Analysis of RMWR (reduced-moderation water reactor) mockup experiments in FCA using JENDL-3.2 and JENDL-3.3

The critical experiments have been carried out at the FCA to estimate the accuracy of prediction of the core characteristics in the design study of RMWR. A part of the experiments was analyzed by two different conventional deterministic methods: the SRAC code system and a standard calculation code system for a fast reactor, and a probabilistic method, MVP. The C/E values were compared between the JENDL-3.2 and JENDL-3.3 libraries. The calculation overestimates the criticality. The C/E values of the central fission rate ratios become larger in the order, F49/F25, F37/F25, F28/F25. For C28/F25 the calculation agrees with the measured one within twice of the experimental error. For the moderator void effect the calculation underestimates the measurement. When the C/E values are compared between JENDL-3.2 and JENDL-3.3, there is no large C/E discrepancy between JENDL-3.2 and JENDL-3.3 except for the criticality. For the criticality JENDL-3.3 gives larger C/E value than JENDL-3.2. (author)