
8 1 2 1 3 1 total 0.000918 0.000208
9 1 2 1 4 1 total 0.002100 0.000477
10 1 2 1 5 1 total 0.000996 0.000228
11 1 2 1 6 1 total 0.000394 0.000090
12 2 1 1 1 1 total 0.000167 0.000030
13 2 1 1 2 1 total 0.001002 0.000178
14 2 1 1 3 1 total 0.000926 0.000165
15 2 1 1 4 1 total 0.002149 0.000384
16 2 1 1 5 1 total 0.001056 0.000189
17 2 1 1 6 1 total 0.000417 0.000076
18 2 2 1 1 1 total 0.000171 0.000082
19 2 2 1 2 1 total 0.001007 0.000480
20 2 2 1 3 1 total 0.000929 0.000445
21 2 2 1 4 1 total 0.002143 0.001028
22 2 2 1 5 1 total 0.001026 0.000492
23 2 2 1 6 1 total 0.000408 0.000196

View file

@ -18,14 +18,19 @@ class MGXSTestHarness(PyAPITestHarness):
# Initialize a one-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 20.])
# Initialize a six-delayed-group structure
delayed_groups = openmc.mgxs.DelayedGroups(range(1,7))
# Initialize MGXS Library for a few cross section types
# for one material-filled cell in the geometry
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'mesh'

View file

@ -1 +1 @@
e2cdca7ea5b3532050af5b12fac26d7ef212d2696bb1b73cdd00929b2243c40d100ad02438c7b090555b49815d0de6c48cf1b4ebf437a48bc80c2d2b4bad292e
08c5f1c783dd88c5fed51c054718ca09fc4e99aa4560a6f928b3902991948f3a878d055ac46c07548904285c2c5f22dc2a3d8c1bb82b8e73d76dd790820117df

