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Report No.

Integrated safety research program of high burnup LWR fuels

Nakamura, Takehiko; Sugiyama, Tomoyuki; Nakamura, Jinichi; Nagase, Fumihisa; Fuketa, Toyoshi

In order to obtain fuel performance and integrity data important for the safety evaluation of high burnup UO$$_{2}$$ and mixed oxide (MOX) fuel rods for light water reactors (LWRs), new series of irradiation tests utilizing the Japan Materials Testing Reactor (JMTR), Nuclear Safety Research Reactor (NSRR) and hot laboratories are being proposed. Upgraded JMTR loops for the fuel bundle irradiation under well controlled environment simulating the LWR water condition and single rod capsules for power and flow transients will be prepared in the program. Combination of the JMTR tests with simulated reactivity initiated accident (RIA) tests in the NSRR and loss of coolant accident (LOCA) tests in hot laboratories would serve as the integrated fuel safety research on the advanced UO$$_{2}$$ and MOX fuels at burnups exceeding current license limits, covering from the normal to accident conditions.



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