Hello,
indeed this needs to be followed-up on.
I have done some testing and can confirm that the OpenMC Official Lucite TSL is faulty.
-
ENDF/B-VIII.0 of Official Data Libraries | OpenMC
produces incorrect results -
ENDF/B-VIII.0 of LANL-Based Data Libraries | OpenMC
correct results (matches MCNP)
This was in a solid block of lucite in my own, closed benchmark.
OpenMC w/OpenMC ENDF80 calculates thermal neutron fluxes 8% higher than they should be (compared against MCNP w/LANL ENDF80 and OpenMC /wLANL ENDF80).
I am now a little worried about the polyethylene TSL… (that one is very important, has much wider use and importance)
I will be creating an issue, hopefully I can include some benchmarks (HEU-MET-THERM-004, PU-MET-THERM-004)