openmc_activator

Standalone openmc activator to get activated composition from MG flux and irradiation scheme.

The module is tested on the Fusion Neutron Source (FNS) Decay Heat Benchmark

This module is actually part of the Fusion Energy Reactor Models Integrator (FERMI) project. A similar module exists for ORIGEN.

Contents

1. download_fns_fusion_decay.py: Script to download and extract the FNS benchmark data files from website
2. compre.ipynb: Jupyter notebook going through the process of using OpenmcActivator to reproduce FNS benchmark with OpenMC and comparing the results
3. openmc_activator.py: Python class for standalone neutron source activation with OpenMC

Note

The jupyter notebook in this repository will not yield results similar to the FNS decay heat benchmark, due to not incorportaing nuclide reaction yield data (e.g., Ag107 -> (n,gamma) -> Ag108 or Ag108m). This was resovled by the original author by using ORIGEN multigroup nuclide reaction yield data to append flux-normalized branch_ratios in the chain file. That data, unfortunately, cannot be shared in this public repository. This issue in the OpenMC git repo details this issue in OpenMC, and disucssions on potential longer-term solutions.