mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-21 14:35:27 -04:00
a17fe6cc82
* add decay heat in material.py * add decay_energy.json into eggs * fix a bug when returned decay_ery is None * add unit test for decayheat * fix typo in doc string * address reviewer's comments * add user defined decay energy * remove json for decay energy * address a few comments * add to docs
627 lines
22 KiB
Python
627 lines
22 KiB
Python
from collections import defaultdict
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from pathlib import Path
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import pytest
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import openmc
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from openmc.data import decay_photon_energy
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import openmc.examples
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import openmc.model
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import openmc.stats
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def test_attributes(uo2):
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assert uo2.name == 'UO2'
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assert uo2.id == 100
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assert uo2.depletable
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def test_add_nuclide():
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"""Test adding nuclides."""
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m = openmc.Material()
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m.add_nuclide('U235', 1.0)
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with pytest.raises(TypeError):
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m.add_nuclide('H1', '1.0')
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with pytest.raises(TypeError):
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m.add_nuclide(1.0, 'H1')
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with pytest.raises(ValueError):
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m.add_nuclide('H1', 1.0, 'oa')
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def test_add_components():
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"""Test adding multipe elements or nuclides at once"""
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m = openmc.Material()
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components = {'H1': 2.0,
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'O16': 1.0,
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'Zr': 1.0,
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'O': 1.0,
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'Ag110_m1': 1.0,
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'U': {'percent': 1.0,
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'enrichment': 4.5},
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'Li': {'percent': 1.0,
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'enrichment': 60.0,
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'enrichment_target': 'Li7'},
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'H': {'percent': 1.0,
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'enrichment': 50.0,
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'enrichment_target': 'H2',
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'enrichment_type': 'wo'}}
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m.add_components(components)
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with pytest.raises(ValueError):
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m.add_components({'U': {'percent': 1.0,
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'enrichment': 100.0}})
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with pytest.raises(ValueError):
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m.add_components({'Pu': {'percent': 1.0,
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'enrichment': 3.0}})
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with pytest.raises(ValueError):
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m.add_components({'U': {'percent': 1.0,
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'enrichment': 70.0,
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'enrichment_target':'U235'}})
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with pytest.raises(ValueError):
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m.add_components({'He': {'percent': 1.0,
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'enrichment': 17.0,
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'enrichment_target': 'He6'}})
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with pytest.raises(ValueError):
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m.add_components({'li': 1.0}) # should fail as 1st char is lowercase
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with pytest.raises(ValueError):
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m.add_components({'LI': 1.0}) # should fail as 2nd char is uppercase
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with pytest.raises(ValueError):
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m.add_components({'Xx': 1.0}) # should fail as Xx is not an element
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with pytest.raises(ValueError):
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m.add_components({'n': 1.0}) # check to avoid n for neutron being accepted
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with pytest.raises(TypeError):
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m.add_components({'H1': '1.0'})
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with pytest.raises(TypeError):
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m.add_components({1.0: 'H1'}, percent_type = 'wo')
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with pytest.raises(ValueError):
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m.add_components({'H1': 1.0}, percent_type = 'oa')
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def test_remove_nuclide():
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"""Test removing nuclides."""
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m = openmc.Material()
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for nuc, percent in [('H1', 1.0), ('H2', 1.0), ('H1', 2.0), ('H2', 2.0)]:
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m.add_nuclide(nuc, percent)
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m.remove_nuclide('H1')
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assert len(m.nuclides) == 2
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assert all(nuc.name == 'H2' for nuc in m.nuclides)
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assert m.nuclides[0].percent == 1.0
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assert m.nuclides[1].percent == 2.0
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def test_remove_elements():
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"""Test removing elements."""
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m = openmc.Material()
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for elem, percent in [('Li', 1.0), ('Be', 1.0)]:
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m.add_element(elem, percent)
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m.remove_element('Li')
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assert len(m.nuclides) == 1
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assert m.nuclides[0].name == 'Be9'
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assert m.nuclides[0].percent == 1.0
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def test_add_element():
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"""Test adding elements."""
