openmc.deplete.abc.NormalizationHelper¶
- class openmc.deplete.abc.NormalizationHelper[source]¶
Abstract class for obtaining normalization factor on tallies
This helper class determines how reaction rates calculated by an instance of
openmc.deplete.abc.TransportOperator
should be normalized for the purpose of constructing a burnup matrix. Based on the method chosen, the power or source rate provided by the user, and reaction rates from aReactionRateHelper
, this class will scale reaction rates to the correct values.- Variables
nuclides (list of str) – All nuclides with desired reaction rates. Ordered to be consistent with
openmc.deplete.abc.TransportOperator
- property nuclides¶
List of nuclides with requested reaction rates
- abstract prepare(chain_nucs: Sequence[str], rate_index: dict)[source]¶
Perform work needed to obtain energy produced
This method is called prior to calculating the reaction rates in
openmc.deplete.abc.TransportOperator.initial_condition()
. Only used for energy-based normalization.- Parameters
chain_nucs (list of str) – All nuclides to be tracked in this problem
rate_index (dict of str to int) – Mapping from nuclide name to index in the fission_rates for
update()
.
- update(fission_rates)[source]¶
Update the normalization based on fission rates (only used for energy-based normalization)
- Parameters
fission_rates (numpy.ndarray) – fission reaction rate for each isotope in the specified material. Should be ordered corresponding to initial
rate_index
used inprepare()