Abstract class for obtaining normalization factor on tallies
This helper class determines how reaction rates calculated by an instance of
openmc.deplete.Operatorshould 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 a
ReactionRateHelper, 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
Return normalization factor
Parameters: source_rate (float) – Power in [W] or source rate in [neutron/sec] Returns: Normalization factor for tallies Return type: float
List of nuclides with requested reaction rates
Perform work needed to obtain energy produced
This method is called prior to the transport simulations in
openmc.deplete.Operator.initial_condition(). Only used for energy-based normalization.
- 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
Reset state for normalization