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m = openmc.Material()
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m.add_element('Zr', 1.0)
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m.add_element('U', 1.0, enrichment=4.5)
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m.add_element('Li', 1.0, enrichment=60.0, enrichment_target='Li7')
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m.add_element('H', 1.0, enrichment=50.0, enrichment_target='H2',
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enrichment_type='wo')
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with pytest.raises(ValueError):
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m.add_element('U', 1.0, enrichment=100.0)
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with pytest.raises(ValueError):
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m.add_element('Pu', 1.0, enrichment=3.0)
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with pytest.raises(ValueError):
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m.add_element('U', 1.0, enrichment=70.0, enrichment_target='U235')
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with pytest.raises(ValueError):
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m.add_element('He', 1.0, enrichment=17.0, enrichment_target='He6')
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with pytest.raises(ValueError):
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m.add_element('li', 1.0) # should fail as 1st char is lowercase
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with pytest.raises(ValueError):
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m.add_element('LI', 1.0) # should fail as 2nd char is uppercase
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with pytest.raises(ValueError):
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m.add_element('Xx', 1.0) # should fail as Xx is not an element
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with pytest.raises(ValueError):
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m.add_element('n', 1.0) # check to avoid n for neutron being accepted
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def test_elements_by_name():
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"""Test adding elements by name"""
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m = openmc.Material()
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m.add_element('woLfrAm', 1.0)
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with pytest.raises(ValueError):
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m.add_element('uranum', 1.0)
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m.add_element('uRaNiUm', 1.0)
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m.add_element('Aluminium', 1.0)
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a = openmc.Material()
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b = openmc.Material()
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c = openmc.Material()
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a.add_element('sulfur', 1.0)
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b.add_element('SulPhUR', 1.0)
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c.add_element('S', 1.0)
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assert a._nuclides == b._nuclides
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assert b._nuclides == c._nuclides
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def test_add_elements_by_formula():
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"""Test adding elements from a formula"""
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# testing the correct nuclides and elements are added to a material
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m = openmc.Material()
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m.add_elements_from_formula('Li4SiO4')
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# checking the ratio of elements is 4:1:4 for Li:Si:O
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elem = defaultdict(float)
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for nuclide, adens in m.get_nuclide_atom_densities().items():
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if nuclide.startswith("Li"):
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elem["Li"] += adens
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if nuclide.startswith("Si"):
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elem["Si"] += adens
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if nuclide.startswith("O"):
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elem["O"] += adens
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total_number_of_atoms = 9
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assert elem["Li"] == pytest.approx(4./total_number_of_atoms)
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assert elem["Si"] == pytest.approx(1./total_number_of_atoms)
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assert elem["O"] == pytest.approx(4/total_number_of_atoms)
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# testing the correct nuclides are added to the Material
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ref_dens = {'Li6': 0.033728, 'Li7': 0.410715,
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'Si28': 0.102477, 'Si29': 0.0052035, 'Si30': 0.0034301,
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'O16': 0.443386, 'O17': 0.000168}
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nuc_dens = m.get_nuclide_atom_densities()
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for nuclide in ref_dens:
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assert nuc_dens[nuclide] == pytest.approx(ref_dens[nuclide], 1e-2)
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# testing the correct nuclides are added to the Material when enriched
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m = openmc.Material()
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m.add_elements_from_formula('Li4SiO4',
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enrichment=60.,
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enrichment_target='Li6')
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ref_dens = {'Li6': 0.2666, 'Li7': 0.1777,
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'Si28': 0.102477, 'Si29': 0.0052035, 'Si30': 0.0034301,
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'O16': 0.443386, 'O17': 0.000168}
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nuc_dens = m.get_nuclide_atom_densities()
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for nuclide in ref_dens:
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assert nuc_dens[nuclide] == pytest.approx(ref_dens[nuclide], 1e-2)
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# testing the use of brackets
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m = openmc.Material()
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m.add_elements_from_formula('Mg2(NO3)2')
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# checking the ratio of elements is 2:2:6 for Mg:N:O
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elem = defaultdict(float)
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for nuclide, adens in m.get_nuclide_atom_densities().items():
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if nuclide.startswith("Mg"):
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elem["Mg"] += adens
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if nuclide.startswith("N"):
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elem["N"] += adens
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if nuclide.startswith("O"):
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elem["O"] += adens
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total_number_of_atoms = 10
