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104 lines
3.1 KiB
Python
104 lines
3.1 KiB
Python
import openmc
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from tests.testing_harness import TestHarness, PyAPITestHarness
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class DistribmatTestHarness(PyAPITestHarness):
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def _build_inputs(self):
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####################
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# Materials
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####################
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moderator = openmc.Material(material_id=1)
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moderator.set_density('g/cc', 1.0)
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moderator.add_nuclide('H1', 2.0)
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moderator.add_nuclide('O16', 1.0)
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dense_fuel = openmc.Material(material_id=2)
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dense_fuel.set_density('g/cc', 4.5)
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dense_fuel.add_nuclide('U235', 1.0)
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light_fuel = openmc.Material(material_id=3)
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light_fuel.set_density('g/cc', 2.0)
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light_fuel.add_nuclide('U235', 1.0)
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mats_file = openmc.Materials([moderator, dense_fuel, light_fuel])
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mats_file.export_to_xml()
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####################
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# Geometry
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####################
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c1 = openmc.Cell(cell_id=1, fill=moderator)
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mod_univ = openmc.Universe(universe_id=1, cells=[c1])
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r0 = openmc.ZCylinder(R=0.3)
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c11 = openmc.Cell(cell_id=11, region=-r0)
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c11.fill = [dense_fuel, None, light_fuel, dense_fuel]
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c12 = openmc.Cell(cell_id=12, region=+r0, fill=moderator)
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fuel_univ = openmc.Universe(universe_id=11, cells=[c11, c12])
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lat = openmc.RectLattice(lattice_id=101)
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lat.lower_left = [-2.0, -2.0]
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lat.pitch = [2.0, 2.0]
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lat.universes = [[fuel_univ]*2]*2
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lat.outer = mod_univ
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x0 = openmc.XPlane(x0=-3.0)
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x1 = openmc.XPlane(x0=3.0)
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y0 = openmc.YPlane(y0=-3.0)
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y1 = openmc.YPlane(y0=3.0)
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for s in [x0, x1, y0, y1]:
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s.boundary_type = 'reflective'
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c101 = openmc.Cell(cell_id=101, fill=lat)
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c101.region = +x0 & -x1 & +y0 & -y1
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root_univ = openmc.Universe(universe_id=0, cells=[c101])
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geometry = openmc.Geometry(root_univ)
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geometry.export_to_xml()
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####################
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# Settings
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####################
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sets_file = openmc.Settings()
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sets_file.batches = 5
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sets_file.inactive = 0
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sets_file.particles = 1000
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sets_file.source = openmc.Source(space=openmc.stats.Box(
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[-1, -1, -1], [1, 1, 1]))
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sets_file.export_to_xml()
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####################
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# Plots
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####################
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plot1 = openmc.Plot(plot_id=1)
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plot1.basis = 'xy'
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plot1.color_by = 'cell'
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plot1.filename = 'cellplot'
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plot1.origin = (0, 0, 0)
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plot1.width = (7, 7)
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plot1.pixels = (400, 400)
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plot2 = openmc.Plot(plot_id=2)
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plot2.basis = 'xy'
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plot2.color_by = 'material'
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plot2.filename = 'matplot'
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plot2.origin = (0, 0, 0)
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plot2.width = (7, 7)
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plot2.pixels = (400, 400)
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plots = openmc.Plots([plot1, plot2])
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plots.export_to_xml()
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def _get_results(self):
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outstr = super()._get_results()
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su = openmc.Summary('summary.h5')
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outstr += str(su.geometry.get_all_cells()[11])
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return outstr
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def test_distribmat():
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harness = DistribmatTestHarness('statepoint.5.h5')
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harness.main()
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