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processing all reactions for ENDF 7.1 chain file #84

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processing all reactions for ENDF 7.1 chain file #84

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11 changes: 8 additions & 3 deletions depletion/generate_endf71_chain.py
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Original file line number Diff line number Diff line change
Expand Up @@ -31,19 +31,24 @@ def main():

decay_files = list((endf_dir / "decay").glob("*endf"))
neutron_files = list((endf_dir / "neutrons").glob("*endf"))
nfy_files = list((endf_dir / "nfy").glob("*endf"))
fpy_files = list((endf_dir / "nfy").glob("*endf"))

# Remove erroneous Be7 evaluation that can cause problems
decay_files.remove(endf_dir / "decay" / "dec-004_Be_007.endf")
neutron_files.remove(endf_dir / "neutrons" / "n-004_Be_007.endf")

# check files exist
for flist, ftype in [(decay_files, "decay"), (neutron_files, "neutron"),
(nfy_files, "neutron fission product yield")]:
(fpy_files, "neutron fission product yield")]:
if not flist:
raise IOError("No {} endf files found in {}".format(ftype, endf_dir))

chain = openmc.deplete.Chain.from_endf(decay_files, nfy_files, neutron_files)
chain = openmc.deplete.Chain.from_endf(
decay_files=decay_files,
fpy_files=fpy_files,
neutron_files=neutron_files,
reactions=list(openmc.deplete.chain.REACTIONS.keys())
)
chain.export_to_xml('chain_endfb71.xml')


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