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Journal Articles

ITER activities in Japan

Tsunematsu, Toshihide; Seki, Masahiro; Tsuji, Hiroshi; Okuno, Kiyoshi; Kato, Takashi; Shibanuma, Kiyoshi; Hanada, Masaya; Watanabe, Kazuhiro; Sakamoto, Keishi; Imai, Tsuyoshi; et al.

Fusion Science and Technology, 42(1), p.75 - 93, 2002/07

 Times Cited Count:1 Percentile:10.13(Nuclear Science & Technology)

Japanese contributions to ITER Engineering Design Activity are presented, together with an introduction of the objectives and design of the ITER whose program have been carried out through the international collaboration by EU, Japan, Russian Federation and the USA. New technologies have been produced through the development, fabrication and testing of scalable models in the fields of superconducting magnet, reactor structure with vacuum vessel, high-heat-flux plasma facing component, neutral beam injector, high-power mm-wave generator and so on. As major contributions from Japan, development and testing results of a 13-T, 640-MJ, Nb$$_{3}$$Sn pulsed magnet, a 18-degree sector of vacuum vessel with a height of 15 m and a width of 9 m, CFC armors to CuCrZr cooling tube that withstood 20 MW/m$$^{2}$$, a 31 mA/cm$$^{2}$$ negative ion beam source, a 1-MeV beam-accelerator, a 1-MW 170-GHz gyrotron were described.

Journal Articles

New cryogenic steels and design approach for ITER superconducting magnet system

Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Hada, Kazuhiko; Tada, Eisuke

Proceedings of 10th International Conference on Nuclear Engineering (ICONE 10) (CD-ROM), 8 Pages, 2002/00

The Japan Atomic Energy Research Institute (JAERI) has conducted to develop a new design code for construction and operation/maintenance of the International Thermonuclear Experimental Reactor (ITER), which will be formed as a code case of ASME B&PV Code Section III, division 4, in collaboration with the ASME international. The new design code will also include the several new techniques and materials developed for each components of ITER. This paper describes the new cryogenic steels used in the magnet system and the design approach with taking account of unique features of the ITER superconducting magnets.

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

A Computational method for predicting back-scatter cross section of three dimensional arbitrarily shaped structures

*

Keisan Kogaku Koenkai Rombunshu, 1(1), p.243 - 246, 1996/05

no abstracts in English

Journal Articles

Fusion reactor design and technology programe in Japan

Seki, Yasushi

Fusion Engineering and Design, 25, p.49 - 66, 1994/00

 Times Cited Count:2 Percentile:28.05(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of a large D$$^{-}$$ ion source for the JT-60U negative-ion-based neutral beam injector

Okumura, Yoshikazu; Hanada, Masaya; Inoue, Takashi; Kuriyama, Masaaki; Maeno, Shuichi*; Matsuoka, Mamoru; Miyamoto, Kenji; Mizuno, Makoto; Ohara, Yoshihiro; Suzuki, Satoshi; et al.

Proceedings of 15th IEEE/NPSS Symposium on Fusion Engineering, p.466 - 469, 1993/00

no abstracts in English

Journal Articles

Liquid-metal heat transfer for the first wall and limiter/divertor plates of fusion reactors

M.Z.Hasan*; Kunugi, Tomoaki

Heat Transfer-Minneapolis,1991 (AIChE Symp. Ser. No. 283), p.67 - 73, 1991/00

no abstracts in English

Journal Articles

Design study of FER superconducting magnet system

Yoshida, Kiyoshi; Koizumi, Koichi; Sugimoto, Makoto; Okuno, Kiyoshi; Tada, Eisuke; Tsuji, Hiroshi; Hasegawa, Mitsuru*; Matsuda, Shinzaburo; Shimamoto, Susumi

Proc. of the 11th Int. Conf. on Magnet Technology, p.908 - 913, 1990/00

no abstracts in English

Journal Articles

Design and related experiments of JT-60 divertor coils

; Okubo, Minoru; ; ; ; *; *

Journal of Nuclear Science and Technology, 24(9), p.730 - 741, 1987/09

 Times Cited Count:1 Percentile:19.33(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Magnet Design for JAERI Heavy-Ion Spectrograph

; ; *; *; *

JAERI-M 9358, 20 Pages, 1981/02

JAERI-M-9358.pdf:0.51MB

no abstracts in English

JAEA Reports

Evaluation of INTOR Reactor Size

JAERI-M 8710, 40 Pages, 1980/02

JAERI-M-8710.pdf:1.19MB

no abstracts in English

11 (Records 1-11 displayed on this page)
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