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Fuketa, Toyoshi; Sugiyama, Tomoyuki; Nakamura, Takehiko; Sasajima, Hideo; Nagase, Fumihisa
NUREG/CP-0185, p.161 - 172, 2004/00
To provide a data base for the regulatory guide of light water reactors, behavior of reactor fuels during off-normal and postulated accident conditions such as reactivity-initiated accident (RIA) is being studied in the Nuclear Safety Research Reactor (NSRR) program of the Japan Atomic Energy Research Institute (JAERI). A series of experiments with high burnup fuel rods is being performed by using pulse irradiation capability of the NSRR. This paper presents recent results obtained from the NSRR power burst experiments with irradiated PWR fuels with ZIRLO and MDA claddings, and discusses effects of pellet expansion as PCMI (Pellet-Cladding Mechanical Interaction) loading and cladding embrittlement primarily due to hydrogen absorption. Separate-effect studies including tube-burst and ring-tensile tests on Zircaloy cladding also described.
Nagase, Fumihisa; Sugano, Mitsuteru*; Ozawa, Masaaki*; Komatsu, Kazushi*; Furuta, Teruo*
JAERI-Research 2001-008, 61 Pages, 2001/03
no abstracts in English
Int. J. Supercomputer Appl., 5(3), p.46 - 62, 1991/00
Times Cited Count:1 Percentile:51.29(Computer Science, Hardware & Architecture)no abstracts in English