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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/pincell/build-xml.py
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@ -11,7 +11,7 @@ particles = 1000
###############################################################################
# Exporting to OpenMC materials.xml File
# Exporting to OpenMC materials.xml file
###############################################################################
# Instantiate some Nuclides
@ -100,15 +100,15 @@ borated_water.add_nuclide(o16, 2.4672e-2)
borated_water.add_nuclide(o17, 6.0099e-5)
borated_water.add_s_alpha_beta('HH2O', '71t')
# Instantiate a MaterialsFile, register all Materials, and export to XML
materials_file = openmc.MaterialsFile()
# Instantiate a Materials object, register all Materials, and export to XML
materials_file = openmc.Materials()
materials_file.default_xs = '71c'
materials_file.add_materials([uo2, helium, zircaloy, borated_water])
materials_file.export_to_xml()
###############################################################################
# Exporting to OpenMC geometry.xml File
# Exporting to OpenMC geometry.xml file
###############################################################################
# Instantiate ZCylinder surfaces
@ -149,22 +149,18 @@ root = openmc.Universe(universe_id=0, name='root universe')
# Register Cells with Universe
root.add_cells([fuel, gap, clad, water])
# 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
@ -181,7 +177,7 @@ settings_file.export_to_xml()
###############################################################################
# Exporting to OpenMC tallies.xml File
# Exporting to OpenMC tallies.xml file
###############################################################################
# Instantiate a tally mesh
@ -201,8 +197,8 @@ tally = openmc.Tally(tally_id=1, name='tally 1')
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()
# Instantiate a Tallies object, register all Tallies, and export to XML
tallies_file = openmc.Tallies()
tallies_file.add_mesh(mesh)
tallies_file.add_tally(tally)
tallies_file.export_to_xml()