Abstract
MNF and AREVA have been developing the BWR core calculation system CASMO-4/MICROBURN-B2, which has been modified to represent the ATRIUM^<TM1> 10XM fuel assembly characteristics and satisfy Japanese regulatory requirements. In this system, the cross section values and other nuclear constants for the assemblies are generated by the CASMO-4 code. The accuracy of isotopic concentration predictions is very important and the verification and the validation of such predictions have been requested by the regulatory agencies. AREVA and MNF have performed calculations for two BWR fuel rods - denoted as SF98 and SF99 - the post-irradiation examination assays of which are described in "Technical Development on Burn-up Credit for Spent LWR Fuels (JAERI-Tech 2000-071)". This paper describes the results of comparisons between the assay results and these calculations, the observed trends, and compares those results and trends with results obtained by other investigators.
