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Journal Articles

Effects of grain size on ultrasonic attenuation in type 316L stainless steel

Wan, T.; Naoe, Takashi; Wakui, Takashi; Futakawa, Masatoshi; Obayashi, Hironari; Sasa, Toshinobu

Materials, 10(7), p.753_1 - 753_17, 2017/07

 Times Cited Count:13 Percentile:59.14(Chemistry, Physical)

Journal Articles

Corrosion of the stainless steel in the zeolite containing diluted artificial seawater under $$gamma$$-ray irradiation

Kato, Chiaki; Sato, Tomonori; Nakano, Junichi; Ueno, Fumiyoshi; Yamagishi, Isao

Proceedings of 2014 Nuclear Plant Chemistry Conference (NPC 2014) (USB Flash Drive), 9 Pages, 2014/10

As a part of consideration for long-term storage of spent zeolite adsorption vessels in the Fukushima Daiichi Nuclear Power Station, corrosion of vessel material in the spent zeolite adsorption vessel is one of important issue. We performed electrochemical tests of stainless steel (type 316L) in the zeolite containing artificial seawater under $$gamma$$-ray irradiation. Steady spontaneous potential (Esp) and pitting potential (VC), of type 316L was measurement. $$^{60}$$Co $$gamma$$-rays source was used under irradiation. Dose rate of $$gamma$$-ray irradiation was controlled for 5 kGy/h and 400 Gy/h. In anode polarization curves, there was no clear difference under irradiation and non-irradiation. The corrosion potential of type 316L increased with increasing time after $$gamma$$-ray irradiation. The Esp was shifted to nobler by $$gamma$$-rays irradiation, while increasing Esp was suppressed by contacted with zeolite.

Journal Articles

Evaluation of in-pile and out-of-pile stress relaxation in 316L stainless steel under uniaxial loading

Kaji, Yoshiyuki; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Yonekawa, Minoru; Nakano, Junichi; Tsuji, Hirokazu; Nakajima, Hajime

Journal of Nuclear Materials, 307-311(Part1), p.331 - 334, 2002/12

 Times Cited Count:4 Percentile:30.46(Materials Science, Multidisciplinary)

Irradiation assisted stress corrosion cracking (IASCC) caused by simultaneous effects of neutron irradiation and high temperature water environments has been pointed out as one of the major concerns of in-core structural materials not only for the light water reactors (LWRs) but also for the water-cooled fusion reactor. It is necessary to evaluate precisely stress condition under irradiation environment, because stress is one of key factors on IASCC. Stress relaxation of tensile type specimens under fast neutron irradiation at 288$$^{circ}$$C has been studied for type 316L stainless steel in Japan Materials Testing Reactor (JMTR). This paper describes the in-pile and out-of-pile stress-relaxation test results of tensile type specimens for type 316L stainless steel as compared with the literature data by Foster, which were mainly obtained by bent beam specimens. Moreover these experimental results were compared with the analytical ones by using Nakagawa's model.

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