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Add option to determine waste disposal rating by nuclide (#3376)

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Paul Romano 2025-05-02 19:07:43 -05:00 • committed by GitHub
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3 changed files with 35 additions and 16 deletions
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22
openmc/material.py
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@ -1348,10 +1348,11 @@ class Material(IDManagerMixin):
return waste._waste_classification(self, metal=metal)
def waste_disposal_rating(
self,
limits: str | dict[str, float] = 'Fetter',
metal: bool = False,
) -> float:
self,
limits: str | dict[str, float] = 'Fetter',
metal: bool = False,
by_nuclide: bool = False,
) -> float | dict[str, float]:
"""Return the waste disposal rating for the material.
This method returns a waste disposal rating for the material based on a
@ -1387,18 +1388,25 @@ class Material(IDManagerMixin):
metal : bool, optional
Whether or not the material is in metal form (only applicable for
NRC based limits)
by_nuclide : bool, optional
Whether to return the waste disposal rating for each nuclide in the
material. If True, a dictionary is returned where the keys are the
nuclide names and the values are the waste disposal ratings for each
nuclide. If False, a single float value is returned that represents
the overall waste disposal rating for the material.
Returns
-------
float
The waste disposal rating for the material.
float or dict
The waste disposal rating for the material or its constituent
nuclides.
See also
--------
Material.waste_classification()
"""
return waste._waste_disposal_rating(self, limits, metal)
return waste._waste_disposal_rating(self, limits, metal, by_nuclide)
def clone(self, memo: dict | None = None) -> Material:
"""Create a copy of this material with a new unique ID.

25
openmc/waste.py
View file

@ -77,10 +77,11 @@ def _waste_classification(mat: openmc.Material, metal: bool = True) -> str:
def _waste_disposal_rating(
mat: openmc.Material,
limits: str | dict[str, float] = 'Fetter',
metal: bool = False,
) -> float:
mat: openmc.Material,
limits: str | dict[str, float] = 'Fetter',
metal: bool = False,
by_nuclide: bool = False,
) -> float | dict[str, float]:
"""Return the waste disposal rating for a material.
This method returns a waste disposal rating for the material based on a set
@ -111,11 +112,17 @@ def _waste_disposal_rating(
metal : bool, optional
Whether or not the material is in metal form (only applicable for NRC
based limits)
by_nuclide : bool, optional
Whether to return the waste disposal rating for each nuclide in the
material. If True, a dictionary is returned where the keys are the
nuclide names and the values are the waste disposal ratings for each
nuclide. If False, a single float value is returned that represents the
overall waste disposal rating for the material.
Returns
-------
float
The waste disposal rating for the material.
float or dict
The waste disposal rating for the material or its constituent nuclides.
"""
if limits == 'Fetter':
@ -272,8 +279,8 @@ def _waste_disposal_rating(
# Calculate the sum of the fractions of the activity of each radionuclide
# compared to the specified limits
ratio = 0.0
ratio = {}
for nuc, ci_m3 in mat.get_activity(units="Ci/m3", by_nuclide=True).items():
if nuc in limits:
ratio += ci_m3 / limits[nuc]
return ratio
ratio[nuc] = ci_m3 / limits[nuc]
return ratio if by_nuclide else sum(ratio.values())

4
tests/unit_tests/test_waste_classification.py
View file

@ -96,3 +96,7 @@ def test_waste_disposal_rating():
ci_m3 = mat.get_activity('Ci/m3')
assert mat.waste_disposal_rating(limits={'K40': 2*ci_m3}) < 1.0
assert mat.waste_disposal_rating(limits={'K40': 0.5*ci_m3}) > 1.0
wdr = mat.waste_disposal_rating(limits={'K40': 4*ci_m3}, by_nuclide=True)
assert isinstance(wdr, dict)
assert wdr['K40'] == pytest.approx(1/4)