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Merge pull request #1032 from paulromano/endf8-fixes

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Tabulated fission energy release
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Sterling Harper 2018-08-07 09:44:51 -05:00 • committed by GitHub
commit 90cc31629a
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6 changed files with 209 additions and 393 deletions
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16
scripts/openmc-ace-to-hdf5
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@ -25,13 +25,6 @@ follows the NNDC data convention (1000*Z + A + 300 + 100*m), or the MCNP data
convention (essentially the same as NNDC, except that the first metastable state
of Am242 is 95242 and the ground state is 95642).
The optional --fission_energy_release argument will accept an HDF5 file
containing a library of fission energy release (ENDF MF=1 MT=458) data. A
library built from ENDF/B-VII.1 data is released with OpenMC and can be found at
openmc/data/fission_Q_data_endb71.h5. This data is necessary for
'fission-q-prompt' and 'fission-q-recoverable' tallies, but is not needed
otherwise.
"""
class CustomFormatter(argparse.ArgumentDefaultsHelpFormatter,
@ -55,8 +48,6 @@ parser.add_argument('--xsdir', help='MCNP xsdir file that lists '
'ACE libraries')
parser.add_argument('--xsdata', help='Serpent xsdata file that lists '
'ACE libraries')
parser.add_argument('--fission_energy_release', help='HDF5 file containing '
'fission energy release data')
parser.add_argument('--libver', choices=['earliest', 'latest'],
default='earliest', help="Output HDF5 versioning. Use "
"'earliest' for backwards compatibility or 'latest' for "
@ -142,13 +133,6 @@ for filename in ace_libraries:
print('Failed to convert {}: {}'.format(table.name, e))
continue
# Fission energy release data, if available
if args.fission_energy_release is not None:
fer = openmc.data.FissionEnergyRelease.from_compact_hdf5(
args.fission_energy_release, neutron)
if fer is not None:
neutron.fission_energy = fer
print('Converting {} (ACE) to {} (HDF5)'.format(table.name,
neutron.name))