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Don't put free neutron in depletion chain

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This commit is contained in:
Paul Romano 2018-03-01 23:09:10 -06:00
parent 7ee08d5280
commit b9ff205090
1 changed files with 7 additions and 0 deletions
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7
openmc/deplete/chain.py
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@ -59,6 +59,10 @@ def replace_missing(product, decay_data):
Z, A, state = openmc.data.zam(product)
symbol = openmc.data.ATOMIC_SYMBOL[Z]
# Replace neutron with proton
if Z == 0 and A == 1:
return 'H1'
# First check if ground state is available
if state:
product = '{}{}'.format(symbol, A)
@ -167,6 +171,9 @@ class Chain(object):
decay_data = {}
for f in decay_files:
data = openmc.data.Decay(f)
# Skip decay data for neutron itself
if data.nuclide['atomic_number'] == 0:
continue
decay_data[data.nuclide['name']] = data
print('Processing fission product yield sub-library files...')