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Updated openmc-ace-to-hdf5 to generate the libraries for us and fixed bugs as found when developing that script. Also updated the Format description in nuclear_data.rst

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This commit is contained in:
Adam Nelson 2016-08-21 11:37:39 -04:00
parent 3b65dde0fd
commit 63b3c6dbd0
5 changed files with 55 additions and 39 deletions
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18
scripts/openmc-ace-to-hdf5
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@ -130,14 +130,12 @@ for filename in ace_libraries:
if xs.endswith('c'):
# Continuous-energy neutron data
if name not in nuclides:
neutron = openmc.data.IncidentNeutron.from_ace(
try:
neutron = openmc.data.IncidentNeutron.from_ace(
table, args.metastable)
# try:
# neutron = openmc.data.IncidentNeutron.from_ace(
# table, args.metastable)
# except Exception as e:
# print('Failed to convert {}: {}'.format(table.name, e))
# continue
except Exception as e:
print('Failed to convert {}: {}'.format(table.name, e))
continue
# Fission energy release data, if available
if args.fission_energy_release is not None:
@ -172,7 +170,11 @@ for filename in ace_libraries:
elif xs.endswith('t'):
# Thermal scattering data
if name not in nuclides:
thermal = openmc.data.ThermalScattering.from_ace(table)
try:
thermal = openmc.data.ThermalScattering.from_ace(table)
except Exception as e:
print('Failed to convert {}: {}'.format(table.name, e))
continue
print('Converting {} (ACE) to {} (HDF5)'.format(table.name,
thermal.name))