Hello,
I am using OpenMC depletion with CoupledOperator function. When I use the OpenMC HDF5 library based on ENDF/B-VII.1, I do not encounter any issue when using normalization_mode="energy-deposition of energy calculation.
But when I use a custom HDF5 library generated from our own ACE files at ASNR, using from_ace(), the depletion calculation fails with: “No energy reported from OpenMC tallies”.
I checked both my ACE files and the converted HDF5 files we have at ASNR, and they contain MT=301 heating but no MT=901 heating-local.
My questions are:
- Is the absence of MT=901 in HDF5 files generated via
IncidentNeutron.from_ace()expected behavior? - Does
normalization_mode="energy-deposition"require MT=901 (heating-local) whenphoton_transport=False, even when valid MT=301 heating data are present? - Is there a recommended workflow for ACE-derived libraries to support
normalization_mode="energy-deposition", or is this mode intended only for libraries generated through the ENDF->NJOY->OpenMC workflow?
Thank you.