openmc.deplete.helpers.ConstantFissionYieldHelper¶
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class
openmc.deplete.helpers.
ConstantFissionYieldHelper
(chain_nuclides, energy=0.0253)[source]¶ Class that uses a single set of fission yields on each isotope
Parameters: - chain_nuclides (iterable of openmc.deplete.Nuclide) – Nuclides tracked in the depletion chain. All nuclides are not required to have fission yield data.
- energy (float, optional) – Key in
openmc.deplete.Nuclide.yield_data
corresponding to the desired set of fission yield data. Typically one of{0.0253, 500000, 14000000}
corresponding to 0.0253 eV, 500 keV, and 14 MeV yield libraries. If the specific key is not found, will fall back to closest energy present. Default: 0.0253 eV for thermal yields
Variables: - constant_yields (collections.defaultdict) – Fission yields for all nuclides that only have one set of
fission yield data. Dictionary of form
{str: {str: float}}
representing yields for{parent: {product: yield}}
. Default return object is an empty dictionary - energy (float) – Energy of fission yield libraries.
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classmethod
from_operator
(operator, **kwargs)[source]¶ Return a new ConstantFissionYieldHelper using operator data
All keyword arguments should be identical to their counterpart in the main
__init__
methodParameters: - operator (openmc.deplete.TransportOperator) – operator with a depletion chain
- kwargs – Additional keyword arguments to be used in construction
Returns: Return type:
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weighted_yields
(_local_mat_index=None)[source]¶ Return fission yields for all nuclides requested
Parameters: _local_mat_index (int, optional) – Current material index. Not used since all yields are constant Returns: library – Dictionary of {parent: {product: fyield}}
Return type: collections.defaultdict