A VALIDATION OF COPPER, NICKEL AND IRON DATA IN ENDF B-VI.2, JEF-2.2 AND JENDL-3.2 THROUGH A SERIES OF BR-1 CRITICAL CORE ANALYSIS/

This report discusses the lessons learned from a validation of copper, nickel and iron data in ENDF/B-VI.2, JEF-2.2 and JENDL-3.2 through an analysis of 97.6 at. % (PU)-P-239 metal fueled BR-1 fast reactor benc hmarks. The specifications for the benchmarks in this study were taken from the ICSBEP handbook. The Monte Carlo code MCNP4B and continuous- energy cross-section libraries processed from the above three evaluate d nuclear data files were used to perform the critical benchmark calcu lations. There is reasonable agreement between the predicted k(eff)-va lues and the benchmarks within the uncertainties of measurements and M onte Carlo calculations, with the exception of the JEF-2.2 and JENDL-3 .2 results for the copper-reflected core. The JEF-2.2 and JENDL-3.2 da ta give higher k(eff)-values than those of ENDF/B-VI.2 for all the thr ee reflector materials. (C) 1998 Elsevier Science Ltd. All rights rese rved.