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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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23
examples/python/basic/build-xml.py
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@ -109,29 +109,20 @@ energyout_filter = openmc.Filter(type='energyout', bins=[0., 20.])
# Instantiate the first Tally
first_tally = openmc.Tally(tally_id=1, name='first tally')
first_tally.add_filter(cell_filter)
scores = ['total', 'scatter', 'nu-scatter', \
first_tally.filters = [cell_filter]
scores = ['total', 'scatter', 'nu-scatter',
'absorption', 'fission', 'nu-fission']
for score in scores:
first_tally.add_score(score)
first_tally.scores = scores
# Instantiate the second Tally
second_tally = openmc.Tally(tally_id=2, name='second tally')
second_tally.add_filter(cell_filter)
second_tally.add_filter(energy_filter)
scores = ['total', 'scatter', 'nu-scatter', \
'absorption', 'fission', 'nu-fission']
for score in scores:
second_tally.add_score(score)
second_tally.filters = [cell_filter, energy_filter]
second_tally.scores = scores
# Instantiate the third Tally
third_tally = openmc.Tally(tally_id=3, name='third tally')
third_tally.add_filter(cell_filter)
third_tally.add_filter(energy_filter)
third_tally.add_filter(energyout_filter)
scores = ['scatter', 'nu-scatter', 'nu-fission']
for score in scores:
third_tally.add_score(score)
third_tally.filters = [cell_filter, energy_filter, energyout_filter]
third_tally.scores = ['scatter', 'nu-scatter', 'nu-fission']
# Instantiate a TalliesFile, register all Tallies, and export to XML
tallies_file = openmc.TalliesFile()

4
examples/python/lattice/hexagonal/build-xml.py
View file

@ -166,8 +166,8 @@ plot_file.export_to_xml()
# Instantiate a distribcell Tally
tally = openmc.Tally(tally_id=1)
tally.add_filter(openmc.Filter(type='distribcell', bins=[cell2.id]))
tally.add_score('total')
tally.filters = [openmc.Filter(type='distribcell', bins=[cell2.id])]
tally.scores = ['total']
# Instantiate a TalliesFile, register Tally/Mesh, and export to XML
tallies_file = openmc.TalliesFile()

4
examples/python/lattice/nested/build-xml.py
View file

@ -175,8 +175,8 @@ mesh_filter.mesh = mesh
# Instantiate the Tally
tally = openmc.Tally(tally_id=1)
tally.add_filter(mesh_filter)
tally.add_score('total')
tally.filters = [mesh_filter]
tally.scores = ['total']
# Instantiate a TalliesFile, register Tally/Mesh, and export to XML
tallies_file = openmc.TalliesFile()

8
examples/python/lattice/simple/build-xml.py
View file

@ -167,13 +167,13 @@ mesh_filter.mesh = mesh
# Instantiate tally Trigger
trigger = openmc.Trigger(trigger_type='rel_err', threshold=1E-2)
trigger.add_score('all')
trigger.scores = ['all']
# Instantiate the Tally
tally = openmc.Tally(tally_id=1)
tally.add_filter(mesh_filter)
tally.add_score('total')
tally.add_trigger(trigger)
tally.filters = [mesh_filter]
tally.scores = ['total']
tally.triggers = [trigger]
# Instantiate a TalliesFile, register Tally/Mesh, and export to XML
tallies_file = openmc.TalliesFile()

7
examples/python/pincell/build-xml.py
View file

@ -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()