Criticality Benchmarks with a Continuous-Energy Monte Carlo Code MVP and JENDL-3.3

摘要

Criticality benchmark testing of JENDL-3.3 was performed with MVP for many critical experiments in the ICSBEP Handbook: highly enriched uranium (HEU) and low enriched uranium (LEU) fueled solutions, LEU fueled water-moderated lattices, MOX fueled water-moderated lattices and metal fueled small assemblies with hard neutron spectra. The calculations with the preliminary U235 and U238 data for ENDF/B-VII (preVII) are also made for some benchmarks to confirm their performances and to compare with the JENDL-3.3 results. The prediction accuracy of criticality with JENDL-3.3 is satisfactory, within ±0.5%Δk in most cases, except for slightly enriched uranium fueled lattices. The preVII data of U238 with lower thermal capture cross section improves the under prediction of k_(eff) for the slightly enriched lattices, while slight overestimations were observed for the LEU lattices whose U235 enrichment is more than 3wt.%. On the other hand, the preVII data gives excellent results for the metal fueled assemblies compared with JENDL-3.3.