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assert elem["Mg"] == pytest.approx(2./total_number_of_atoms)
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assert elem["N"] == pytest.approx(2./total_number_of_atoms)
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assert elem["O"] == pytest.approx(6/total_number_of_atoms)
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# testing the correct nuclides are added when brackets are used
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ref_dens = {'Mg24': 0.157902, 'Mg25': 0.02004, 'Mg26': 0.022058,
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'N14': 0.199267, 'N15': 0.000732,
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'O16': 0.599772, 'O17': 0.000227}
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nuc_dens = m.get_nuclide_atom_densities()
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for nuclide in ref_dens:
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assert nuc_dens[nuclide] == pytest.approx(ref_dens[nuclide], 1e-2)
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# testing non integer multiplier results in a value error
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m = openmc.Material()
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with pytest.raises(ValueError):
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m.add_elements_from_formula('Li4.2SiO4')
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# testing lowercase elements results in a value error
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m = openmc.Material()
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with pytest.raises(ValueError):
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m.add_elements_from_formula('li4SiO4')
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# testing lowercase elements results in a value error
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m = openmc.Material()
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with pytest.raises(ValueError):
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m.add_elements_from_formula('Li4Sio4')
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# testing incorrect character in formula results in a value error
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m = openmc.Material()
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with pytest.raises(ValueError):
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m.add_elements_from_formula('Li4$SiO4')
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# testing unequal opening and closing brackets
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m = openmc.Material()
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with pytest.raises(ValueError):
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m.add_elements_from_formula('Fe(H2O)4(OH)2)')
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def test_density():
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m = openmc.Material()
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for unit in ['g/cm3', 'g/cc', 'kg/m3', 'atom/b-cm', 'atom/cm3']:
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m.set_density(unit, 1.0)
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with pytest.raises(ValueError):
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m.set_density('g/litre', 1.0)
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def test_salphabeta():
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m = openmc.Material()
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m.add_s_alpha_beta('c_H_in_H2O', 0.5)
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def test_repr():
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m = openmc.Material()
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m.add_nuclide('Zr90', 1.0)
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m.add_nuclide('H2', 0.5)
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m.add_s_alpha_beta('c_D_in_D2O')
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m.set_density('sum')
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m.temperature = 600.0
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repr(m)
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def test_macroscopic(run_in_tmpdir):
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m = openmc.Material(name='UO2')
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m.add_macroscopic('UO2')
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with pytest.raises(ValueError):
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m.add_nuclide('H1', 1.0)
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with pytest.raises(ValueError):
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m.add_element('O', 1.0)
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with pytest.raises(ValueError):
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m.add_macroscopic('Other')
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m2 = openmc.Material()
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m2.add_nuclide('He4', 1.0)
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with pytest.raises(ValueError):
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m2.add_macroscopic('UO2')
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# Make sure we can remove/add macroscopic
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m.remove_macroscopic('UO2')
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m.add_macroscopic('UO2')
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repr(m)
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# Make sure we can export a material with macroscopic data
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mats = openmc.Materials([m])
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mats.export_to_xml()
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def test_paths():
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model = openmc.examples.pwr_assembly()
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model.geometry.determine_paths()
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fuel = model.materials[0]
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assert fuel.num_instances == 264
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assert len(fuel.paths) == 264
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def test_isotropic():
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m1 = openmc.Material()
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m1.add_nuclide('U235', 1.0)
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m1.add_nuclide('O16', 2.0)
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m1.isotropic = ['O16']
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assert m1.isotropic == ['O16']
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m2 = openmc.Material()
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m2.add_nuclide('H1', 1.0)
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mats = openmc.Materials([m1, m2])
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mats.make_isotropic_in_lab()
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assert m1.isotropic == ['U235', 'O16']
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assert m2.isotropic == ['H1']
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def test_get_nuclides():
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mat = openmc.Material()
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mat.add_nuclide('Li6', 1.0)
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assert mat.get_nuclides() == ['Li6']
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assert mat.get_nuclides(element='Li') == ['Li6']
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assert mat.get_nuclides(element='Be') == []
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mat.add_element('Li', 1.0)
