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Journal Articles

Investigation of compatibility of low activation ferritic steel with high performance plasma by full covering of inside vacuum vessel wall on JFT-2M

Tsuzuki, Kazuhiro; Shinohara, Koji; Kamiya, Kensaku; Kawashima, Hisato; Sato, Masayasu; Kurita, Genichi; Bakhtiari, M.; Ogawa, Hiroaki; Hoshino, Katsumichi; Kasai, Satoshi; et al.

Journal of Nuclear Materials, 329-333(1), p.721 - 725, 2004/08

 Times Cited Count:7 Percentile:43.42(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

High performance tokamak experiments with a ferritic steel wall on JFT-2M

Tsuzuki, Kazuhiro; Kimura, Haruyuki; Kawashima, Hisato; Sato, Masayasu; Kamiya, Kensaku; Shinohara, Koji; Ogawa, Hiroaki; Hoshino, Katsumichi; Bakhtiari, M.; Kasai, Satoshi; et al.

Nuclear Fusion, 43(10), p.1288 - 1293, 2003/10

 Times Cited Count:40 Percentile:72.92(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Effects of triple ion beams in ferritic/martensitic steel on swelling behavior

Wakai, Eiichi; Sawai, Tomotsugu; Furuya, Kazuyuki; Naito, Akira; Aruga, Takeo; Kikuchi, Kenji; Yamashita, Shinichiro*; Onuki, Somei*; Yamamoto, Shunya; Naramoto, Hiroshi; et al.

Journal of Nuclear Materials, 307-311(Part.1), p.278 - 282, 2002/12

 Times Cited Count:66 Percentile:95.42(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Characterization of 316L(N)-IG SS joint produced by hot isostatic pressing technique

Nakano, Junichi; Miwa, Yukio; Tsukada, Takashi; Kikuchi, Masahiko; Kita, Satoshi; Nemoto, Yoshiyuki; Tsuji, Hirokazu; Jitsukawa, Shiro

Journal of Nuclear Materials, 307-311(Part2), p.1568 - 1572, 2002/12

 Times Cited Count:13 Percentile:61.85(Materials Science, Multidisciplinary)

Type 316LN stainless steel of the international thermonuclear experimental reactor (ITER) Grade (316LN-IG SS) is being considered for the first wall/ blanket component. Hot isostatic pressing (HIP) technique is expected for the fabrication of module. To evaluate the integrity and susceptibility to stress corrosion cracking (SCC) of HIPed 316LN-IG SS, tensile tests in vacuum and slow strain rate tests (SSRT) in high temperature water were performed. Specimen with the HIPed joint shows no deterioration of the tensile strength and susceptibility to SCC in oxygenated water. Thermally sensitized specimen with the HIPed joint was low susceptible to SCC in creviced environment. It is concluded that the strength at joint location is as high as that at the base alloy and the joint interface appears integrity.

JAEA Reports

Conceptual design of solid breeder blanket system cooled by supercritical water

Enoeda, Mikio; Ohara, Yoshihiro; Akiba, Masato; Sato, Satoshi; Hatano, Toshihisa; Kosaku, Yasuo; Kuroda, Toshimasa*; Kikuchi, Shigeto*; Yanagi, Yoshihiko*; Konishi, Satoshi; et al.

JAERI-Tech 2001-078, 120 Pages, 2001/12

JAERI-Tech-2001-078.pdf:8.3MB

This report is a summary of the design works, which was discussed in the design workshop held in 2000 for the demonstration (DEMO) blanket aimed to strengthen the commercial competitiveness and technical feasibility simultaneously. The DEMO blanket must supply the feasibility and experience of the total design of the power plant and the materials. This conceptual design study was performed to determine the updated strategy and goal of the R&D of the DEMO blanket which applies the supercritical water cooling proposed in A-SSTR, taking into account the recent progress of the plasma research and reactor engineering technology.

Journal Articles

Error field analysis of steady state tokamak reactor with ferromagnetic (F82H) blanket

; Mori, Masahiro; Kikuchi, Mitsuru; Ninomiya, Hiromasa; Jitsukawa, Shiro; Ito, Takao; Kuriyama, Masaaki;

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), p.1214 - 1217, 1995/06

no abstracts in English

Journal Articles

Cleaning of shielding window of hot cell

Kikuchi, Teruo; Kurobane, Shiro; Ito, Tadaharu

Dekomisshoningu Giho, (5), p.60 - 66, 1992/06

no abstracts in English

Journal Articles

H-mode experiments with outer and lower divertors in JT-60

Nakamura, Hiroo; Tsuji, Shunji; ; Ozeki, Takahisa; Ishida, Shinichi; Azumi, Masafumi; Akiba, Masato; Ando, Toshiro; Fujii, Tsuneyuki; Fukuda, Takeshi; et al.

Nuclear Fusion, 30(2), p.235 - 250, 1990/02

 Times Cited Count:17 Percentile:53.98(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Results of the H-mode experiments with outer and lower divertors

Nakamura, Hiroo; Tsuji, Shunji; ; Ozeki, Takahisa; Ishida, Shinichi; Azumi, Masafumi; Akiba, Masato; Ando, Toshiro; Fujii, Tsuneyuki; Fukuda, Takeshi; et al.

JAERI-M 89-106, 52 Pages, 1989/08

JAERI-M-89-106.pdf:1.27MB

no abstracts in English

Journal Articles

JT-60U system design

Matsukawa, Makoto; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; Kikuchi, Mitsuru; ; Koizumi, Koichi; ; et al.

Fusion Technology 1988, p.293 - 297, 1989/00

no abstracts in English

Journal Articles

JT-60 upgrade program

Kikuchi, Mitsuru; Ando, Toshiro; Araki, Masanori; ; Horiike, Hiroshi; Ikeda, Yoshitaka; ; Koizumi, Koichi; Matsukawa, Makoto; ; et al.

Fusion Technology 1988, p.287 - 292, 1989/00

no abstracts in English

JAEA Reports

Irradiation-induced dimensional changes of fuel compacts and graphite sleeves of OGL-1 fuel assemblies

Hayashi, Kimio; Minato, Kazuo; Kobayashi, Fumiaki; Tobita, Tsutomu; Kikuchi, Teruo; Kurobane, Shiro; ; Fukuda, Kosaku

JAERI-M 88-107, 111 Pages, 1988/06

JAERI-M-88-107.pdf:2.27MB

no abstracts in English

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