TRANSX/DANT benchmark studies using a ENDF/B-V based MATXS library

摘要

A series of 20 benchmark critical experiments were studied using the DANT code with cross section libraries prepared by TRANSX from ENDF/B-V based MATXS libraries. The benchmarks were selected to cover both fast and thermal systems utilizing either uranium or plutonium as the primary fissile isotope. An effort was made to cover the range of isotopes prevalent in nuclear systems, though no heterogeneous thermal plutonium cases were included. The results indicate that the code package and library give satisfactory results for the majority of cases, though the results are somewhat poorer for thermal plutonium cases.