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Report No.
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Expeimental investigation of thermal margin in tight-lattice rod bundle; Large-scale thermal-hydraulic experiments under high pressure conditions

Tamai, Hidesada

An Innovative Water Reactor for Flexible Fuel Cycle (FLWR) core has a tight-lattice bundle structure and it is operated under low mass velocity and high void fraction conditions, for aiming at the achievement of a high conversion ratio of plutonium mixed oxide (MOX) fuel. These conditions make core cooling difficult, and the FLWR thermal-hydraulic characteristics under such conditions are not known well. The confirmation of thermal-hydraulic characteristics is, therefore, one of the most important R&D requirements for the FLWR design. We investigated the thermal-hydraulic performance of the FLWR core using a test section with 37-rod bundles under high pressure conditions simulating the FLWR operating conditions. The result obtains that the FLWR has sufficient thermal margins for cooling of the core.

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