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Sakamoto, Mizuki*; Ono, Noriyasu*; Asakura, Nobuyuki; Hoshino, Kazuo
Purazuma, Kaku Yugo Gakkai-Shi, 90(8), p.473 - 479, 2014/08
no abstracts in English
Kamada, Yutaka
Nihon Genshiryoku Gakkai-Shi, 47(1), p.45 - 52, 2005/01
no abstracts in English
Asakura, Nobuyuki; Takenaga, Hidenobu; Sakurai, Shinji; Sakasai, Akira; Tamai, Hiroshi; Shimizu, Katsuhiro; Porter, G. D.*
Plasma Physics and Controlled Fusion, 44(10), p.2101 - 2119, 2002/10
Times Cited Count：21 Percentile：54.51(Physics, Fluids & Plasmas)no abstracts in English
Takenaga, Hidenobu; JT-60 Team
Physics of Plasmas, 8(5), p.2217 - 2223, 2001/05
Times Cited Count：44 Percentile：76.96(Physics, Fluids & Plasmas)no abstracts in English
JT-60 Team
JAERI-Research 99-048, 126 Pages, 1999/09
JAERI-Research-99-048.pdf:7.11MB
no abstracts in English
JT-60 Team
JAERI-Research 98-039, 155 Pages, 1998/09
JAERI-Research-98-039.pdf:8.57MB
no abstracts in English
Sakurai, Shinji; Hosogane, Nobuyuki; Masaki, Kei; ; ; *; *; Shimizu, Katsuhiro; Akino, Noboru; Miyo, Yasuhiko; et al.
Fusion Engineering and Design, 39-40, p.371 - 376, 1998/00
Times Cited Count：5 Percentile：44.27(Nuclear Science & Technology)no abstracts in English
; Fukuda, Takeshi; Kamada, Yutaka; Takenaga, Hidenobu; Takizuka, Tomonori; Mori, Masahiro; Fujita, Takaaki; JT-60 Team
Plasma Physics and Controlled Fusion, 40(5), p.713 - 716, 1998/00
Times Cited Count：8 Percentile：29.08(Physics, Fluids & Plasmas)no abstracts in English
Sakasai, Akira
Purazuma, Kaku Yugo Gakkai-Shi, 72(9), p.884 - 893, 1996/09
no abstracts in English
Sakurai, Shinji; Hosogane, Nobuyuki; ; Masaki, Kei; ; *; *; Takahashi, Shoryu*; Saido, Masahiro; Inoue, Masahiko*; et al.
Fusion Technology 1996, 0, 4 Pages, 1996/00
no abstracts in English
Shimada, Michiya
Purazuma, Kaku Yugo Gakkai-Shi, 69(10), p.1146 - 1149, 1993/10
This is an introduction chapter of a series of review papers on divertor research status and issues. The concept and function of divertor are explained. The primary function of divertor is control of impurities, particles and heat. To satisfy the requirements of divertor, the divertor plasma must be cold and dense, significantly radiating and suppressing the backflow of impurity and particle.
Shimada, Michiya
Purazuma, Kaku Yugo Gakkai-Shi, 69(10), p.1155 - 1162, 1993/10
This is a review article on divertor research: present status and issues. In light of importance of divertor research, divertor diagnositics have been significantly developed, and their data have been compared with transport code calculations and divertor database has been accumulated, which has enabled quantitative discussion on thermal and particle transport, radiative cooling and impurity source. However, inter-machine database has not been archived yet. Inter-machine comparison would improve the estimation of divertor characteristics in future devices.
Shimada, Michiya; JT-60 Team
Plasma Physics and Controlled Nuclear Fusion Research 1992, Vol.1, p.57 - 77, 1993/09
Heating experiments have been carried out in JT-60U with plasma currents of up to 4 MA, toroidal fields of up to 4.2 T and a neutral beam heating power of 30 MW. Carbon fibre composite divertor plates with good alignment and bevelled edges provide an excellent power handling capability: no carbon burst has been observed during 5 s heating pulses at 20 MW. An H-mode was observed at the high toroidal field of 4.2 T. A confinement improvement factor of up to 1.6 over L-mode scaling has been obtained during the continuous ELMy phase at 4.2 T, for 2.7 MA and an injection power of 25 MW.
Shimada, Michiya; Sakasai, Akira; Yoshino, Ryuji; Kamada, Yutaka; Kubo, Hirotaka; Sugie, Tatsuo; Tsuji, Shunji; Nakamura, Hiroo; Nemoto, Masahiro; Koide, Yoshihiko; et al.
Journal of Nuclear Materials, 196-198, p.164 - 167, 1992/00
Times Cited Count：11 Percentile：70.41(Materials Science, Multidisciplinary)no abstracts in English
Takizuka, Tomonori
Kaku Yugo Kenkyu, 64(3), p.255 - 280, 1990/09
no abstracts in English
Shimada, Michiya; *; P.Petersen*; P.Riedy*; B.Burley*; T.Petrie*; G.Janeschitz*; M.A.Mahdavi*
Journal of Nuclear Materials, 176-177, p.821 - 824, 1990/00
Times Cited Count：17 Percentile：82.06(Materials Science, Multidisciplinary)no abstracts in English
Nakamura, Hiroo; Ando, Toshiro; Yoshida, Hidetoshi; *; Nishitani, Takeo; Nagashima, Keisuke
JAERI-M 87-167, 29 Pages, 1987/10
no abstracts in English
Sengoku, Seio
JAERI-M 85-102, 102 Pages, 1985/08
no abstracts in English
Kikuchi, Mitsuru; Fasoli, A.*; Takizuka, Tomonori*; Diamond, P.*; Medvedev, S.*; Duan, X.*; Zushi, Hideki*; Furukawa, Masaru*; Kishimoto, Yasuaki*; Wu, Y.*; et al.
no journal, ,
Power and particle control is challenging for standard D-shaped H-mode scenario in tokamak. Possibility of negative triangularity as innovative tokamak concept is discussed by Kikuchi et al. Experimental and numerical studies of negative triangular plasma at CRPP-EPFL success-fully demonstrated improved connement and the weakening of the SOL flow acceleration is implied for the negative triangularity. Recent studies on mechanism of type II and grassy ELM show importance of closure of second stability access to achieve small ELM regimes and also kinetic effects. Medvedev showed that closure of second stability also occurs for negative triangularity. But the MHD stability in negative triangularity is a bit more complicated so that closure of second stability does not imply easy access to small ELM regimes. We discuss critical elements behind.
Takenaga, Hidenobu
no journal, ,
Particle control is important for control of burning plasma, because the plasma density is one of a few controllable parameters in the burning plasma which has a self-sustained system. Heat and particle balance was studied using Slim CS parameters, where tritium is fueled in the main plasma, and deuterium is fueled in both the main plasma and the edge plasma. When the confinement times for the particles fueled in the main and edge plasmas are assumed to be 2 s and 2 ms, respectively, and the divertor pumping fraction is assumed to be 3%, the total deuterium fueling rate is one order of magnitude larger than the tritium fueling rate. Although impurity is accumulated with a peaked density profile, accumulation level is acceptable for Ar. Effect of pellet injection and gas-jet on plasma confinement is discussed and it is suggested that burning plasma control taking account of plasma confinement and a pressure profile is necessary based on the burn simulation experiments.
