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Implemented lattice/nested example input file using Python API
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Will Boyd
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commit
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6 changed files with 189 additions and 108 deletions
189
examples/python/lattice/nested/build-xml.py
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examples/python/lattice/nested/build-xml.py
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import openmc
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###############################################################################
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# Simulation Input File Parameters
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###############################################################################
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# OpenMC simulation parameters
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batches = 20
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inactive = 10
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particles = 10000
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###############################################################################
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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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h1 = openmc.Nuclide('H-1')
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o16 = openmc.Nuclide('O-16')
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u235 = openmc.Nuclide('U-235')
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# Instantiate some Materials and register the appropriate Nuclides
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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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moderator = openmc.Material(material_id=2, name='moderator')
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moderator.setDensity('g/cc', 1.0)
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moderator.addNuclide(h1, 2.)
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moderator.addNuclide(o16, 1.)
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moderator.addSAlphaBeta('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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materials_file.setDefaultXS('71c')
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materials_file.addMaterials([moderator, fuel])
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materials_file.exportToXML()
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###############################################################################
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# Exporting to OpenMC geometry.xml File
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###############################################################################
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# Instantiate Surfaces
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left = openmc.XPlane(surface_id=1, x0=-2, name='left')
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right = openmc.XPlane(surface_id=2, x0=2, name='right')
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bottom = openmc.YPlane(surface_id=3, y0=-2, name='bottom')
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top = openmc.YPlane(surface_id=4, y0=2, name='top')
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fuel1 = openmc.ZCylinder(surface_id=5, x0=0, y0=0, R=0.4)
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fuel2 = openmc.ZCylinder(surface_id=6, x0=0, y0=0, R=0.3)
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fuel3 = openmc.ZCylinder(surface_id=7, x0=0, y0=0, R=0.2)
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left.setBoundaryType('vacuum')
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right.setBoundaryType('vacuum')
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top.setBoundaryType('vacuum')
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bottom.setBoundaryType('vacuum')
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# Instantiate Cells
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cell1 = openmc.Cell(cell_id=1, name='Cell 1')
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cell2 = openmc.Cell(cell_id=2, name='Cell 2')
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cell3 = openmc.Cell(cell_id=101, name='cell 3')
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cell4 = openmc.Cell(cell_id=102, name='cell 4')
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cell5 = openmc.Cell(cell_id=201, name='cell 5')
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cell6 = openmc.Cell(cell_id=202, name='cell 6')
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cell7 = openmc.Cell(cell_id=301, name='cell 7')
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cell8 = openmc.Cell(cell_id=302, name='cell 8')
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# Register Surfaces with Cells
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cell1.addSurface(left, halfspace=+1)
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cell1.addSurface(right, halfspace=-1)
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cell1.addSurface(bottom, halfspace=+1)
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cell1.addSurface(top, halfspace=-1)
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cell2.addSurface(left, halfspace=+1)
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cell2.addSurface(right, halfspace=-1)
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cell2.addSurface(bottom, halfspace=+1)
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cell2.addSurface(top, halfspace=-1)
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cell3.addSurface(fuel1, halfspace=-1)
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cell4.addSurface(fuel1, halfspace=+1)
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cell5.addSurface(fuel2, halfspace=-1)
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cell6.addSurface(fuel2, halfspace=+1)
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cell7.addSurface(fuel3, halfspace=-1)
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cell8.addSurface(fuel3, halfspace=+1)
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# Register Materials with Cells
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cell3.setFill(fuel)
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cell4.setFill(moderator)
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cell5.setFill(fuel)
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cell6.setFill(moderator)
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cell7.setFill(fuel)
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cell8.setFill(moderator)
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# Instantiate Universe
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univ1 = openmc.Universe(universe_id=1)
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univ2 = openmc.Universe(universe_id=2)
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univ3 = openmc.Universe(universe_id=3)
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univ4 = openmc.Universe(universe_id=5)
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root = openmc.Universe(universe_id=0, name='root universe')
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# Register Cells with Universe
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univ1.addCells([cell3, cell4])
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univ2.addCells([cell5, cell6])
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univ3.addCells([cell7, cell8])
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root.addCell(cell1)
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univ4.addCell(cell2)
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# Instantiate nested Lattices
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lattice1 = openmc.Lattice(lattice_id=4, name='4x4 assembly')
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lattice1.setDimension([2, 2])
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lattice1.setLowerLeft([-1., -1.])
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lattice1.setWidth([1., 1.])
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lattice1.setUniverses([[univ1, univ2],
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[univ2, univ3]])
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lattice2 = openmc.Lattice(lattice_id=6, name='4x4 core')
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lattice2.setDimension([2, 2])
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lattice2.setLowerLeft([-2., -2.])
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lattice2.setWidth([2., 2.])
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lattice2.setUniverses([[univ4, univ4],
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[univ4, univ4]])
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# Fill Cell with the Lattice
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cell1.setFill(lattice2)
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cell2.setFill(lattice1)
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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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# 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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###############################################################################
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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.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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###############################################################################
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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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plot.setOrigin([0, 0, 0])
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plot.setWidth([4, 4])
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plot.setPixels([400, 400])
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plot.setColor('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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plot_file.addPlot(plot)
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plot_file.exportToXML()
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###############################################################################
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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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mesh = openmc.Mesh(mesh_id=1)
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mesh.setType('rectangular')
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mesh.setDimension([4, 4])
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mesh.setLowerLeft([-2, -2])
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mesh.setWidth([1, 1])
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# Instantiate tally Filter
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mesh_filter = openmc.Filter()
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mesh_filter.setMesh(mesh)
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# Instantiate the Tally
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tally = openmc.Tally(tally_id=1)
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tally.addFilter(mesh_filter)
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tally.addScore('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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tallies_file.addMesh(mesh)
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tallies_file.addTally(tally)
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tallies_file.exportToXML()
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