OpenMC/tests/unit_tests/test_material.py
2019-10-28 11:55:45 -05:00

220 lines
6.2 KiB
Python

import openmc
import openmc.model
import openmc.stats
import openmc.examples
import pytest
def test_attributes(uo2):
assert uo2.name == 'UO2'
assert uo2.id == 100
assert uo2.depletable
def test_nuclides(uo2):
"""Test adding/removing nuclides."""
m = openmc.Material()
m.add_nuclide('U235', 1.0)
with pytest.raises(TypeError):
m.add_nuclide('H1', '1.0')
with pytest.raises(TypeError):
m.add_nuclide(1.0, 'H1')
with pytest.raises(ValueError):
m.add_nuclide('H1', 1.0, 'oa')
m.remove_nuclide('U235')
def test_elements():
"""Test adding elements."""
m = openmc.Material()
m.add_element('Zr', 1.0)
m.add_element('U', 1.0, enrichment=4.5)
with pytest.raises(ValueError):
m.add_element('U', 1.0, enrichment=100.0)
with pytest.raises(ValueError):
m.add_element('Pu', 1.0, enrichment=3.0)
def test_density():
m = openmc.Material()
for unit in ['g/cm3', 'g/cc', 'kg/m3', 'atom/b-cm', 'atom/cm3']:
m.set_density(unit, 1.0)
with pytest.raises(ValueError):
m.set_density('g/litre', 1.0)
def test_salphabeta():
m = openmc.Material()
m.add_s_alpha_beta('c_H_in_H2O', 0.5)
def test_repr():
m = openmc.Material()
m.add_nuclide('Zr90', 1.0)
m.add_nuclide('H2', 0.5)
m.add_s_alpha_beta('c_D_in_D2O')
m.set_density('sum')
m.temperature = 600.0
repr(m)
def test_macroscopic(run_in_tmpdir):
m = openmc.Material(name='UO2')
m.add_macroscopic('UO2')
with pytest.raises(ValueError):
m.add_nuclide('H1', 1.0)
with pytest.raises(ValueError):
m.add_element('O', 1.0)
with pytest.raises(ValueError):
m.add_macroscopic('Other')
m2 = openmc.Material()
m2.add_nuclide('He4', 1.0)
with pytest.raises(ValueError):
m2.add_macroscopic('UO2')
# Make sure we can remove/add macroscopic
m.remove_macroscopic('UO2')
m.add_macroscopic('UO2')
repr(m)
# Make sure we can export a material with macroscopic data
mats = openmc.Materials([m])
mats.export_to_xml()
def test_paths():
model = openmc.examples.pwr_assembly()
model.geometry.determine_paths()
fuel = model.materials[0]
assert fuel.num_instances == 264
assert len(fuel.paths) == 264
def test_isotropic():
m1 = openmc.Material()
m1.add_nuclide('U235', 1.0)
m1.add_nuclide('O16', 2.0)
m1.isotropic = ['O16']
assert m1.isotropic == ['O16']
m2 = openmc.Material()
m2.add_nuclide('H1', 1.0)
mats = openmc.Materials([m1, m2])
mats.make_isotropic_in_lab()
assert m1.isotropic == ['U235', 'O16']
assert m2.isotropic == ['H1']
def test_get_nuclide_densities(uo2):
nucs = uo2.get_nuclide_densities()
for nuc, density, density_type in nucs.values():
assert nuc in ('U235', 'O16')
assert density > 0
assert density_type in ('ao', 'wo')
def test_get_nuclide_atom_densities(uo2):
nucs = uo2.get_nuclide_atom_densities()
for nuc, density in nucs.values():
assert nuc in ('U235', 'O16')
assert density > 0
def test_mass():
m = openmc.Material()
m.add_nuclide('Zr90', 1.0, 'wo')
m.add_nuclide('U235', 1.0, 'wo')
m.set_density('g/cm3', 2.0)
m.volume = 10.0
assert m.get_mass_density('Zr90') == pytest.approx(1.0)
assert m.get_mass_density('U235') == pytest.approx(1.0)
assert m.get_mass_density() == pytest.approx(2.0)
assert m.get_mass('Zr90') == pytest.approx(10.0)
assert m.get_mass('U235') == pytest.approx(10.0)
assert m.get_mass() == pytest.approx(20.0)
assert m.fissionable_mass == pytest.approx(10.0)
def test_materials(run_in_tmpdir):
m1 = openmc.Material()
m1.add_nuclide('U235', 1.0, 'wo')
m1.add_nuclide('O16', 2.0, 'wo')
m1.set_density('g/cm3', 10.0)
m1.depletable = True
m1.temperature = 900.0
m2 = openmc.Material()
m2.add_nuclide('H1', 2.0)
m2.add_nuclide('O16', 1.0)
m2.add_s_alpha_beta('c_H_in_H2O')
m2.set_density('kg/m3', 1000.0)
mats = openmc.Materials([m1, m2])
mats.cross_sections = '/some/fake/cross_sections.xml'
mats.export_to_xml()
def test_borated_water():
# Test against reference values from the BEAVRS benchmark.
m = openmc.model.borated_water(975, 566.5, 15.51, material_id=50)
assert m.density == pytest.approx(0.7405, 1e-3)
assert m.temperature == pytest.approx(566.5)
assert m._sab[0][0] == 'c_H_in_H2O'
ref_dens = {'B10':8.0023e-06, 'B11':3.2210e-05, 'H1':4.9458e-02,
'O16':2.4672e-02}
nuc_dens = m.get_nuclide_atom_densities()
for nuclide in ref_dens:
assert nuc_dens[nuclide][1] == pytest.approx(ref_dens[nuclide], 1e-2)
assert m.id == 50
# Test the Celsius conversion.
m = openmc.model.borated_water(975, 293.35, 15.51, 'C')
assert m.density == pytest.approx(0.7405, 1e-3)
# Test Fahrenheit and psi conversions.
m = openmc.model.borated_water(975, 560.0, 2250.0, 'F', 'psi')
assert m.density == pytest.approx(0.7405, 1e-3)
# Test the density override
m = openmc.model.borated_water(975, 566.5, 15.51, density=0.9)
assert m.density == pytest.approx(0.9, 1e-3)
def test_from_xml(run_in_tmpdir):
# Create a materials.xml file
m1 = openmc.Material(1, 'water')
m1.add_nuclide('H1', 1.0)
m1.add_nuclide('O16', 2.0)
m1.add_s_alpha_beta('c_H_in_H2O')
m1.temperature = 300
m1.volume = 100
m1.set_density('g/cm3', 0.9)
m1.isotropic = ['H1']
m2 = openmc.Material(2, 'zirc')
m2.add_nuclide('Zr90', 1.0, 'wo')
m2.set_density('kg/m3', 10.0)
m3 = openmc.Material(3)
m3.add_nuclide('N14', 0.02)
mats = openmc.Materials([m1, m2, m3])
mats.cross_sections = 'fake_path.xml'
mats.export_to_xml()
# Regenerate materials from XML
mats = openmc.Materials.from_xml()
assert len(mats) == 3
m1 = mats[0]
assert m1.id == 1
assert m1.name == 'water'
assert m1.nuclides == [('H1', 1.0, 'ao'), ('O16', 2.0, 'ao')]
assert m1.isotropic == ['H1']
assert m1.temperature == 300
assert m1.volume == 100
m2 = mats[1]
assert m2.nuclides == [('Zr90', 1.0, 'wo')]
assert m2.density == 10.0
assert m2.density_units == 'kg/m3'
assert mats[2].density_units == 'sum'