EPJ Web of Conferences (Mar 2013)
Improved MOX fuel calculations using new Pu-239, Am-241 and Pu-240 evaluations
Abstract
Several studies based on the JEFF-3.1.1 nuclear data library show a systematic overestimation of the critical keff for core configurations of MOX fuel assemblies. The present work investigates possible improvements of the C/E results by using new evaluations for Am-241, Pu-239 and Pu-240.