Multi-group capability for kinetics parameter calculations with Iterated Fission Probability #3385
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Adapting of the tally scores to give multigroup beta-effective values when passed a delayed group filter.
Fixed setting the Tally Index for the DelayedGroup Filter.
changed @lru_cache to the lighter @cache from Python 3.9 added _init_ifp() to automatically create IFP tallies for the enabled setting and ifp_results() for quick data retrieval with automatic arithmetic.
changed @lru_cache to the lighter @cache from Python 3.9 added _init_ifp() to automatically create IFP tallies for the enabled setting and ifp_results() for quick data retrieval with automatic arithmetic.
…/openmc-ifp into kinetics_ifp_mpi_optim
… IFP tally is used
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Description
Adaptation of existing kinetics parameter calculations using Iterated Fission Probability (IFP) to provide multi-group effective delayed neutron fractions. This adaptation of the current IFP implementation added in 47ca291 will allow OpenMC to generate all parameters necessary for full 6-group point kinetics modelling.
Additional convenience functions will be added to build on top of #3133 to streamline enabling full kinetics parameter calculations and provision. Ideally, the
openmc.model.Modelclass will be modified to automatically initialize all the necessary tallies when the appropriate IFP settings are created in theopenmc.Settings. Adjustments toopenmc.Statepointwill handle the calculation of the parameters from the existing tallies and provide the parameters.Development is being done with support from @sallustius and @JoffreyDorville.
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