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Address #698 comments
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3 changed files with 8 additions and 8 deletions
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@ -9,8 +9,8 @@ ENDF-102_ for details). It gives the information needed to compute the energy
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carried away from fission reactions by each reaction product (e.g. fragment
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nuclei, neutrons) which depends on the incident neutron energy. OpenMC is
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distributed with one of these files under
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openmc/data/fission_Q_data_endfb71.h5. More files of this format can be
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created from ENDF files with the
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data/fission_Q_data_endfb71.h5. More files of this format can be created from
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ENDF files with the
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``openmc.data.write_compact_458_library`` function. They can be read with the
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``openmc.data.FissionEnergyRelease.from_compact_hdf5`` class method.
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@ -13,12 +13,11 @@ INTERPOLATION_SCHEME = {1: 'histogram', 2: 'linear-linear', 3: 'linear-log',
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class Function1D(object):
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"""A function of one independent variable with HDF5 support."""
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__metaclass__ = ABCMeta
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def __init__(self): pass
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@abstractmethod
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def __call__(self): pass
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def __call__(self):
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raise NotImplemented('Subclasses of Function1D should overwrite the '
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'__call__ and to_hdf5 methods')
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@abstractmethod
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def to_hdf5(self, group, name='xy'):
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@ -32,7 +31,8 @@ class Function1D(object):
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Name of the dataset to create
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"""
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pass
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raise NotImplemented('Subclasses of Function1D should overwrite the '
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'__call__ and to_hdf5 methods')
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@classmethod
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def from_hdf5(cls, dataset):
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@ -124,7 +124,7 @@ for filename in ace_libraries:
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# Fission energy release data, if available
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if args.fission_energy_release is not None:
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fer = openmc.data.FissionEnergyRelease.from_compact_hdf5(
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args.fission_energy_release, neutron)
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args.fission_energy_release, neutron)
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if fer is not None:
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neutron.fission_energy = fer
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