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Rename main Python API classes to get rid of File.

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This commit is contained in:
Paul Romano 2016-04-25 10:37:06 -05:00
parent cccca4062a
commit 50a80693b5
37 changed files with 203 additions and 284 deletions
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28
examples/python/basic/build-xml.py
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@ -12,7 +12,7 @@ particles = 10000
###############################################################################
# Exporting to OpenMC materials.xml File
# Exporting to OpenMC materials.xml file
###############################################################################
# Instantiate some Nuclides
@ -31,15 +31,15 @@ fuel = openmc.Material(material_id=40, name='fuel')
fuel.set_density('g/cc', 4.5)
fuel.add_nuclide(u235, 1.)
# Instantiate a MaterialsFile, register all Materials, and export to XML
materials_file = openmc.MaterialsFile()
# Instantiate a Materials collection, register all Materials, and export to XML
materials_file = openmc.Materials()
materials_file.default_xs = '71c'
materials_file.add_materials([moderator, fuel])
materials_file.export_to_xml()
###############################################################################
# Exporting to OpenMC geometry.xml File
# Exporting to OpenMC geometry.xml file
###############################################################################
# Instantiate ZCylinder surfaces
@ -74,22 +74,18 @@ cell1.fill = universe1
universe1.add_cells([cell2, cell3])
root.add_cells([cell1, cell4])
# Instantiate a Geometry and register the root Universe
# Instantiate a Geometry and register the root Universe, and export to XML
geometry = openmc.Geometry()
geometry.root_universe = root
# Instantiate a GeometryFile, register Geometry, and export to XML
geometry_file = openmc.GeometryFile()
geometry_file.geometry = geometry
geometry_file.export_to_xml()
geometry.export_to_xml()
###############################################################################
# Exporting to OpenMC settings.xml File
# Exporting to OpenMC settings.xml file
###############################################################################
# Instantiate a SettingsFile, set all runtime parameters, and export to XML
settings_file = openmc.SettingsFile()
# Instantiate a Settings object, set all runtime parameters, and export to XML
settings_file = openmc.Settings()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
@ -103,7 +99,7 @@ settings_file.export_to_xml()
###############################################################################
# Exporting to OpenMC tallies.xml File
# Exporting to OpenMC tallies.xml file
###############################################################################
# Instantiate some tally Filters
@ -128,8 +124,8 @@ third_tally = openmc.Tally(tally_id=3, name='third tally')
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()
# Instantiate a Tallies object, register all Tallies, and export to XML
tallies_file = openmc.Tallies()
tallies_file.add_tally(first_tally)
tallies_file.add_tally(second_tally)
tallies_file.add_tally(third_tally)