mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 14:15:42 -04:00
Rename main Python API classes to get rid of File.
This commit is contained in:
Paul Romano
parent
cccca4062a
commit
50a80693b5
37 changed files with 203 additions and 284 deletions
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@ -35,15 +35,15 @@ iron = openmc.Material(material_id=3, name='iron')
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iron.set_density('g/cc', 7.9)
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iron.add_nuclide(fe56, 1.)
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# Instantiate a MaterialsFile, register all Materials, and export to XML
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materials_file = openmc.MaterialsFile()
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# Instantiate a Materials object, 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, iron])
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materials_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC geometry.xml File
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# Exporting to OpenMC geometry.xml file
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###############################################################################
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# Instantiate Surfaces
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@ -105,22 +105,18 @@ lattice.outer = univ2
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# Fill Cell with the Lattice
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cell1.fill = lattice
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# Instantiate a Geometry and register the root Universe
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# Instantiate a Geometry and 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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# Instantiate a GeometryFile, register Geometry, and export to XML
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geometry_file = openmc.GeometryFile()
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geometry_file.geometry = geometry
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geometry_file.export_to_xml()
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geometry.export_to_xml()
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###############################################################################
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# Exporting to OpenMC settings.xml File
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# Exporting to OpenMC settings.xml file
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###############################################################################
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# Instantiate a SettingsFile, set all runtime parameters, and export to XML
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settings_file = openmc.SettingsFile()
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settings_file = openmc.Settings()
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settings_file.batches = batches
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settings_file.inactive = inactive
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settings_file.particles = particles
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@ -137,7 +133,7 @@ settings_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC plots.xml File
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# Exporting to OpenMC plots.xml file
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###############################################################################
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plot_xy = openmc.Plot(plot_id=1)
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@ -155,8 +151,8 @@ plot_yz.width = [8, 8]
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plot_yz.pixels = [400, 400]
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plot_yz.color = 'mat'
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# Instantiate a PlotsFile, add Plot, and export to XML
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plot_file = openmc.PlotsFile()
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# Instantiate a Plots object, add plots, and export to XML
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plot_file = openmc.Plots()
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plot_file.add_plot(plot_xy)
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plot_file.add_plot(plot_yz)
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plot_file.export_to_xml()
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@ -171,7 +167,7 @@ tally = openmc.Tally(tally_id=1)
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tally.filters = [openmc.Filter(type='distribcell', bins=[cell2.id])]
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tally.scores = ['total']
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# Instantiate a TalliesFile, register Tally/Mesh, and export to XML
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tallies_file = openmc.TalliesFile()
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# Instantiate a Tallies object, register Tally/Mesh, and export to XML
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tallies_file = openmc.Tallies()
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tallies_file.add_tally(tally)
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tallies_file.export_to_xml()
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@ -11,7 +11,7 @@ particles = 10000
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###############################################################################
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# Exporting to OpenMC materials.xml File
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# Exporting to OpenMC materials.xml file
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###############################################################################
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# Instantiate some Nuclides
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@ -30,15 +30,15 @@ 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 MaterialsFile, register all Materials, and export to XML
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materials_file = openmc.MaterialsFile()
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# Instantiate a Materials object, 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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materials_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC geometry.xml File
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# Exporting to OpenMC geometry.xml file
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###############################################################################
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# Instantiate Surfaces
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@ -116,22 +116,18 @@ 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
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# Instantiate a Geometry and 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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# Instantiate a GeometryFile, register Geometry, and export to XML
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geometry_file = openmc.GeometryFile()
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geometry_file.geometry = geometry
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geometry_file.export_to_xml()
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geometry.export_to_xml()
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###############################################################################
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# Exporting to OpenMC settings.xml File
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# Exporting to OpenMC settings.xml file
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###############################################################################
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# Instantiate a SettingsFile, set all runtime parameters, and export to XML
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settings_file = openmc.SettingsFile()
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# Instantiate a Settings object, set all runtime parameters, and export to XML
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settings_file = openmc.Settings()
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settings_file.batches = batches
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settings_file.inactive = inactive
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settings_file.particles = particles
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@ -145,7 +141,7 @@ settings_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC plots.xml File
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# Exporting to OpenMC plots.xml file
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###############################################################################
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plot = openmc.Plot(plot_id=1)
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@ -154,14 +150,14 @@ plot.width = [4, 4]
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plot.pixels = [400, 400]
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plot.color = 'mat'
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# Instantiate a PlotsFile, add Plot, and export to XML
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plot_file = openmc.PlotsFile()
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# Instantiate a Plots object, add Plot, and export to XML
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plot_file = openmc.Plots()
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plot_file.add_plot(plot)
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plot_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC tallies.xml File
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# Exporting to OpenMC tallies.xml file
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###############################################################################
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# Instantiate a tally mesh
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@ -180,8 +176,8 @@ 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 TalliesFile, register Tally/Mesh, and export to XML
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tallies_file = openmc.TalliesFile()
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# Instantiate a Tallies object, 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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tallies_file.export_to_xml()
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@ -11,7 +11,7 @@ particles = 10000
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###############################################################################
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# Exporting to OpenMC materials.xml File
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# Exporting to OpenMC materials.xml file
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###############################################################################
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# Instantiate some Nuclides
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@ -30,15 +30,15 @@ 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 MaterialsFile, register all Materials, and export to XML
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materials_file = openmc.MaterialsFile()
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# Instantiate a Materials object, 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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materials_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC geometry.xml File
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# Exporting to OpenMC geometry.xml file
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###############################################################################
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# Instantiate Surfaces
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@ -106,22 +106,18 @@ lattice.universes = [[univ1, univ2, univ1, univ2],
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# Fill Cell with the Lattice
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cell1.fill = lattice
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# Instantiate a Geometry and register the root Universe
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# Instantiate a Geometry and 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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# Instantiate a GeometryFile, register Geometry, and export to XML
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geometry_file = openmc.GeometryFile()
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geometry_file.geometry = geometry
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geometry_file.export_to_xml()
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geometry.export_to_xml()
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###############################################################################
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# Exporting to OpenMC settings.xml File
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# Exporting to OpenMC settings.xml file
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###############################################################################
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# Instantiate a SettingsFile, set all runtime parameters, and export to XML
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settings_file = openmc.SettingsFile()
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# Instantiate a Settings object, set all runtime parameters, and export to XML
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settings_file = openmc.Settings()
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settings_file.batches = batches
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settings_file.inactive = inactive
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settings_file.particles = particles
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@ -137,7 +133,7 @@ settings_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC plots.xml File
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# Exporting to OpenMC plots.xml file
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###############################################################################
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plot = openmc.Plot(plot_id=1)
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@ -146,14 +142,14 @@ plot.width = [4, 4]
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plot.pixels = [400, 400]
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plot.color = 'mat'
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# Instantiate a PlotsFile, add Plot, and export to XML
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plot_file = openmc.PlotsFile()
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# Instantiate a Plots object, add Plot, and export to XML
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plot_file = openmc.Plots()
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plot_file.add_plot(plot)
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plot_file.export_to_xml()
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###############################################################################
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# Exporting to OpenMC tallies.xml File
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# Exporting to OpenMC tallies.xml file
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###############################################################################
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# Instantiate a tally mesh
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@ -177,8 +173,8 @@ tally.filters = [mesh_filter]
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tally.scores = ['total']
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tally.triggers = [trigger]
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# Instantiate a TalliesFile, register Tally/Mesh, and export to XML
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tallies_file = openmc.TalliesFile()
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# Instantiate a Tallies object, 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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tallies_file.export_to_xml()
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