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Add function to pull nuclear data from OpenMC nuclear data, GNDS, or ACE files
I was going through the documentation for MC/DC materials, and it wasn't clear to me how to create a nuclide with a continuous energy nuclear data set. Obviously users wouldn't manually specify this. Rather they would pull it from a file. It would be nice to be able to pull this from an OpenMC HDF5 file, or if really necessary, an ACE file.
This is something we've discussed and plan to implement, thanks Micah!