openmc.deplete.helpers.ConstantFissionYieldHelper¶
- 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 dictionaryenergy (float) – Energy of fission yield libraries.
- 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__
method- Parameters
operator (openmc.deplete.abc.TransportOperator) – operator with a depletion chain
kwargs – Additional keyword arguments to be used in construction
- Return type