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67 lines
2.2 KiB
Python
67 lines
2.2 KiB
Python
"""Test one-group cross section generation"""
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from pathlib import Path
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import numpy as np
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import pytest
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import openmc
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from openmc.deplete import MicroXS, get_microxs_and_flux
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from tests.regression_tests import config
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CHAIN_FILE = Path(__file__).parents[2] / "chain_simple.xml"
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@pytest.fixture(scope="module")
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def model():
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fuel = openmc.Material(name="uo2")
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fuel.add_element("U", 1, percent_type="ao", enrichment=4.25)
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fuel.add_element("O", 2)
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fuel.set_density("g/cc", 10.4)
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clad = openmc.Material(name="clad")
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clad.add_element("Zr", 1)
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clad.set_density("g/cc", 6)
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water = openmc.Material(name="water")
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water.add_element("O", 1)
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water.add_element("H", 2)
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water.set_density("g/cc", 1.0)
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water.add_s_alpha_beta("c_H_in_H2O")
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radii = [0.42, 0.45]
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fuel.volume = np.pi * radii[0] ** 2
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materials = openmc.Materials([fuel, clad, water])
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pin_surfaces = [openmc.ZCylinder(r=r) for r in radii]
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pin_univ = openmc.model.pin(pin_surfaces, materials)
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bound_box = openmc.model.RectangularPrism(1.24, 1.24, boundary_type="reflective")
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root_cell = openmc.Cell(fill=pin_univ, region=-bound_box)
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geometry = openmc.Geometry([root_cell])
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settings = openmc.Settings()
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settings.particles = 1000
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settings.inactive = 5
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settings.batches = 10
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return openmc.Model(geometry, materials, settings)
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@pytest.mark.parametrize("domain_type", ["materials", "mesh"])
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def test_from_model(model, domain_type):
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if domain_type == 'materials':
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domains = model.materials[:1]
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elif domain_type == 'mesh':
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mesh = openmc.RegularMesh()
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mesh.lower_left = (-0.62, -0.62)
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mesh.upper_right = (0.62, 0.62)
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mesh.dimension = (3, 3)
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domains = mesh
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nuclides = ['U234', 'U235', 'U238', 'U236', 'O16', 'O17', 'I135', 'Xe135',
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'Xe136', 'Cs135', 'Gd157', 'Gd156']
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_, test_xs = get_microxs_and_flux(model, domains, nuclides, chain_file=CHAIN_FILE)
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if config['update']:
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test_xs[0].to_csv(f'test_reference_{domain_type}.csv')
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ref_xs = MicroXS.from_csv(f'test_reference_{domain_type}.csv')
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np.testing.assert_allclose(test_xs[0].data, ref_xs.data, rtol=1e-11)
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