ON THE VALIDATION OF RELEASE-3 OF ENDF B-VI NUCLEAR-DATA FOR LIGHT-WATER REACTOR CRITICALITY ANALYSIS/

Release 3 of the ENDF/B-VI nuclear data library is validated for use i n light water criticality analysis. Eigenvalue and fuel rod fission de nsity results are compared to those corresponding to version V and rel ease 2 of version VI. Twelve critical experiments with varying paramet ers such as temperature, burnable absorber content and the amount of c ontrol poison are simulated with the continuous energy Monte Carlo cod e MCNP as the basis for comparison. II is found that the ENDF/B-V libr ary yields more accurate results than ENDF/B-VI, releases 2 and 3 for criticality analysis in light water reactors. (C) 1997 Elsevier Scienc e Ltd.