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Updated sample input scripts for Python API to conform to new API specs
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8 changed files with 291 additions and 330 deletions
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@ -20,14 +20,14 @@ u235 = openmc.Nuclide('U-235')
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# Instantiate a Material and register the Nuclide
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fuel = openmc.Material(material_id=1, name='fuel')
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fuel.setDensity('g/cc', 4.5)
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fuel.addNuclide(u235, 1.)
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fuel.set_density('g/cc', 4.5)
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fuel.add_nuclide(u235, 1.)
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# Instantiate a MaterialsFile, register Material, and export to XML
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materials_file = openmc.MaterialsFile()
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materials_file.setDefaultXS('71c')
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materials_file.addMaterial(fuel)
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materials_file.exportToXML()
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materials_file.set_default_xs('71c')
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materials_file.add_material(fuel)
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materials_file.export_to_xml()
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###############################################################################
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@ -42,41 +42,41 @@ surf4 = openmc.YPlane(surface_id=4, y0=+1, name='surf 4')
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surf5 = openmc.ZPlane(surface_id=5, z0=-1, name='surf 5')
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surf6 = openmc.ZPlane(surface_id=6, z0=+1, name='surf 6')
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surf1.setBoundaryType('vacuum')
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surf2.setBoundaryType('vacuum')
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surf3.setBoundaryType('reflective')
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surf4.setBoundaryType('reflective')
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surf5.setBoundaryType('reflective')
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surf6.setBoundaryType('reflective')
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surf1.set_boundary_type('vacuum')
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surf2.set_boundary_type('vacuum')
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surf3.set_boundary_type('reflective')
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surf4.set_boundary_type('reflective')
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surf5.set_boundary_type('reflective')
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surf6.set_boundary_type('reflective')
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# Instantiate Cell
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cell = openmc.Cell(cell_id=1, name='cell 1')
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# Register Surfaces with Cell
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cell.addSurface(surface=surf1, halfspace=+1)
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cell.addSurface(surface=surf2, halfspace=-1)
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cell.addSurface(surface=surf3, halfspace=+1)
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cell.addSurface(surface=surf4, halfspace=-1)
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cell.addSurface(surface=surf5, halfspace=+1)
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cell.addSurface(surface=surf6, halfspace=-1)
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cell.add_surface(surface=surf1, halfspace=+1)
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cell.add_surface(surface=surf2, halfspace=-1)
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cell.add_surface(surface=surf3, halfspace=+1)
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cell.add_surface(surface=surf4, halfspace=-1)
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cell.add_surface(surface=surf5, halfspace=+1)
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cell.add_surface(surface=surf6, halfspace=-1)
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# Register Material with Cell
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cell.setFill(fuel)
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cell.set_fill(fuel)
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# Instantiate Universes
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root = openmc.Universe(universe_id=0, name='root universe')
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# Register Cell with Universe
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root.addCell(cell)
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root.add_cell(cell)
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# Instantiate a Geometry and register the root Universe
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geometry = openmc.Geometry()
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geometry.setRootUniverse(root)
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geometry.set_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.setGeometry(geometry)
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geometry_file.exportToXML()
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geometry_file.set_geometry(geometry)
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geometry_file.export_to_xml()
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###############################################################################
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@ -85,8 +85,8 @@ geometry_file.exportToXML()
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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.setBatches(batches)
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settings_file.setInactive(inactive)
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settings_file.setParticles(particles)
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settings_file.setSourceSpace('box', [-1, -1, -1, 1, 1, 1])
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settings_file.exportToXML()
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settings_file.set_batches(batches)
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settings_file.set_inactive(inactive)
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settings_file.set_particles(particles)
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settings_file.set_source_space('box', [-1, -1, -1, 1, 1, 1])
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settings_file.export_to_xml()
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@ -1,17 +0,0 @@
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<?xml version='1.0' encoding='utf-8'?>
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<geometry>
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<!--cell 1-->
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<cell id="1" material="1" surfaces="1 -2 3 -4 5 -6" universe="0" />
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<!--surf 1-->
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<surface boundary="vacuum" coeffs="-1" id="1" type="x-plane" />
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<!--surf 2-->
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<surface boundary="vacuum" coeffs="1" id="2" type="x-plane" />
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<!--surf 3-->
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<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
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<!--surf 4-->
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<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
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<!--surf 5-->
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<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
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<!--surf 6-->
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<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
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</geometry>
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@ -1,9 +0,0 @@
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<?xml version='1.0' encoding='utf-8'?>
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<materials>
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<default_xs>71c</default_xs>
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<!--fuel-->
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<material id="1">
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<density units="g/cc" value="4.5" />
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<nuclide ao="1.0" name="U-235" />
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</material>
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</materials>
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@ -1,13 +0,0 @@
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<?xml version='1.0' encoding='utf-8'?>
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<settings>
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<eigenvalue>
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<particles>10000</particles>
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<batches>500</batches>
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<inactive>10</inactive>
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</eigenvalue>
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<source>
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<space type="box">
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<parameters>-1 -1 -1 1 1 1</parameters>
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</space>
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</source>
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</settings>
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