Assessment of Criticality Computational Software for the US Department of Energy Office of Civilian Radioactive Waste Management Applications

摘要

State-of-the-art computational software was evaluated relative to the performance of criticality analyses of facilities and equipment involved in the handling, transport and storage of spent light-water reactor fuel. It was determined that the KENO V.a Monte Carlo program was the most suitable. Of the other programs evaluated, the MONK6.2 code was found to be the leading candidate for the performance of independent, corroborative analyses. The validation of cross-section data from the SCALE system for shipping cask and fuel consolidation applications was reviewed. For current design practices, the data validation is adequate. For new design approaches, such as neutron flux traps or taking credit for fission product absorption, additional validation studies must be performed. 45 refs., 4 figs., 13 tabs. (ERA citation 14:008624)