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Research for thermal-hydraulic performance in tight-lattice fuel assembly, 1; Outline of research program

Akimoto, Hajime; Tamai, Hidesada; Onuki, Akira; Takase, Kazuyuki

A thermal-hydraulic research program for Reduced-Moderation Water Reactor (RMWR) has been performed since 2002. The RMWR has a tight-lattice core to attain the breeding of nuclear fuel for the effective use of Plutonium in a light-water reactor system. In this R&D program, large-scale thermal-hydraulic tests, several model experiments and development of advanced numerical analysis codes are being carried out to confirm the cooling performance in tight-lattice fuel assembly of the RMWR. In this paper, outline of the research program is described as well as the latest results of critical power measurement in the large-scale thermal-hydraulic tests and model experiments, which simulates the tight-lattice core of the RMWR.

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