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120 lines
3.4 KiB
Python
120 lines
3.4 KiB
Python
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from math import sqrt
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import pytest
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import numpy as np
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import openmc
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import openmc.lib
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from tests import cdtemp
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@pytest.fixture(scope='module', autouse=True)
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def double_hex_lattice_model():
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openmc.reset_auto_ids()
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radius = 0.9
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pin_lattice_pitch = 2.0
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# make the hex prism a little larger to make sure test
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# locations are definitively in the model
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hex_prism_edge = 1.2 * pin_lattice_pitch
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model = openmc.Model()
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# materials
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nat_u = openmc.Material()
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nat_u.set_density('g/cm3', 12.0)
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nat_u.add_element('U', 1.0)
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graphite = openmc.Material()
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graphite.set_density('g/cm3', 1.1995)
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graphite.add_element('C', 1.0)
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# zplanes to define lower and upper region
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z_low = openmc.ZPlane(-10, boundary_type='vacuum')
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z_mid = openmc.ZPlane(0)
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z_high = openmc.ZPlane(10, boundary_type='vacuum')
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hex_prism = openmc.model.HexagonalPrism(
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edge_length=hex_prism_edge, boundary_type='reflective')
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# geometry
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cyl = openmc.ZCylinder(r=radius)
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univ = openmc.model.pin([cyl], [nat_u, graphite])
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# create a hexagonal lattice of compacts
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hex_lattice = openmc.HexLattice()
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hex_lattice.orientation = 'y'
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hex_lattice.pitch = (pin_lattice_pitch,)
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hex_lattice.center = (0., 0.)
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center = [univ]
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ring = [univ, univ, univ, univ, univ, univ]
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hex_lattice.universes = [ring, center]
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lower_hex_cell = openmc.Cell(fill=hex_lattice, region=-hex_prism & +z_low & -z_mid)
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upper_hex_cell = openmc.Cell(fill=hex_lattice, region=-hex_prism & +z_mid & -z_high)
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hex_cells = [lower_hex_cell, upper_hex_cell]
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model.geometry = openmc.Geometry(hex_cells)
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# moderator
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cell = next(iter(univ.get_all_cells().values()))
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tally = openmc.Tally(tally_id=1)
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filter = openmc.DistribcellFilter(cell)
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tally.filters = [filter]
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tally.scores = ['flux']
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model.tallies = [tally]
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# settings
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# source definition. fission source given bounding box of graphite active region
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system_LL = (-pin_lattice_pitch*sqrt(3)/2, -pin_lattice_pitch, -5)
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system_UR = (pin_lattice_pitch*sqrt(3)/2, pin_lattice_pitch, 5)
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source_dist = openmc.stats.Box(system_LL, system_UR)
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model.settings.source = openmc.IndependentSource(space=source_dist)
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model.settings.particles = 100
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model.settings.inactive = 2
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model.settings.batches = 10
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with cdtemp():
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model.export_to_xml()
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openmc.lib.init()
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yield
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openmc.lib.finalize()
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# Lower cell instances
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# 6
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# 5 4
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# 3
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# 2 1
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# 0
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# Upper cell instances
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# 13
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# 12 11
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# 10
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# 9 8
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# 7
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hex_expected_results = [
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((0.0, -2.0, -5.0), 0),
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((1.732, -1.0, -5.0), 1),
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((-1.732, -1.0, -5.0), 2),
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((0.0, 0.0, -0.1), 3),
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((1.732, 1.0, -5.0), 4),
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((-1.732, 1.0, -5.0), 5),
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((0.0, 2.0, -0.1), 6),
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((0.0, -2.0, 5.0), 7),
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((1.732, -1.0, 5.0), 8),
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((-1.732, -1.0, 5.0), 9),
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((0.0, 0.0, 5.0), 10),
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((1.732, 1.0, 5.0), 11),
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((-1.732, 1.0, 5.0), 12),
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((0.0, 2.0, 5.0), 13),
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]
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@pytest.mark.parametrize("r,expected_cell_instance", hex_expected_results, ids=str)
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def test_cell_instance_hex_multilattice(r, expected_cell_instance):
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_, cell_instance = openmc.lib.find_cell(r)
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assert cell_instance == expected_cell_instance
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def test_cell_instance_multilattice_results():
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openmc.lib.run()
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tally_results = openmc.lib.tallies[1].mean
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assert (tally_results != 0.0).all()
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