Hello everyone, I’ve recently been attempting to obtain macroscopic cross-sections using tallies and apply them to “multi-group” calculations in OpenMC. I’ve tried three methods so far, but none have worked successfully:
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I performed numerical calculations on values like total, absorption, and flux obtained from tallies to get macroscopic cross-sections, and tried exporting them using the
export_to_hdf5method. However, the values obtained this way cannot be used with this method. -
I wanted to format the calculated macroscopic cross-sections into the structure of an MGXS library and create an
mgxs_libobject. But I was informed that this must be retrieved from a statepoint file. -
I attempted to read the
mgxs_libfrom the statepoint file first, then modify its values to my calculated macroscopic cross-sections. However, I consistently encountered the following error: “UnboundLocalError: cannot access local variable ‘scatt_mgxs’ where it is not associated with a value”.
Does anyone know how to use self-calculated macroscopic cross-sections for multi-group Monte Carlo calculations in OpenMC?
Thank you very much!
Yunhan