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assert mat.get_nuclides() == ['Li6', 'Li7']
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assert mat.get_nuclides(element='Be') == []
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mat.add_element('Be', 1.0)
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assert mat.get_nuclides() == ['Li6', 'Li7', 'Be9']
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assert mat.get_nuclides(element='Be') == ['Be9']
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def test_get_elements():
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# test that zero elements exist on creation
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m = openmc.Material()
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assert len(m.get_elements()) == 0
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# test addition of a single element
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m.add_element('Li', 0.2)
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assert m.get_elements() == ["Li"]
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# test that adding the same element
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m.add_element('Li', 0.3)
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assert m.get_elements() == ["Li"]
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# test adding another element
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m.add_element('Si', 0.3)
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assert m.get_elements() == ["Li", "Si"]
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# test adding a third element
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m.add_element('O', 0.4)
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assert m.get_elements() == ["Li", "O", "Si"]
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# test removal of nuclides
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m.remove_nuclide('O16')
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m.remove_nuclide('O17')
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assert m.get_elements() == ["Li", "Si"]
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def test_get_nuclide_densities(uo2):
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nucs = uo2.get_nuclide_densities()
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for nuc, density, density_type in nucs.values():
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assert nuc in ('U235', 'O16')
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assert density > 0
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assert density_type in ('ao', 'wo')
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def test_get_nuclide_atom_densities(uo2):
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for nuc, density in uo2.get_nuclide_atom_densities().items():
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assert nuc in ('U235', 'O16')
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assert density > 0
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def test_get_nuclide_atom_densities_specific(uo2):
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one_nuc = uo2.get_nuclide_atom_densities(nuclide='O16')
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assert list(one_nuc.keys()) == ['O16']
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assert list(one_nuc.values())[0] > 0
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all_nuc = uo2.get_nuclide_atom_densities()
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assert all_nuc['O16'] == one_nuc['O16']
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def test_get_nuclide_atoms():
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mat = openmc.Material()
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mat.add_nuclide('Li6', 1.0)
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mat.set_density('atom/cm3', 3.26e20)
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mat.volume = 100.0
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atoms = mat.get_nuclide_atoms()
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assert atoms['Li6'] == pytest.approx(mat.density * mat.volume)
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def test_mass():
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m = openmc.Material()
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m.add_nuclide('Zr90', 1.0, 'wo')
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m.add_nuclide('U235', 1.0, 'wo')
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m.set_density('g/cm3', 2.0)
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m.volume = 10.0
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assert m.get_mass_density('Zr90') == pytest.approx(1.0)
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assert m.get_mass_density('U235') == pytest.approx(1.0)
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assert m.get_mass_density() == pytest.approx(2.0)
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assert m.get_mass('Zr90') == pytest.approx(10.0)
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assert m.get_mass('U235') == pytest.approx(10.0)
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assert m.get_mass() == pytest.approx(20.0)
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assert m.fissionable_mass == pytest.approx(10.0)
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def test_materials(run_in_tmpdir):
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m1 = openmc.Material()
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m1.add_nuclide('U235', 1.0, 'wo')
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m1.add_nuclide('O16', 2.0, 'wo')
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m1.set_density('g/cm3', 10.0)
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m1.depletable = True
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m1.temperature = 900.0
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m2 = openmc.Material()
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m2.add_nuclide('H1', 2.0)
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m2.add_nuclide('O16', 1.0)
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m2.add_s_alpha_beta('c_H_in_H2O')
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m2.set_density('kg/m3', 1000.0)
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mats = openmc.Materials([m1, m2])
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mats.cross_sections = '/some/fake/cross_sections.xml'
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mats.export_to_xml()
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def test_borated_water():
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# Test against reference values from the BEAVRS benchmark.
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m = openmc.model.borated_water(975, 566.5, 15.51, material_id=50)
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assert m.density == pytest.approx(0.7405, 1e-3)
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assert m.temperature == pytest.approx(566.5)
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assert m._sab[0][0] == 'c_H_in_H2O'
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ref_dens = {'B10':8.0023e-06, 'B11':3.2210e-05, 'H1':4.9458e-02,
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'O16':2.4672e-02}
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nuc_dens = m.get_nuclide_atom_densities()
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for nuclide in ref_dens:
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assert nuc_dens[nuclide] == pytest.approx(ref_dens[nuclide], 1e-2)
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assert m.id == 50
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# Test the Celsius conversion.
