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Respond to @wbinventor comments on #632

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This commit is contained in:
Paul Romano 2016-04-26 07:08:03 -05:00
parent 6234c4e05e
commit 1e57cb8407
15 changed files with 146 additions and 138 deletions
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6
examples/python/pincell_multigroup/build-xml.py
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@ -81,7 +81,7 @@ water = openmc.Material(material_id=2, name='Water')
water.set_density('macro', 1.0)
water.add_macroscopic(h2o_data)
# Instantiate a Materials object, register all Materials, and export to XML
# Instantiate a Materials collection, register all Materials, and export to XML
materials_file = openmc.Materials()
materials_file.default_xs = '300K'
materials_file.add_materials([uo2, water])
@ -122,7 +122,7 @@ root = openmc.Universe(universe_id=0, name='root universe')
# Register Cells with Universe
root.add_cells([fuel, moderator])
# Instantiate a Geometry and register the root Universe, and export to XML
# Instantiate a Geometry, register the root Universe, and export to XML
geometry = openmc.Geometry()
geometry.root_universe = root
geometry.export_to_xml()
@ -173,7 +173,7 @@ tally.add_score('flux')
tally.add_score('fission')
tally.add_score('nu-fission')
# Instantiate a Tallies object, register all Tallies, and export to XML
# Instantiate a Tallies collection, register all Tallies, and export to XML
tallies_file = openmc.Tallies()
tallies_file.add_mesh(mesh)
tallies_file.add_tally(tally)