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Journal Articles

Development of optimum manufacturing technologies of radial plates for the ITER toroidal field coils

Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Abe, Kanako*; Shimizu, Tatsuya; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*; Takayanagi, Tadatoshi*

Fusion Engineering and Design, 82(5-14), p.1473 - 1480, 2007/10

 Times Cited Count:7 Percentile:47.34(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Manufacturing study and trial fabrication of radial plate for ITER toroidal field coil

Abe, Kanako*; Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*

IEEE Transactions on Applied Superconductivity, 16(2), p.807 - 810, 2006/06

 Times Cited Count:11 Percentile:51.53(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Development and test results of a 60kA HTS current lead for fusion application

Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Abe, Kanako*; Nunoya, Yoshihiko; Sugimoto, Makoto; Ando, Toshinari*; Okuno, Kiyoshi; Bono, Takaaki*; Tomioka, Akira*; et al.

Teion Kogaku, 39(3), p.122 - 129, 2004/03

JAERI has been developing a large-capacity high-temperature superconductor (HTS) current lead for fusion application, and succeeded in fabricating and testing a 60kA HTS current lead satisfying ITER requirements. Targets of performance are 1/10 heat leak and 1/3 electric power consumption of cryogenic system compared with a conventional lead. To achieve the target, selection of sheath material of HTS, optimizing the Cu part, reduction of joule heat at joint between HTS and Cu parts, improve of heat transfer between HTS and stainless steel tube. Developed 60kA HTS current lead satisfied the design condition and almost achieved the targets. Adoption of the HTS current lead can reduce 13% electric power consumption of cryogenic system for ITER.

Oral presentation

Development of production technology through the trail fabrication of structures for the toroidal field coil

Nakajima, Hideo; Hamada, Kazuya; Abe, Kanako*; Takano, Katsutoshi; Tsutsumi, Fumiaki; Kawano, Katsumi; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Test fabrication of ITER superconducting coil structure material and its mechanical performance at 4 K

Hamada, Kazuya; Nakajima, Hideo; Abe, Kanako*; Kawano, Katsumi; Takano, Katsutoshi; Tsutsumi, Fumiaki; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Engineering developments for the fabrication of the ITER superconducting coils

Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Hamada, Kazuya; Nunoya, Yoshihiko; Kawano, Katsumi; Nabara, Yoshihiro; Abe, Kanako*; Okuno, Kiyoshi

no journal, , 

no abstracts in English

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