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Calculation of kinetic parameters relevant to fissile system with an external neutron source #3495

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@GuySten GuySten commented Jul 11, 2025

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

  • I have performed a self-review of my own code
  • I have run clang-format (version 15) on any C++ source files (if applicable)
  • I have followed the style guidelines for Python source files (if applicable)
  • I have made corresponding changes to the documentation (if applicable)
  • I have added tests that prove my fix is effective or that my feature works (if applicable)

@GuySten GuySten marked this pull request as ready for review July 13, 2025 03:28
@GuySten GuySten changed the title Calculation of kinetics parameters relevant to fissile system with an external neutron source Calculation of kinetic parameters relevant to fissile system with an external neutron source Jul 13, 2025
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