Outlines and status of safety research on fuels and materials using JMTR

Nakamura, Takehiko ; Nishiyama, Yutaka ; Chimi, Yasuhiro; Hanawa, Satoshi ; Ogiyanagi, Jin ; Nakamura, Jinichi ; Sasajima, Hideo ; Suzuki, Masahide

In parallel to the refurbishment, installation of new tests rigs for fuel and material irradiation research is progressing in the JMTR. The new test program will contribute to solve irradiation related issues on plant aging and high-duty uses of the current LWRs and on development of next-generation reactors. New tests on fuel integrity under simulated abnormal transients and high-duty irradiation conditions are planned in the JMTR. Power ramp tests of new- design fuel rods will also be performed in the first stage of the program, which is expected to start in year 2011 after refurbishment of the JMTR. For the materials irradiation, fracture toughness of reactor vessel steels and IASCC behavior of stainless steels are being studied in addition to basic irradiation behavior of nuclear materials such as hafnium. The irradiation studies would contribute not only to solve the current problems but also to identify possible seeds of troubles and to make proactive responses.