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RIA- and LOCA-simulating experiments on high burnup LWR fuels

高燃焼度軽水炉燃料のRIA及びLOCA模擬実験

更田 豊志; 永瀬 文久; 杉山 智之

Fuketa, Toyoshi; Nagase, Fumihisa; Sugiyama, Tomoyuki

軽水炉燃料の安全規制に必要なデータを提供するため、原研では、異常運転時及び反応度事故(RIA)や冷却材喪失事故(LOCA)といった想定された事故時の燃料挙動について研究を行っている。高燃焼度燃料に対する一連のRIA模擬実験を原子炉安全性研究炉(NSRR)で実施しており、LOCA時の燃料挙動については被覆管急冷破断試験及び被覆管の酸化速度や機械特性に関する個別効果試験を含む広汎な研究を行っている。

To provide a data base for the regulatory guide of light water reactors, behaviors of reactor fuels during off-normal and postulated accident conditions such as reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA) are being studied at the Japan Atomic Energy Research Institute (JAERI). A series of RIA-simulating experiments with high burnup fuel rods is being performed by using pulse-irradiation capability of the Nuclear Safety Research Reactor (NSRR). Fuel behaviors during a LOCA are also examined in an extensive program comprising of integral thermal shock tests and separate tests for oxidation rate and mechanical properties of fuel cladding.

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