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OpenMC Monte Carlo Code
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Feature request. Decay data processing and xml file for lookup #2138

Open shimwell opened 1 year ago

shimwell commented 1 year ago

While looking through PR #2135 I was thinking it might be useful if the openmc.data.Decay class have an export_to_hdf5 and a from_hdf5 classmethod.

This would allow us to process endf decay data into h5 files.

Once in h5 file format perhaps we could have decay data entries in the cross_sections.xml file or an equivalent xml file?

This would help automatically loading the decay data on demand for materials with lots of nuclides when we don't what to identify the individual endf files to use each time when making Decay instances.

shimwell commented 1 year ago

Perhaps the openmc.data.Decay.export_to_hdf5 could look a bit like this https://github.com/shimwell/openmc/blob/79b2740eea196f23cd2198e79c4e8658597fb70f/openmc/data/decay.py#L483-L520