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Journal Articles

ITER nuclear components, preparing for the construction and R&D results

Ioki, Kimihiro*; Akiba, Masato; Barabaschi, P.*; Barabash, V.*; Chiocchio, S.*; Daenner, W.*; Elio, F.*; Enoeda, Mikio; Ezato, Koichiro; Federici, G.*; et al.

Journal of Nuclear Materials, 329-333(1), p.31 - 38, 2004/08

 Times Cited Count:13 Percentile:66.18(Materials Science, Multidisciplinary)

The preparation of the procurement specifications is being progressed for key components. Progress has been made in the preparation of the procurement specifications for key nuclear components of ITER. Detailed design of the vacuum vessel (VV) and in-vessel components is being performed to consider fabrication methods and non-destructive tests (NDT). R&D activities are being carried out on vacuum vessel UT inspection with waves launched at an angle of 20 or 30 degree, on flow distribution tests of a two-channel model, on fabrication and testing of FW mockups and panels, on the blanket flexible support as a complete system including the housing, on the blanket co-axial pipe connection with guard vacuum for leak detection, and on divertor vertical target prototypes. The results give confidence in the validity of the design and identify possibilities of attractive alternate fabrication methods.

JAEA Reports

Development of fabrication technology for ITER vacuum vessel

Nakahira, Masataka; Shibanuma, Kiyoshi; Kajiura, Soji*; Shibui, Masanao*; Koizumi, Koichi; Takeda, Nobukazu; Kakudate, Satoshi; Taguchi, Ko*; Oka, Kiyoshi; Obara, Kenjiro; et al.

JAERI-Tech 2002-029, 27 Pages, 2002/03

JAERI-Tech-2002-029.pdf:2.04MB

The ITER vacuum vessel (VV) R&D has progressed with the international collaborative efforts by the Japan, Russia and US Parties during the Engineering Design Activities (EDA). Fabrication and testing of a full-scale VV sector model and a port extension have yielded critical information on the fabrication and assembly technologies of the vacuum vessel, magnitude of welding distortions, dimensional accuracy and achievable tolerances during sector fabrication and field assembly. In particular, the dimensional tolerances of $$pm$$3 mm for VV sector fabrication and $$pm$$10 mm for VV sector field assembly have been achieved and satisfied the requirements of $$pm$$5 mm and $$pm$$20 mm, respectively. Also, the basic feasibility of the remote welding robot has been demonstrated. This report presents detailed fabrication and assembly technologies such as welding technology applicable to the thick wall without large distortion, field joint welding technology between sectors and remote welding technology through the VV R&D project.

Journal Articles

Development and performance evaluation of 13T-46kA Nb$$_{3}$$Al conductor

Koizumi, Norikiyo; Ando, Toshinari; Takahashi, Yoshikazu; Matsui, Kunihiro; Nakajima, Hideo; Tsuchiya, Yoshinori; Kikuchi, Kenji; Nunoya, Yoshihiko; Kato, Takashi; Isono, Takaaki; et al.

Senshin A15-gata Kagobutsu Chodendo Senzai Shimpojiumu Rombunshu, p.5 - 9, 2000/00

no abstracts in English

Journal Articles

Development of remote handling tools and equipment

Nakahira, Masataka; Oka, Kiyoshi; *; *; *; Oda, Yasushi*; Kajiura, Soji*; Yamazaki, Seiichiro*; *

Purazuma, Kaku Yugo Gakkai-Shi, 73(1), p.54 - 68, 1997/01

no abstracts in English

Journal Articles

Present activities preparation of a Japanese draft of structural design guidelines for the experimental fusion reactor

Miya, Kenzo*; ; Takatsu, Hideyuki; Hada, Kazuhiko; Koizumi, Koichi; Jitsukawa, Shiro; ; Okawa, Yoshinao; Shimakawa, T.*; Aoto, Kazumi*; et al.

Fusion Engineering and Design, 31, p.145 - 165, 1996/00

 Times Cited Count:3 Percentile:33.71(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Japanese contributions to containment structure, assembly and maintenance and reactor building for ITER

Shibanuma, Kiyoshi; *; *; *; Okawa, Yoshinao; *; Tada, Eisuke; Koizumi, Koichi; *; Nishio, Satoshi; et al.

JAERI-M 91-080, 357 Pages, 1991/06

JAERI-M-91-080.pdf:12.46MB

no abstracts in English

JAEA Reports

Shielding design of reactor core region in Fusion Experimental Reactor

*; Takatsu, Hideyuki; Kuroda, Toshimasa*; Seki, Yasushi; Kajiura, Soji*; *; *; *

JAERI-M 91-017, 69 Pages, 1991/02

JAERI-M-91-017.pdf:2.26MB

no abstracts in English

Journal Articles

Design and fabrication of the JT-60 graphite wall

Yamamoto, Masahiro; Shimizu, Masatsugu; Arai, Takashi; Nakamura, Hiroo; Ando, Toshiro; Ogiwara, Norio; Takatsu, Hideyuki; *; Okubo, Minoru; ; et al.

Nihon Genshiryoku Gakkai-Shi, 29(7), p.634 - 641, 1987/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

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