View file

@ -84,6 +84,45 @@
material group in nuclide mean std. dev.
1 10000 1 total 0.019239 0.001310
0 10000 2 total 0.466719 0.041411
material delayedgroup group in nuclide mean std. dev.
1 10000 1 1 total 0.000023 0.000002
3 10000 2 1 total 0.000144 0.000011
5 10000 3 1 total 0.000151 0.000011
7 10000 4 1 total 0.000074 0.000005
9 10000 5 1 total 0.000041 0.000003
11 10000 6 1 total 0.000017 0.000001
0 10000 1 2 total 0.000107 0.000009
2 10000 2 2 total 0.000552 0.000049
4 10000 3 2 total 0.000527 0.000047
6 10000 4 2 total 0.000222 0.000019
8 10000 5 2 total 0.000091 0.000008
10 10000 6 2 total 0.000038 0.000003
material delayedgroup group out nuclide mean std. dev.
1 10000 1 1 total 0.0 0.000000
3 10000 2 1 total 1.0 0.869128
5 10000 3 1 total 1.0 1.414214
7 10000 4 1 total 1.0 0.360359
9 10000 5 1 total 0.0 0.000000
11 10000 6 1 total 0.0 0.000000
0 10000 1 2 total 0.0 0.000000
2 10000 2 2 total 0.0 0.000000
4 10000 3 2 total 0.0 0.000000
6 10000 4 2 total 0.0 0.000000
8 10000 5 2 total 0.0 0.000000
10 10000 6 2 total 0.0 0.000000
material delayedgroup group in nuclide mean std. dev.
1 10000 1 1 total 0.000049 0.000005
3 10000 2 1 total 0.000306 0.000030
5 10000 3 1 total 0.000322 0.000031
7 10000 4 1 total 0.003822 0.000321
9 10000 5 1 total 0.002135 0.000183
11 10000 6 1 total 0.000875 0.000075
0 10000 1 2 total 0.000228 0.000025
2 10000 2 2 total 0.001175 0.000127
4 10000 3 2 total 0.001122 0.000122
6 10000 4 2 total 0.011426 0.001099
8 10000 5 2 total 0.004684 0.000451
10 10000 6 2 total 0.001962 0.000189
material group in nuclide mean std. dev.
1 10001 1 total 0.313738 0.015582
0 10001 2 total 0.300821 0.028052
@ -170,6 +209,45 @@
material group in nuclide mean std. dev.
1 10001 1 total 0.0 0.0
0 10001 2 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
1 10001 1 1 total 0.0 0.0
3 10001 2 1 total 0.0 0.0
5 10001 3 1 total 0.0 0.0
7 10001 4 1 total 0.0 0.0
9 10001 5 1 total 0.0 0.0
11 10001 6 1 total 0.0 0.0
0 10001 1 2 total 0.0 0.0
2 10001 2 2 total 0.0 0.0
4 10001 3 2 total 0.0 0.0
6 10001 4 2 total 0.0 0.0
8 10001 5 2 total 0.0 0.0
10 10001 6 2 total 0.0 0.0
material delayedgroup group out nuclide mean std. dev.
1 10001 1 1 total 0.0 0.0
3 10001 2 1 total 0.0 0.0
5 10001 3 1 total 0.0 0.0
7 10001 4 1 total 0.0 0.0
9 10001 5 1 total 0.0 0.0
11 10001 6 1 total 0.0 0.0
0 10001 1 2 total 0.0 0.0
2 10001 2 2 total 0.0 0.0
4 10001 3 2 total 0.0 0.0
6 10001 4 2 total 0.0 0.0
8 10001 5 2 total 0.0 0.0
10 10001 6 2 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
1 10001 1 1 total 0.0 0.0
3 10001 2 1 total 0.0 0.0
5 10001 3 1 total 0.0 0.0
7 10001 4 1 total 0.0 0.0
9 10001 5 1 total 0.0 0.0
11 10001 6 1 total 0.0 0.0
0 10001 1 2 total 0.0 0.0
2 10001 2 2 total 0.0 0.0
4 10001 3 2 total 0.0 0.0
6 10001 4 2 total 0.0 0.0
8 10001 5 2 total 0.0 0.0
10 10001 6 2 total 0.0 0.0
material group in nuclide mean std. dev.
1 10002 1 total 0.664572 0.031215
0 10002 2 total 2.052384 0.224343
@ -256,3 +334,42 @@
material group in nuclide mean std. dev.
1 10002 1 total 0.0 0.0
0 10002 2 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
1 10002 1 1 total 0.0 0.0
3 10002 2 1 total 0.0 0.0
5 10002 3 1 total 0.0 0.0
7 10002 4 1 total 0.0 0.0
9 10002 5 1 total 0.0 0.0
11 10002 6 1 total 0.0 0.0
0 10002 1 2 total 0.0 0.0
2 10002 2 2 total 0.0 0.0
4 10002 3 2 total 0.0 0.0
6 10002 4 2 total 0.0 0.0
8 10002 5 2 total 0.0 0.0
10 10002 6 2 total 0.0 0.0
material delayedgroup group out nuclide mean std. dev.
1 10002 1 1 total 0.0 0.0
3 10002 2 1 total 0.0 0.0
5 10002 3 1 total 0.0 0.0
7 10002 4 1 total 0.0 0.0
9 10002 5 1 total 0.0 0.0
11 10002 6 1 total 0.0 0.0
0 10002 1 2 total 0.0 0.0
2 10002 2 2 total 0.0 0.0
4 10002 3 2 total 0.0 0.0
6 10002 4 2 total 0.0 0.0
8 10002 5 2 total 0.0 0.0
10 10002 6 2 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
1 10002 1 1 total 0.0 0.0
3 10002 2 1 total 0.0 0.0
5 10002 3 1 total 0.0 0.0
7 10002 4 1 total 0.0 0.0
9 10002 5 1 total 0.0 0.0
11 10002 6 1 total 0.0 0.0
0 10002 1 2 total 0.0 0.0
2 10002 2 2 total 0.0 0.0
4 10002 3 2 total 0.0 0.0
6 10002 4 2 total 0.0 0.0
8 10002 5 2 total 0.0 0.0
10 10002 6 2 total 0.0 0.0

View file

@ -23,12 +23,18 @@ class MGXSTestHarness(PyAPITestHarness):
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize a six-delayed-group structure
delayed_groups = openmc.mgxs.DelayedGroups(range(1,7))
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
# Test all MGXS types
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()

View file

@ -1 +1 @@
bafab1921a12146abb2bb29603b52b9cc28a5a950a7a6bb1e3f012c05891c310fad643760d4f148b04d0fef3d1f3e141d146e3a278d81cc6fc8187c37717c5e7
2800fad5519917ffc985094d3263a3e0aac1abf6acb0c25416264135b36141812cc8d7dafc01585b104b8d6ad03cd44b6ce277fdb7df5a3f859fe26e61244e2a