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m = openmc.model.borated_water(975, 293.35, 15.51, 'C')
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assert m.density == pytest.approx(0.7405, 1e-3)
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|
# 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'
|
|
|
|
|
|
def test_mix_materials():
|
|
m1 = openmc.Material()
|
|
m1.add_nuclide('U235', 1.)
|
|
m1dens = 10.0
|
|
m1amm = m1.average_molar_mass
|
|
m1.set_density('g/cm3', m1dens)
|
|
m2 = openmc.Material()
|
|
m2.add_nuclide('Zr90', 1.)
|
|
m2dens = 2.0
|
|
m2amm = m2.average_molar_mass
|
|
m2.set_density('g/cm3', m2dens)
|
|
f0, f1 = 0.6, 0.4
|
|
dens3 = (f0*m1amm + f1*m2amm) / (f0*m1amm/m1dens + f1*m2amm/m2dens)
|
|
dens4 = 1. / (f0 / m1dens + f1 / m2dens)
|
|
dens5 = f0*m1dens + f1*m2dens
|
|
m3 = openmc.Material.mix_materials([m1, m2], [f0, f1], percent_type='ao')
|
|
m4 = openmc.Material.mix_materials([m1, m2], [f0, f1], percent_type='wo')
|
|
m5 = openmc.Material.mix_materials([m1, m2], [f0, f1], percent_type='vo')
|
|
assert m3.density == pytest.approx(dens3)
|
|
assert m4.density == pytest.approx(dens4)
|
|
assert m5.density == pytest.approx(dens5)
|
|
|
|
|
|
def test_get_activity():
|
|
"""Tests the activity of stable, metastable and active materials"""
|
|
|
|
# Creates a material with stable isotopes to check the activity is 0
|
|
m1 = openmc.Material()
|
|
m1.add_element("Fe", 0.7)
|
|
m1.add_element("Li", 0.3)
|
|
m1.set_density('g/cm3', 1.5)
|
|
# activity in Bq/cc and Bq/g should not require volume setting
|
|
assert m1.get_activity(units='Bq/cm3') == 0
|
|
assert m1.get_activity(units='Bq/g') == 0
|
|
m1.volume = 1
|
|
assert m1.get_activity(units='Bq') == 0
|
|
|
|
# Checks that 1g of tritium has the correct activity scaling
|
|
m2 = openmc.Material()
|
|
m2.add_nuclide("H3", 1)
|
|
m2.set_density('g/cm3', 1)
|
|
m2.volume = 1
|
|
assert pytest.approx(m2.get_activity(units='Bq')) == 3.559778e14
|
|
m2.set_density('g/cm3', 2)
|
|
assert pytest.approx(m2.get_activity(units='Bq')) == 3.559778e14*2
|
|
m2.volume = 3
|
|
assert pytest.approx(m2.get_activity(units='Bq')) == 3.559778e14*2*3
|
|
|
|
# Checks that 1 mol of a metastable nuclides has the correct activity
|
|
m3 = openmc.Material()
|
|
m3.add_nuclide("Tc99_m1", 1)
|
|
m3.set_density('g/cm3', 1)
|
|
m3.volume = 98.9
|
|
assert pytest.approx(m3.get_activity(units='Bq'), rel=0.001) == 1.93e19
|
|
|
|
# Checks that specific and volumetric activity of tritium are correct
|
|
m4 = openmc.Material()
|
|
m4.add_nuclide("H3", 1)
|
|
m4.set_density('g/cm3', 1.5)
|
|
assert pytest.approx(m4.get_activity(units='Bq/g')) == 355978108155965.94 # [Bq/g]
|
|
assert pytest.approx(m4.get_activity(units='Bq/g', by_nuclide=True)["H3"]) == 355978108155965.94 # [Bq/g]
|
|
assert pytest.approx(m4.get_activity(units='Bq/cm3')) == 355978108155965.94*3/2 # [Bq/cc]
|
|
assert pytest.approx(m4.get_activity(units='Bq/cm3', by_nuclide=True)["H3"]) == 355978108155965.94*3/2 # [Bq/cc]
|
|
# volume is required to calculate total activity
|
|
m4.volume = 10.
