Continous Energy Neutron Cross Section Data Library for MCDC

This is the cross section library for the dynamic neutron transport code MC/DC [github], [documentation]. The data is published as .h5 files and is mono-temperature. This data is produced from data provided by OpenMC and is copmiled for MC/DC's use.

This work was supported by the Center for Exascale Monte-Carlo Neutron Transport (CEMeNT) a PSAAP-III project funded by the Department of Energy, grant number: DE-NA003967.