Hello Every one,
I’m using MCNP cross section data i added MCNP data directory into cross_sections_ascii.xml and i added this directory in my setting.xml file . In my material.xml file im having
all other cross sections tables are being loaded very well , but im getting this error at the end
ERROR: S(a,b) table lwtr.10t did not match any nuclide on material 3
while im using Openmc v 0.8.0 , any idea how to fix this error ???
Thanks
Ahmed K Madani