def test_fission_yield_distribution():
"""Test an energy-dependent yield distribution"""
yield_dict = {
0.0253: {
"Xe135": 7.85e-4,
"Gd155": 4.08e-12,
"Sm149": 1.71e-12
},
1.40e7: {
"Xe135": 4.54e-3,
"Gd155": 5.83e-8,
"Sm149": 2.69e-8
},
5.00e5: {
"Xe135": 1.12e-3,
"Gd155": 1.32e-12
}, # drop Sm149
}
yield_dist = nuclide.FissionYieldDistribution(yield_dict)
assert len(yield_dist) == len(yield_dict)
assert yield_dist.energies == tuple(sorted(yield_dict.keys()))
for exp_ene, exp_dist in yield_dict.items():
act_dist = yield_dict[exp_ene]
for exp_prod, exp_yield in exp_dist.items():
assert act_dist[exp_prod] == exp_yield
exp_yield = numpy.array([[4.08e-12, 1.71e-12, 7.85e-4],
[1.32e-12, 0.0, 1.12e-3],
[5.83e-8, 2.69e-8, 4.54e-3]])
assert numpy.array_equal(yield_dist.yield_matrix, exp_yield)
# Test the operations / special methods for fission yield
orig_yields = yield_dist[0.0253]
assert len(orig_yields) == len(yield_dict[0.0253])
for key, value in yield_dict[0.0253].items():
assert key in orig_yields
assert orig_yields[key] == value
# __getitem__ return yields as a view into yield matrix
assert orig_yields.yields.base is yield_dist.yield_matrix
# Fission yield feature uses scaled and incremented
mod_yields = orig_yields * 2
assert numpy.array_equal(orig_yields.yields * 2, mod_yields.yields)
mod_yields += orig_yields
assert numpy.array_equal(orig_yields.yields * 3, mod_yields.yields)
# Failure modes for adding, multiplying yields
similar = numpy.empty_like(orig_yields.yields)
with pytest.raises(TypeError):
orig_yields + similar
with pytest.raises(TypeError):
similar + orig_yields
with pytest.raises(TypeError):
orig_yields += similar
with pytest.raises(TypeError):
orig_yields * similar
with pytest.raises(TypeError):
similar * orig_yields
with pytest.raises(TypeError):
orig_yields *= similar
def test_from_xml():
"""Test reading nuclide data from an XML element."""
data = """
<nuclide name="U235" reactions="2">
<decay type="sf" target="U235" branching_ratio="7.2e-11"/>
<decay type="alpha" target="Th231" branching_ratio="0.999999999928"/>
<reaction type="(n,2n)" target="U234" Q="-5297781.0"/>
<reaction type="(n,3n)" target="U233" Q="-12142300.0"/>
<reaction type="(n,4n)" target="U232" Q="-17885600.0"/>
<reaction type="(n,gamma)" target="U236" Q="6545200.0"/>
<reaction type="fission" Q="193405400.0"/>
<neutron_fission_yields>
<energies>0.0253</energies>
<fission_yields energy="0.0253">
<products>Te134 Zr100 Xe138</products>
<data>0.062155 0.0497641 0.0481413</data>
</fission_yields>
</neutron_fission_yields>
</nuclide>
"""
element = ET.fromstring(data)
u235 = nuclide.Nuclide.from_xml(element)
assert u235.decay_modes == [
nuclide.DecayTuple('sf', 'U235', 7.2e-11),
nuclide.DecayTuple('alpha', 'Th231', 1 - 7.2e-11)
]
assert u235.reactions == [
nuclide.ReactionTuple('(n,2n)', 'U234', -5297781.0, 1.0),
nuclide.ReactionTuple('(n,3n)', 'U233', -12142300.0, 1.0),
nuclide.ReactionTuple('(n,4n)', 'U232', -17885600.0, 1.0),
nuclide.ReactionTuple('(n,gamma)', 'U236', 6545200.0, 1.0),
nuclide.ReactionTuple('fission', None, 193405400.0, 1.0),
]
expected_yield_data = nuclide.FissionYieldDistribution(
{0.0253: {
"Xe138": 0.0481413,
"Zr100": 0.0497641,
"Te134": 0.062155
}})
assert u235.yield_data == expected_yield_data
# test accessing the yield energies through the FissionYieldDistribution
assert u235.yield_energies == (0.0253, )
assert u235.yield_energies is u235.yield_data.energies
with pytest.raises(AttributeError): # not settable
u235.yield_energies = [0.0253, 5e5]
def test_export_to_xml(run_in_tmpdir):
"""Test writing a depletion chain to XML."""
# Prevent different MPI ranks from conflicting
filename = 'test{}.xml'.format(comm.rank)
H1 = nuclide.Nuclide("H1")
A = nuclide.Nuclide("A")
A.half_life = 2.36520e4
A.decay_modes = [
nuclide.DecayTuple("beta1", "B", 0.6),
nuclide.DecayTuple("beta2", "C", 0.4)
]
A.reactions = [
nuclide.ReactionTuple("(n,gamma)", "C", 0.0, 1.0),
nuclide.ReactionTuple("(n,p)", "B", 0.0, 1.0)
]
B = nuclide.Nuclide("B")
B.half_life = 3.29040e4
B.decay_modes = [nuclide.DecayTuple("beta", "A", 1.0)]
B.reactions = [
nuclide.ReactionTuple("(n,gamma)", "C", 0.0, 1.0),
nuclide.ReactionTuple("(n,d)", "A", 0.0, 1.0)
]
C = nuclide.Nuclide("C")
C.reactions = [
nuclide.ReactionTuple("fission", None, 2.0e8, 1.0),
nuclide.ReactionTuple("(n,gamma)", "A", 0.0, 0.7),
nuclide.ReactionTuple("(n,gamma)", "B", 0.0, 0.3)
]
C.yield_data = nuclide.FissionYieldDistribution(
{0.0253: {
"A": 0.0292737,
"B": 0.002566345
}})
chain = Chain()
chain.nuclides = [H1, A, B, C]
chain.export_to_xml(filename)
chain_xml = open(filename, 'r').read()
assert _TEST_CHAIN == chain_xml
def test_to_xml_element():
"""Test writing nuclide data to an XML element."""
C = nuclide.Nuclide("C")
C.half_life = 0.123
C.decay_modes = [
nuclide.DecayTuple('beta-', 'B', 0.99),
nuclide.DecayTuple('alpha', 'D', 0.01)
]
C.reactions = [
nuclide.ReactionTuple('fission', None, 2.0e8, 1.0),
nuclide.ReactionTuple('(n,gamma)', 'A', 0.0, 1.0)
]
C.yield_data = nuclide.FissionYieldDistribution(
{0.0253: {
"A": 0.0292737,
"B": 0.002566345
}})
element = C.to_xml_element()
assert element.get("half_life") == "0.123"
decay_elems = element.findall("decay")
assert len(decay_elems) == 2
assert decay_elems[0].get("type") == "beta-"
assert decay_elems[0].get("target") == "B"
assert decay_elems[0].get("branching_ratio") == "0.99"
assert decay_elems[1].get("type") == "alpha"
assert decay_elems[1].get("target") == "D"
assert decay_elems[1].get("branching_ratio") == "0.01"
rx_elems = element.findall("reaction")
assert len(rx_elems) == 2
assert rx_elems[0].get("type") == "fission"
assert float(rx_elems[0].get("Q")) == 2.0e8
assert rx_elems[1].get("type") == "(n,gamma)"
assert rx_elems[1].get("target") == "A"
assert float(rx_elems[1].get("Q")) == 0.0
assert element.find('neutron_fission_yields') is not None