Calculation of kinetic parameters relevant to fissile system with an external neutron source #3495
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Description
This PR extend OpenMC capabilities to calculate kinetic parameters relevant to fissile systems with
an external neutron source (i.e. ADS, reactor startup).
The changes needed include calculating standard deviation of k of each generation and storing it in the statepoint in the cpp side and simple postprocessing on the python side.
Theory and Validation
The implementation and testing follows the following papers:
Checklist