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Yamamoto, Tomohiko; Imai, Yoshiyuki; Marufuji, Takato; Akasaka, Naoaki; Yan, X.; Otani, Akihito*; Kai, Satoru*; Mori, Takashi*; Uoji, Tomoki*; Ueno, Tomohiro*; et al.
Proceedings of the ASME 2025 Pressure Vessels & Piping Conference (PVP2025) (Internet), 7 Pages, 2025/07
Ninomiya, Hiromasa; Akiba, Masato; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Inoue, Nobuyuki; et al.
Journal of the Korean Physical Society, 49, p.S428 - S432, 2006/12
To contribute DEMO and ITER, the design to modify the present JT-60U into superconducting coil machine, named National Centralized Tokamak (NCT), is being progressed under nationwide collaborations in Japan. Mission, design and strategy of this NCT program is summarized.
Kikuchi, Mitsuru; Tamai, Hiroshi; Matsukawa, Makoto; Fujita, Takaaki; Takase, Yuichi*; Sakurai, Shinji; Kizu, Kaname; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; et al.
Nuclear Fusion, 46(3), p.S29 - S38, 2006/03
Times Cited Count：13 Percentile：39.50(Physics, Fluids & Plasmas)The National Centralized Tokamak (NCT) facility program is a domestic research program for advanced tokamak research to succeed JT-60U incorporating Japanese university accomplishments. The mission of NCT is to establish high beta steady-state operation for DEMO and to contribute to ITER. The machine flexibility and mobility is pursued in aspect ratio and shape controllability, feedback control of resistive wall modes, wide current and pressure profile control capability for the demonstration of the high-b steady state.
Tsuchiya, Katsuhiko; Akiba, Masato; Azechi, Hiroshi*; Fujii, Tsuneyuki; Fujita, Takaaki; Fujiwara, Masami*; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; et al.
Fusion Engineering and Design, 81(8-14), p.1599 - 1605, 2006/02
Times Cited Count：1 Percentile：9.37(Nuclear Science & Technology)no abstracts in English
plasma operationTamai, Hiroshi; Akiba, Masato; Azechi, Hiroshi*; Fujita, Takaaki; Hamamatsu, Kiyotaka; Hashizume, Hidetoshi*; Hayashi, Nobuhiko; Horiike, Hiroshi*; Hosogane, Nobuyuki; Ichimura, Makoto*; et al.
Nuclear Fusion, 45(12), p.1676 - 1683, 2005/12
Times Cited Count：15 Percentile：43.68(Physics, Fluids & Plasmas)Design studies are shown on the National Centralized Tokamak facility. The machine design is carried out to investigate the capability for the flexibility in aspect ratio and shape controllability for the demonstration of the high-beta steady state operation with nation-wide collaboration, in parallel with ITER towards DEMO. Two designs are proposed and assessed with respect to the physics requirements such as confinement, stability, current drive, divertor, and energetic particle confinement. The operation range in the aspect ratio and the plasma shape is widely enhanced in consistent with the sufficient divertor pumping. Evaluations of the plasma performance towards the determination of machine design are presented.
Kawamura, Hiroshi; Ishitsuka, Etsuo; Tsuchiya, Kunihiko; Nakamichi, Masaru; Uchida, Munenori*; Yamada, Hirokazu*; Nakamura, Kazuyuki; Ito, Haruhiko; Nakazawa, Tetsuya; Takahashi, Heishichiro*; et al.
Nuclear Fusion, 43(8), p.675 - 680, 2003/08
Times Cited Count：33 Percentile：66.93(Physics, Fluids & Plasmas)no abstracts in English
Ninomiya, Hiromasa; Kitsunezaki, Akio; Shimizu, Masatsugu; Kuriyama, Masaaki; JT-60 Team; Kimura, Haruyuki; Kawashima, Hisato; Tsuzuki, Kazuhiro; Sato, Masayasu; Isei, Nobuaki; et al.
Fusion Science and Technology, 42(1), p.7 - 31, 2002/07
Times Cited Count：13 Percentile：21.21(Nuclear Science & Technology)In order to establish scientific basis for the sustainment of highly integrated performance required in the advanced steady-state operation, JT-60U has been optimizing the discharge control scenarios of improved confinement plasmas and expanding the operation regions. Promising results toward the steady-state tokamak were obtained. The detail of such results is reported. JFT-2M has performed advanced and basic research for the development of high performance tokamak plasma as well as the structural material for a fusion reactor. The toroidal ripple reduction with ferritic steel plates outside the vacuum vessel was successfully demonstrated. No adverse effects were observed in the pre-testing on compatibility between ferritic steel plates, covering ~20% of the inside wall of the vacuum vessel, and plasma. The results of TRIAM-1M is also reported.
Yoneda, Yoshihiro*; Takahara, Hiroyuki*; Nakamura, Naoaki*; Akiyama, Shinsuke*; Moriya, Toshifumi*; Negi, Tateyuki*
PNC TJ1380 98-001, 624 Pages, 1998/03
no abstracts in English
Yoneda, Yoshihiro*; Takahara, Hiroyuki*; Nakamura, Naoaki*; Akiyama, Shinsuke*; Moriya, Toshifumi*; Negi, Tateyuki*
PNC TJ1380 97-002, 157 Pages, 1997/03
None
Yoneda, Yoshihiro*; Takahara, Hiroyuki*; Nakamura, Naoaki*; Akiyama, Shinsuke*; Moriya, Toshifumi*; Negi, Tateyuki*
PNC TJ1380 97-001, 1338 Pages, 1997/03
None
Yokoi, Koichi*; Noguchi, Yoshifumi*; Morita, Masaya*; Nakamura, Naoaki*; Takahara, Hiroyuki*; Moriya, Toshifumi*
PNC TJ1380 95-004, 235 Pages, 1995/03
None
Cho, Hisashi*; Yokoi, Koichi*; Noguchi, Yoshifumi*; Morita, Masaya*; Nakamura, Naoaki*; Takahara, Hiroyuki*; Moriya, Toshifumi*
PNC TJ1380 94-001, 1308 Pages, 1994/03
None
Cho, Hisashi*; Noguchi, Yoshifumi*; Morita, Masaya*; Nakamura, Naoaki*; Iwasaki, Hiroshi*; Hotta, Masakuni*; Hokari, Toshiyuki*
PNC TJ1380 91-001, 470 Pages, 1991/05
None
Hamabe, Shuji*; Cho, Hisashi*; Yokoi, Koichi*; Noguchi, Yoshifumi*; Iijima, Akio*; Morita, Masaya*; Nakamura, Naoaki*
PNC TJ4380 90-002, 463 Pages, 1990/05
None
Yamamoto, Tomohiko; Imai, Yoshiyuki; Marufuji, Takato; Akasaka, Naoaki; Yan, X.; Otani, Akihito*; Kai, Satoru*; Mori, Takashi*; Uoji, Tomoki*; Ueno, Tomohiro*; et al.
no journal, ,
no abstracts in English
