The MNP analysis of BWR-simulated critical experiments with ENDF/B-VI.2 and JEF-2.2

In the past few years, a number of new revisions of major evaluated nuclear data files such as ENDF/B-VI.2, JEF-2.2, JENDL-3.2, and BROND-2.2 have been released and validated through analyses of the Cross-Section Evaluation Working Group benchmarks at room temperature. Sitaraman and Rahnemal reported the detailed specifications for two sets of criticals, which were made up of actual power reactor fuel bundles in critical configurations at both room and operating temperatures. This paper describes two sets of boiling water reactor simulated experiments at temperatures representative of cold as well as operating conditions analyzed by the MCNP-4a codes with continuous energy pointwise cross-section data