From 91a6454f7309126ea8d8bb96c839ceaf00ba0af1 Mon Sep 17 00:00:00 2001 From: Sterling Harper Date: Thu, 4 Oct 2018 14:01:01 -0400 Subject: [PATCH] Remove reference to compact MT 458 data --- scripts/openmc-convert-mcnp71-data | 9 --------- 1 file changed, 9 deletions(-) diff --git a/scripts/openmc-convert-mcnp71-data b/scripts/openmc-convert-mcnp71-data index ce8c427d60..eaaad078dd 100755 --- a/scripts/openmc-convert-mcnp71-data +++ b/scripts/openmc-convert-mcnp71-data @@ -25,8 +25,6 @@ parser = argparse.ArgumentParser( ) parser.add_argument('-d', '--destination', default='mcnp_endfb71', help='Directory to create new library in') -parser.add_argument('-f', '--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 " @@ -64,13 +62,6 @@ for basename, xs_list in sorted(suffixes.items()): else: data = openmc.data.IncidentNeutron.from_ace(filename, 'mcnp') - # Add 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, data) - if fer is not None: - data.fission_energy = fer - # For each higher temperature, add cross sections to the existing table for xs in xs_list[1:]: filename = '.'.join((basename, xs))