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Kizu, Kaname; Tsuchiya, Katsuhiko; Obana, Tetsuhiro*; Takahata, Kazuya*; Hoshi, Ryo; Hamaguchi, Shinji*; Nunoya, Yoshihiko; Yoshida, Kiyoshi; Matsukawa, Makoto; Yanagi, Nagato*; et al.
Fusion Engineering and Design, 84(2-6), p.1058 - 1062, 2009/06
Times Cited Count:12 Percentile:62.42(Nuclear Science & Technology)The maximum magnetic field and maximum current of EF coils for JT-60SA is 6.2T, 20 kA, respectively. The EF coil conductors are NbTi cable-in-conduit (CIC) conductor with SS316L conduit. In order to confirm the performance of current sharing temperature () tests under coil operational condition was performed. As a results, the degradation of was 0.01-0.08 K indicating that the conductor design and its fabrication method is appropriate. Experimental results were compared with the and by standard plasma operation scenario. It was confirmed that the conductor has margin of 1K.
Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Yanagi, Nagato*; Mito, Toshiyuki*; Imagawa, Shinsaku*; Kizu, Kaname; Tsuchiya, Katsuhiko; Hoshi, Ryo; Yoshida, Kiyoshi
Fusion Engineering and Design, 84(7-11), p.1442 - 1445, 2009/06
Times Cited Count:18 Percentile:74.84(Nuclear Science & Technology)The superconductor test facility in National Institute for Fusion Science (NIFS) has been upgraded in order to test cable-in-conduit (CIC) conductors for the JT-60SA equilibrium field (EF) coil. In the test facility, supercritical helium (SHe) lines were newly assembled with transfer tubes and a heat exchanger. The CIC conductor was covered with a thermal insulation vessel filled with gas helium at atmospheric pressure. The temperature of the conductor was varied using a film heater attached to an inlet pipe. The Ic and Tcs measurements of the prototype CIC conductor have successfully been carried out with the upgraded test facility. In the measurements, the conductor temperature was precisely controlled.
Takahashi, Yoshihiro*; Fugane, Masaru*; Imagawa, Ryo*; Owaki, Akihiro*; Hirao, Toshio; Onoda, Shinobu; Oshima, Takeshi
JAEA-Review 2008-055, JAEA Takasaki Annual Report 2007, P. 7, 2008/11
no abstracts in English
Onishi, Kazunori*; Takahashi, Yoshihiro*; Nakajima, Yasuhito*; Nagasawa, Takaharu*; Fugane, Masaru; Imagawa, Ryo*; Nomoto, Keisuke*; Hirao, Toshio; Onoda, Shinobu; Oshima, Takeshi
no journal, ,
no abstracts in English
Fugane, Masaru; Takahashi, Yoshihiro*; Nakajima, Yasuhito*; Nagasawa, Takaharu*; Imagawa, Ryo*; Nomoto, Keisuke*; Onishi, Kazunori*; Hirao, Toshio; Onoda, Shinobu; Oshima, Takeshi
no journal, ,
no abstracts in English
Onoda, Shinobu; Fugane, Masaru; Hirao, Toshio; Oshima, Takeshi; Takahashi, Yoshihiro*; Imagawa, Ryo*; Onishi, Kazunori*
no journal, ,
no abstracts in English
Kizu, Kaname; Tsuchiya, Katsuhiko; Hoshi, Ryo; Yoshida, Kiyoshi; Matsukawa, Makoto; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Yanagi, Nagato*; Imagawa, Shinsaku*; et al.
no journal, ,
The maximum magnetic field and maximum current of EF coils for JT-60SA is 6.2 T, 20 kA, respectively. The EF coil conductors are NbTi cable-in-conduit (CIC) conductor with SS316L conduit. In order to confirm the performance of current sharing temperature (Tcs) tests under coil operational condition was performed. As a results, the degradation of Tcs was 0.02-0.07 K indicating that the conductor design and its fabrication method is appropriate.
Imagawa, Ryo*; Fugane, Masaru*; Takahashi, Yoshihiro*; Hirao, Toshio; Onoda, Shinobu; Oshima, Takeshi
no journal, ,
no abstracts in English
Takahashi, Yoshihiro*; Fugane, Masaru*; Imagawa, Ryo*; Owaki, Akihiro*; Hirao, Toshio; Onoda, Shinobu; Oshima, Takeshi
no journal, ,
no abstracts in English
Takahashi, Yoshihiro*; Imagawa, Ryo*; Owaki, Akihiro*; Takeyasu, Hidenori*; Hirao, Toshio; Onoda, Shinobu; Makino, Takahiro; Oshima, Takeshi
no journal, ,
no abstracts in English