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feefcc6713
Co-authored-by: Jon Shimwell <jon@proximafusion.com> Co-authored-by: GuySten <62616591+GuySten@users.noreply.github.com>
65 lines
1.8 KiB
Python
65 lines
1.8 KiB
Python
import openmc
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def test_get_tally_filter_type(run_in_tmpdir):
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"""Test various ways of retrieving tallies from a StatePoint object."""
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mat = openmc.Material()
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mat.add_nuclide("H1", 1.0)
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mat.set_density("g/cm3", 10.0)
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sphere = openmc.Sphere(r=10.0, boundary_type="vacuum")
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cell = openmc.Cell(fill=mat, region=-sphere)
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geometry = openmc.Geometry([cell])
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settings = openmc.Settings()
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settings.particles = 10
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settings.batches = 2
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settings.run_mode = "fixed source"
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reg_mesh = openmc.RegularMesh().from_domain(cell)
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tally1 = openmc.Tally(tally_id=1)
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mesh_filter = openmc.MeshFilter(reg_mesh)
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tally1.filters = [mesh_filter]
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tally1.scores = ["flux"]
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tally2 = openmc.Tally(tally_id=2, name="heating tally")
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cell_filter = openmc.CellFilter(cell)
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tally2.filters = [cell_filter]
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tally2.scores = ["heating"]
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tallies = openmc.Tallies([tally1, tally2])
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model = openmc.Model(
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geometry=geometry, materials=[mat], settings=settings, tallies=tallies
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)
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sp_filename = model.run()
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sp = openmc.StatePoint(sp_filename)
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tally_found = sp.get_tally(filter_type=openmc.MeshFilter)
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assert tally_found.id == 1
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tally_found = sp.get_tally(filter_type=openmc.CellFilter)
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assert tally_found.id == 2
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tally_found = sp.get_tally(filters=[mesh_filter])
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assert tally_found.id == 1
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tally_found = sp.get_tally(filters=[cell_filter])
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assert tally_found.id == 2
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tally_found = sp.get_tally(scores=["heating"])
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assert tally_found.id == 2
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tally_found = sp.get_tally(name="heating tally")
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assert tally_found.id == 2
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tally_found = sp.get_tally(name=None)
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assert tally_found.id == 1
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tally_found = sp.get_tally(id=1)
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assert tally_found.id == 1
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tally_found = sp.get_tally(id=2)
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assert tally_found.id == 2
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