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Add 'boxes' example input files

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Paul Romano 2015-10-04 11:10:38 +07:00
parent 3ca7279bd8
commit a611b69500
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examples/python/boxes/build-xml.py Normal file
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import openmc
###############################################################################
# Simulation Input File Parameters
###############################################################################
# OpenMC simulation parameters
batches = 15
inactive = 5
particles = 10000
###############################################################################
# Exporting to OpenMC materials.xml File
###############################################################################
# Instantiate some Nuclides
h1 = openmc.Nuclide('H-1')
o16 = openmc.Nuclide('O-16')
u235 = openmc.Nuclide('U-235')
u238 = openmc.Nuclide('U-238')
# Instantiate some Materials and register the appropriate Nuclides
fuel1 = openmc.Material(material_id=1, name='fuel')
fuel1.set_density('g/cc', 4.5)
fuel1.add_nuclide(u235, 1.)
fuel2 = openmc.Material(material_id=2, name='depleted fuel')
fuel2.set_density('g/cc', 4.5)
fuel2.add_nuclide(u238, 1.)
moderator = openmc.Material(material_id=3, name='moderator')
moderator.set_density('g/cc', 1.0)
moderator.add_nuclide(h1, 2.)
moderator.add_nuclide(o16, 1.)
moderator.add_s_alpha_beta('HH2O', '71t')
# Instantiate a MaterialsFile, register all Materials, and export to XML
materials_file = openmc.MaterialsFile()
materials_file.default_xs = '71c'
materials_file.add_materials([fuel1, fuel2, moderator])
materials_file.export_to_xml()
###############################################################################
# Exporting to OpenMC geometry.xml File
###############################################################################
# Instantiate planar surfaces
x1 = openmc.XPlane(surface_id=1, x0=-10)
x2 = openmc.XPlane(surface_id=2, x0=-7)
x3 = openmc.XPlane(surface_id=3, x0=-4)
x4 = openmc.XPlane(surface_id=4, x0=4)
x5 = openmc.XPlane(surface_id=5, x0=7)
x6 = openmc.XPlane(surface_id=6, x0=10)
y1 = openmc.YPlane(surface_id=11, y0=-10)
y2 = openmc.YPlane(surface_id=12, y0=-7)
y3 = openmc.YPlane(surface_id=13, y0=-4)
y4 = openmc.YPlane(surface_id=14, y0=4)
y5 = openmc.YPlane(surface_id=15, y0=7)
y6 = openmc.YPlane(surface_id=16, y0=10)
z1 = openmc.ZPlane(surface_id=21, z0=-10)
z2 = openmc.ZPlane(surface_id=22, z0=-7)
z3 = openmc.ZPlane(surface_id=23, z0=-4)
z4 = openmc.ZPlane(surface_id=24, z0=4)
z5 = openmc.ZPlane(surface_id=25, z0=7)
z6 = openmc.ZPlane(surface_id=26, z0=10)
# Set vacuum boundary conditions on outside
for surface in [x1, x6, y1, y6, z1, z6]:
surface.boundary_type = 'vacuum'
# Instantiate Cells
inner_box = openmc.Cell(cell_id=1, name='inner box')
middle_box = openmc.Cell(cell_id=2, name='middle box')
outer_box = openmc.Cell(cell_id=3, name='outer box')
# Use each set of six planes to create solid cube regions. We can then use these
# to create cubic shells.
inner_cube = +x3 & -x4 & +y3 & -y4 & +z3 & -z4
middle_cube = +x2 & -x5 & +y2 & -y5 & +z2 & -z5
outer_cube = +x1 & -x6 & +y1 & -y6 & +z1 & -z6
# Use surface half-spaces to define regions
inner_box.region = inner_cube
middle_box.region = middle_cube & ~inner_cube
outer_box.region = outer_cube & ~middle_cube
# Register Materials with Cells
inner_box.fill = fuel1
middle_box.fill = fuel2
outer_box.fill = moderator
# Instantiate root universe
root = openmc.Universe(universe_id=0, name='root universe')
root.add_cells([inner_box, middle_box, outer_box])
# Instantiate a Geometry and register the root Universe
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()
###############################################################################
# Exporting to OpenMC settings.xml File
###############################################################################
# Instantiate a SettingsFile, set all runtime parameters, and export to XML
settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.set_source_space('point', [0., 0., 0.])
settings_file.export_to_xml()