forked from crp/openmc-designs
130 lines
No EOL
3.3 KiB
Python
130 lines
No EOL
3.3 KiB
Python
#!/usr/bin/env python3
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import openmc
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## Monte Carlo Performance Benchmark, version 1.2, July 2011
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fuel = openmc.Material(name="Fuel", material_id=1)
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fuel.set_density('g/cm3', 10.062)
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fuel.add_nuclide("U234", 4.9476e-6)
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fuel.add_nuclide("U235", 4.8218e-4)
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fuel.add_nuclide("U236", 9.0402e-5)
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fuel.add_nuclide("U238", 2.1504e-2)
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fuel.add_nuclide("Np237", 7.3733e-6)
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fuel.add_nuclide("Pu238", 1.5148e-6)
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fuel.add_nuclide("Pu239", 1.3955e-4)
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fuel.add_nuclide("Pu240", 3.4405e-5)
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fuel.add_nuclide("Pu241", 2.1439e-5)
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fuel.add_nuclide("Pu242", 3.7422e-6)
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fuel.add_nuclide("Am241", 4.5041e-7)
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fuel.add_nuclide("Am242_m1", 9.2301e-9)
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fuel.add_nuclide("Am243", 4.7878e-7)
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fuel.add_nuclide("Cm242", 1.0485e-7)
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fuel.add_nuclide("Cm243", 1.4268e-9)
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fuel.add_nuclide("Cm244", 8.8756e-8)
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fuel.add_nuclide("Cm245", 3.5285e-9)
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fuel.add_nuclide("Mo95", 2.6497e-5)
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fuel.add_nuclide("Tc99", 3.2772e-5)
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fuel.add_nuclide("Ru101", 3.0742e-5)
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fuel.add_nuclide("Ru103", 2.3505e-6)
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fuel.add_nuclide("Ag109", 2.0009e-6)
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fuel.add_nuclide("Xe135", 1.0801e-8)
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fuel.add_nuclide("Cs133", 3.4612e-5)
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fuel.add_nuclide("Nd143", 2.6078e-5)
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fuel.add_nuclide("Nd145", 1.9898e-5)
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fuel.add_nuclide("Sm147", 1.6128e-6)
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fuel.add_nuclide("Sm149", 1.1627e-7)
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fuel.add_nuclide("Sm150", 7.1727e-6)
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fuel.add_nuclide("Sm151", 5.4947e-7)
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fuel.add_nuclide("Sm152", 3.0221e-6)
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fuel.add_nuclide("Eu153", 2.6209e-6)
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fuel.add_nuclide("Gd155", 1.5369e-9)
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fuel.add_nuclide("O16", 4.5737e-2)
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clad = openmc.Material(name='Cladding', material_id=2)
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clad.set_density('g/cm3', 5.77)
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clad.add_element("Zr", 1.0)
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cold_water = openmc.Material(name='Cold borated water', material_id=3)
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cold_water.set_density("atom/b-cm", 0.07416)
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cold_water.add_nuclide("H1", 2.0)
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cold_water.add_nuclide("O16", 1.0)
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cold_water.add_nuclide("B10", 6.490e-4)
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cold_water.add_nuclide("B11", 2.689e-3)
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cold_water.add_s_alpha_beta('c_H_in_H2O')
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hot_water = openmc.Material(name='Hot borated water', material_id=4)
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hot_water.set_density("atom/b-cm", 0.06614)
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hot_water.add_nuclide("H1", 2.0)
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hot_water.add_nuclide("O16", 1.0)
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hot_water.add_nuclide("B10", 6.490e-4)
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hot_water.add_nuclide("B11", 2.689e-3)
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hot_water.add_s_alpha_beta('c_H_in_H2O')
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rpv_steel = openmc.Material(name='Reactor pressure vessel steel',
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material_id=5)
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rpv_steel.set_density("g/cm3", 7.9)
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lower_rad_ref = openmc.Material(name='Lower radial reflector',
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material_id=6)
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lower_rad_ref.set_density("g/cm3", 4.32)
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upper_rad_ref = openmc.Material(name='Upper radial reflector /'
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'Top plate region', material_id=7)
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upper_rad_ref.set_density("g/cm3", 4.28)
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bot_plate = openmc.Material(name='Bottom plate region', material_id=8)
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bot_plate.set_density("g/cm3", 7.184)
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bot_nozzle = openmc.Material(name='Bottom nozzle region', material_id=9)
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bot_nozzle.set_density("g/cm3", 2.53)
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top_nozzle = openmc.Material(name='Top nozzle region', material_id=10)
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top_nozzle.set_density("g/cm3", 1.746)
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top_fa = openmc.Material(name='Top of fuel assemblies', material_id=11)
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top_fa.set_density("g/cm3", 3.044)
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bot_fa = openmc.Material(name='Bottom of fuel assemblies', material_id=12)
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bot_fa.set_density("g/cm3", 1.762)
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# Define the materials file.
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materials = openmc.Materials()
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materials.default_xs = '71c'
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materials += [fuel, , , , , , , , , , , , bot_fa]
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materials.export_to_xml()
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# Define surfaces. |