|
|
assert pytest.approx(m4.get_activity(units='Bq')) == 355978108155965.94*3/2*10 # [Bq]
|
|
|
|
|
|
def test_get_decay_heat():
|
|
# Set chain file for testing
|
|
openmc.config['chain_file'] = Path(__file__).parents[1] / 'chain_simple.xml'
|
|
|
|
"""Tests the decay heat of stable, metastable and active materials"""
|
|
m1 = openmc.Material()
|
|
m1.add_nuclide("U235", 0.2)
|
|
m1.add_nuclide("U238", 0.8)
|
|
m1.set_density('g/cm3', 10.5)
|
|
# decay heat in W/cc and W/g should not require volume setting
|
|
assert m1.get_decay_heat(units='W/cm3') == 0
|
|
assert m1.get_decay_heat(units='W/g') == 0
|
|
m1.volume = 1
|
|
assert m1.get_decay_heat(units='W') == 0
|
|
|
|
# Checks that 1g of tritium has the correct decay heat scaling
|
|
m2 = openmc.Material()
|
|
m2.add_nuclide("I135", 1)
|
|
m2.set_density('g/cm3', 1)
|
|
m2.volume = 1
|
|
assert pytest.approx(m2.get_decay_heat(units='W')) == 40175.15720273193
|
|
m2.set_density('g/cm3', 2)
|
|
assert pytest.approx(m2.get_decay_heat(units='W')) == 40175.15720273193*2
|
|
m2.volume = 3
|
|
assert pytest.approx(m2.get_decay_heat(units='W')) == 40175.15720273193*2*3
|
|
|
|
# Checks that 1 mol of a metastable nuclides has the correct decay heat
|
|
m3 = openmc.Material()
|
|
m3.add_nuclide("Xe135", 1)
|
|
m3.set_density('g/cm3', 1)
|
|
m3.volume = 98.9
|
|
assert pytest.approx(m3.get_decay_heat(units='W'), rel=0.001) == 846181.2921143445
|
|
|
|
# Checks that specific and volumetric decay heat of tritium are correct
|
|
m4 = openmc.Material()
|
|
m4.add_nuclide("I135", 1)
|
|
m4.set_density('g/cm3', 1.5)
|
|
assert pytest.approx(m4.get_decay_heat(units='W/g')) == 40175.15720273193 # [W/g]
|
|
assert pytest.approx(m4.get_decay_heat(units='W/g', by_nuclide=True)["I135"]) == 40175.15720273193 # [W/g]
|
|
assert pytest.approx(m4.get_decay_heat(units='W/cm3')) == 40175.15720273193*3/2 # [W/cc]
|
|
assert pytest.approx(m4.get_decay_heat(units='W/cm3', by_nuclide=True)["I135"]) == 40175.15720273193*3/2 #[W/cc]
|
|
# volume is required to calculate total decay heat
|
|
m4.volume = 10.
|
|
assert pytest.approx(m4.get_decay_heat(units='W')) == 40175.15720273193*3/2*10 # [W]
|
|
|
|
|
|
def test_decay_photon_energy():
|
|
# Set chain file for testing
|
|
openmc.config['chain_file'] = Path(__file__).parents[1] / 'chain_simple.xml'
|
|
|
|
# Material representing single atom of I135 and Cs135
|
|
m = openmc.Material()
|
|
m.add_nuclide('I135', 1.0e-24)
|
|
m.add_nuclide('Cs135', 1.0e-24)
|
|
m.volume = 1.0
|
|
|
|
# Get decay photon source and make sure it's the right type
|
|
src = m.decay_photon_energy
|
|
assert isinstance(src, openmc.stats.Discrete)
|
|
|
|
# If we add Xe135 (which has a tabular distribution), the photon source
|
|
# should be a mixture distribution
|
|
m.add_nuclide('Xe135', 1.0e-24)
|
|
src = m.decay_photon_energy
|
|
assert isinstance(src, openmc.stats.Mixture)
|
|
|
|
# With a single atom of each, the intensity of the photon source should be
|
|
# equal to the sum of the intensities for each nuclide
|
|
def intensity(src):
|
|
return src.integral() if src is not None else 0.0
|
|
|
|
assert src.integral() == pytest.approx(sum(
|
|
intensity(decay_photon_energy(nuc)) for nuc in m.get_nuclides()
|
|
))
|
|
|
|
# A material with no unstable nuclides should have no decay photon source
|
|
stable = openmc.Material()
|
|
stable.add_nuclide('Gd156', 1.0)
|
|
stable.volume = 1.0
|
|
assert stable.decay_photon_energy is None
|