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Add property setters for Tally.scores, nuclides, filters, triggers

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This commit is contained in:
Paul Romano 2016-02-02 10:07:08 -06:00
parent 12f2467d6e
commit 9b152b0ddf
14 changed files with 257 additions and 279 deletions
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7
examples/python/pincell/build-xml.py
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@ -196,11 +196,8 @@ mesh_filter.mesh = mesh
# Instantiate the Tally
tally = openmc.Tally(tally_id=1, name='tally 1')
tally.add_filter(energy_filter)
tally.add_filter(mesh_filter)
tally.add_score('flux')
tally.add_score('fission')
tally.add_score('nu-fission')
tally.filters = [energy_filter, mesh_filter]
tally.scores = ['flux', 'fission', 'nu-fission']
# Instantiate a TalliesFile, register all Tallies, and export to XML
tallies_file = openmc.TalliesFile()