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load any nuclide requested that is not present in materials prior to constructing tally

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This commit is contained in:
Kalin Kiesling 2023-03-22 12:45:33 -05:00
parent ed02703f4b
commit 5160417e3e
1 changed files with 9 additions and 3 deletions
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12
openmc/deplete/helpers.py
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@ -15,7 +15,7 @@ from openmc.mpi import comm
from openmc.checkvalue import check_type, check_greater_than
from openmc.data import JOULE_PER_EV, REACTION_MT
from openmc.lib import (
Tally, MaterialFilter, EnergyFilter, EnergyFunctionFilter)
Tally, MaterialFilter, EnergyFilter, EnergyFunctionFilter, load_nuclide)
import openmc.lib
from .abc import (
ReactionRateHelper, NormalizationHelper, FissionYieldHelper)
@ -189,7 +189,7 @@ class DirectReactionRateHelper(ReactionRateHelper):
def reset_tally_means(self):
"""Reset the cached mean rate tallies.
.. note::
This step must be performed after each transport cycle
"""
self._rate_tally_means_cache = None
@ -306,6 +306,12 @@ class FluxCollapseHelper(ReactionRateHelper):
self._rate_tally.filters = [MaterialFilter(materials)]
self._rate_tally_means_cache = None
if self._nuclides_direct is not None:
# check if any direct tally nuclides are requested that are not
# already loaded with the materials. Load separately if so.
mat_nuclides = [n for mat in materials for n in mat.nuclides]
extra_nuclides = set(self._nuclides_direct) - set(mat_nuclides)
for nuc in extra_nuclides:
load_nuclide(nuc)
self._rate_tally.nuclides = self._nuclides_direct
@property
@ -327,7 +333,7 @@ class FluxCollapseHelper(ReactionRateHelper):
def reset_tally_means(self):
"""Reset the cached mean rate and flux tallies.
.. note::
This step must be performed after each transport cycle
"""
self._flux_tally_means_cache = None