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Kubo, Shinji
Suiso Enerugi Shisutemu, 48(2), p.126 - 132, 2023/06
no abstracts in English
Yamashita, Shinichiro
Nihon Genshiryoku Gakkai-Shi ATOMO
, 65(4), p.233 - 237, 2023/04
In the wake of the accident at the Fukushima Daiichi Nuclear Power Plant (NPP) of TEPCO due to the Great East Japan Earthquake in 2011, interest in the early implementation of accident tolerant fuel (ATF) not only for many existing NPPs but also for future NPPs, which is expected to dramatically improve the safety of light water reactors, has increased globally, and research and development is currently underway in many countries around the world. In this article, an overview of domestic ATF technology development that has been carried out with the support of the Ministry of Economy, Trade and Industry since 2015, will be introduced.
Soma, Yasutaka; Kato, Chiaki; Ueno, Fumiyoshi
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Vol.2, p.509 - 521, 2018/00
In-situ electrochemical measurement within crevice of stainless steel in 288
C water has been conducted to analyze crevice water chemistry. Small sensors (
250
m) measured local solution electrical conductivity, 
, polarization resistance, and electrochemical corrosion potential. Real-time response of the as functions of bulk water conductivity, dissolved oxygen (DO) concentration has been quantitatively analyzed. The effect of geometrical factors on the crevice environment was also studied. The differ more than an order of magnitude depending on the oxygen potential inside the crevice. The increased by small amount of bulk DO (e.g. 30 ppb). Maximum was observed with DO of 32000 ppb and became more than 100 times higher than that of bulk water. Crevice geometry affected significantly on the water chemistry inside.
Department of HTTR Project; Department of Advanced Nuclear Heat Technology
JAERI-Review 2004-026, 206 Pages, 2004/12
JAERI-Review-2004-026.pdf:14.16MB
no abstracts in English
Shiina, Yasuaki; Takizuka, Takakazu; Kasahara, Seiji
Nihon Genshiryoku Gakkai-Shi, 46(12), p.862 - 863, 2004/12
no abstracts in English
Miwa, Yukio; Tsukada, Takashi
Proceedings of Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2003, p.301 - 306, 2003/00
Local composition change at grain boundaries due to radiation-induced segregation (RIS) followed by loss of corrosion resistance is considered to be a key mechanism on irradiation-assisted stress corrosion cracking (IASCC). However it is not clear that the local composition change induces the loss of corrosion resistance at grain boundaries, because RIS results in not only depletion of Cr but also enrichment of Ni and Si. This chemical composition change is different from that of thermally-sensitized stainless steels. In this study, experimental alloys were manufactured simulating the composition at grain boundaries of irradiated type 304 stainless steel and corrosion behavior of the experimental alloys was examined by weight loss measurement in 573 K water and anode polarization measurement in 1N sulfuric acid and 1mol/l sodium sulfate at 303 K. Following results were obtained: (1) In oxygenated water (DO=10ppm) at 573 K, weight loss increased with decreasing the concentration of Cr and did not depend on the concentration of Ni and Si. (2) Results of anode polarization measurements showed that alloys contained lower Cr and higher Ni and Si concentration exhibited lower corrosion potential in oxygenated, lower pH solution. In de-aerated solutions both sulfuric acid and sodium sulfate, however, there was a little influence of chemical composition on the corrosion potential.
Ishida, Toshihisa; Imayoshi, Sho*; Yoritsune, Tsutomu; Nunokaya, Hiroshi*; Ochiai, Masaaki; Ishizaka, Yuichi*
Journal of Nuclear Science and Technology, 38(7), p.557 - 570, 2001/07
Times Cited Count：18 Percentile：76.38(Nuclear Science & Technology)no abstracts in English
Kusunoki, Tsuyoshi; Ito, Toshio*; Nariai, Hideki*
Nihon Kikai Gakkai 2000-Nendo Nenji Taikai Koen Rombunshu, p.645 - 646, 2000/08
no abstracts in English
*; Fujiwara, Masayuki*
JNC TJ8430 2000-001, 55 Pages, 2000/03
JNC-TJ8430-2000-001.pdf:4.82MB
no abstracts in English
Tsukada, Takashi; Miwa, Yukio; Tsuji, Hirokazu; Nakajima, Hajime
Journal of Nuclear Materials, 258-263, p.1669 - 1674, 1998/00
Times Cited Count：3 Percentile：31.81(Materials Science, Multidisciplinary)no abstracts in English
Hino, Ryutaro; ; Sekita, Kenji; Haga, Katsuhiro; *
JAERI-Research 97-064, 48 Pages, 1997/09
JAERI-Research-97-064.pdf:1.92MB
no abstracts in English
Hino, Ryutaro; ; ; Haga, Katsuhiro; *;
JAERI-Tech 95-049, 20 Pages, 1995/11
no abstracts in English
Hino, Ryutaro; Suzuki, Kunihiro; Haga, Katsuhiro; Nekoya, Shinichi; Fukaya, Kiyoshi; Shimizu, Saburo; Onuki, Kaoru; Takada, Shoji; Mogi, Haruyoshi; Sudo, Yukio
JAERI-Review 95-016, 115 Pages, 1995/10
no abstracts in English
Hino, Ryutaro; ; ; Haga, Katsuhiro; ; *
JAERI-Research 95-057, 42 Pages, 1995/08
JAERI-Research-95-057.pdf:1.48MB
no abstracts in English
E.Achenbach*
JAERI-Review 95-008, 98 Pages, 1995/06
JAERI-Review-95-008.pdf:3.14MB
no abstracts in English
Hino, Ryutaro;
Nihon Genshiryoku Gakkai-Shi, 37(11), p.1042 - 1049, 1995/00
Times Cited Count：2 Percentile：28.04(Nuclear Science & Technology)no abstracts in English
Hino, Ryutaro;
Nihon Genshiryoku Gakkai-Shi, 35(6), p.546 - 548, 1993/06
Times Cited Count：0 Percentile：0.49(Nuclear Science & Technology)no abstracts in English
Tsukada, Takashi; Shiba, Kiyoyuki; G.E.C.Bell*; Nakajima, Hajime
Corrosion 92, p.104-1 - 104-14, 1992/00
no abstracts in English
Kiuchi, Kiyoshi; *; *;
Proc. of the Int. Symp. on Material Chemistry in Nuclear Environment, p.65 - 78, 1992/00
no abstracts in English
JAERI-M 90-089, 70 Pages, 1990/06
no abstracts in English
