Analysis of innovative water reactor for flexible fuel cycle in FCA using JENDL-3.3

To obtain experimental data and to evaluate the prediction accuracy for the core characteristics in the design study of Innovative Water Reactor for Flexible fuel cycle (FLWR), critical experiments were carried out using a series of mock-up cores at FCA. Three mockup cores with different void fractions of the moderator were constructed to obtain experimental data in wide range of neutron spectra. Major items of the experiment are criticality, reaction rate ratios, moderator void reactivity worth and the Doppler effect. Conventional deterministic calculation systems were used to analyze the experiment with the use of the JENDL-3.2 and JENDL-3.3 libraries. The ratios of calculated and experimental (C/E) values were compared between both the JENDL libraries. The current analysis method showed good prediction accuracy in most of the experiments and no significant differences were observed in the C/E values between the libraries in this study. (author)