Hi all,
In a depletion analysis, I wish to know the fission rate in a single nuclide over time. I used:
results = openmc.deplete.ResultsList.from_hdf5(“depletion_results.h5”)
fission = results.get_reaction_rate(“1”,”U235”,”fission”)
I noted that the fission values are multiplied by 1e15. In this case, are the fission rate units “reactions per source particle” or are they internally converted?
Thanks,
Javier