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Respond to @wbinventor comments on #632
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15 changed files with 146 additions and 138 deletions
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@ -30,7 +30,7 @@ moderator.add_nuclide(h1, 2.)
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moderator.add_nuclide(o16, 1.)
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moderator.add_s_alpha_beta('HH2O', '71t')
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# Instantiate a Materials object, register all Materials, and export to XML
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# Instantiate a Materials collection, register all Materials, and export to XML
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materials_file = openmc.Materials()
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materials_file.default_xs = '71c'
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materials_file.add_materials([moderator, fuel])
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@ -116,7 +116,7 @@ lattice2.universes = [[univ4, univ4],
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cell1.fill = lattice2
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cell2.fill = lattice1
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# Instantiate a Geometry and register the root Universe, and export to XML
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# Instantiate a Geometry, register the root Universe, and export to XML
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geometry = openmc.Geometry()
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geometry.root_universe = root
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geometry.export_to_xml()
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@ -176,7 +176,7 @@ tally = openmc.Tally(tally_id=1)
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tally.filters = [mesh_filter]
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tally.scores = ['total']
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# Instantiate a Tallies object, register Tally/Mesh, and export to XML
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# Instantiate a Tallies collection, register Tally/Mesh, and export to XML
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tallies_file = openmc.Tallies()
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tallies_file.add_mesh(mesh)
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tallies_file.add_tally(tally)
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