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added helpful dict with reaction names as keys

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This commit is contained in:
Jonathan Shimwell 2020-10-08 17:08:24 +01:00
parent 869d7205a3
commit 1c01fe751d
2 changed files with 6 additions and 5 deletions
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2
openmc/data/reaction.py
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@ -64,6 +64,8 @@ REACTION_NAME.update({i: '(n,3He{})'.format(i - 750) for i in range(750, 799)})
REACTION_NAME.update({i: '(n,a{})'.format(i - 800) for i in range(800, 849)})
REACTION_NAME.update({i: '(n,2n{})'.format(i - 875) for i in range(875, 891)})
REACTION_NUMBER = dict(zip(REACTION_NAME.values(), REACTION_NAME.keys()))
FISSION_MTS = (18, 19, 20, 21, 38)

9
openmc/deplete/helpers.py
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@ -11,7 +11,7 @@ from numpy import dot, zeros, newaxis, asarray
from . import comm
from openmc.checkvalue import check_type, check_greater_than
from openmc.data import JOULE_PER_EV, REACTION_NAME
from openmc.data import JOULE_PER_EV, REACTION_NUMBER
from openmc.lib import (
Tally, MaterialFilter, EnergyFilter, EnergyFunctionFilter)
import openmc.lib
@ -168,10 +168,9 @@ class FluxCollapseHelper(ReactionRateHelper):
"""
self._materials = materials
# Convert reactions to MT values (needed when collapsing)
mt_values = {v: k for k, v in REACTION_NAME.items()}
mt_values['fission'] = 18
self._mts = [mt_values[x] for x in scores]
# adds an entry for fisson to the dictionary of reactions
REACTION_NUMBER['fission'] = 18
self._mts = [REACTION_NUMBER[x] for x in scores]
self._scores = scores
# Create flux tally with material and energy filters