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Urano, Hajime; Morisaki, Tomohiro*
Purazuma, Kaku Yugo Gakkai-Shi, 88(11), p.669 - 671, 2012/11
JT-60SA is placed on the position for achieving two main objectives. One is a supporting ITER for burning plasma and the other is a complementing ITER for DEMO reactor. Although H-mode operation is a robust operating mode in present diverted tokamaks and is beneficial in improving the edge and core confinement, there are some uncertainties in projecting H-mode operation towards ITER and DEMO reactor. Key issues among these uncertainties are the power required to access and maintain H-mode, the height and width of the H-mode pedestal affecting the overall confinement and plasma performance, the characteristics of the ELMs, and the pedestal control for high beta long pulse operation.
Shoji, Mamoru*; Masuzaki, Suguru*; Kobayashi, Masahiro*; Goto, Motoshi*; Morisaki, Tomohiro*; Yamada, Hiroshi*; Komori, Akio*; Iwamae, Atsushi; Sakaue, Atsushi*; LHD Experimental Group*
Fusion Science and Technology, 58(1), p.208 - 218, 2010/07
Times Cited Count：9 Percentile：52.91(Nuclear Science & Technology)Isayama, Akihiko; Sakakibara, Satoru*; Furukawa, Masaru*; Matsunaga, Go; Yamazaki, Kozo*; Watanabe, Kiyomasa*; Idomura, Yasuhiro; Sakamoto, Yoshiteru; Tanaka, Kenji*; Tamura, Naoki*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 86(6), p.374 - 377, 2010/06
no abstracts in English
Osakabe, Masaki*; Shinohara, Koji; Toi, Kazuo*; Todo, Yasushi*; Hamamatsu, Kiyotaka; Murakami, Sadayoshi*; Yamamoto, Satoshi*; Idomura, Yasuhiro; Sakamoto, Yoshiteru; Tanaka, Kenji*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 85(12), p.839 - 842, 2009/12
no abstracts in English
Idomura, Yasuhiro; Yoshida, Maiko; Yagi, Masatoshi*; Tanaka, Kenji*; Hayashi, Nobuhiko; Sakamoto, Yoshiteru; Tamura, Naoki*; Oyama, Naoyuki; Urano, Hajime; Aiba, Nobuyuki; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 84(12), p.952 - 955, 2008/12
no abstracts in English
Motojima, Osamu*; Yamada, Hiroshi*; Komori, Akio*; Oyabu, Nobuyoshi*; Muto, Takashi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.
Nuclear Fusion, 47(10), p.S668 - S676, 2007/10
Times Cited Count：34 Percentile：73.71(Physics, Fluids & Plasmas)The performance of net-current free heliotron plasmas has been developed by findings of innovative operational scenarios in conjunction with an upgrade of the heating power and the pumping/fuelling capability in the Large Helical Device (LHD). Consequently, the operational regime has been extended, in particular, with regard to high density, long pulse length and high beta. Diversified studies in LHD have elucidated the advantages of net-current free heliotron plasmas. In particular, an internal diffusion barrier (IDB) by a combination of efficient pumping of the local island divertor function and core fuelling by pellet injection has realized a super dense core as high as 5
10
m
, which stimulates an attractive super dense core reactor. Achievements of a volume averaged beta of 4.5% and a discharge duration of 54 min with a total input energy of 1.6 GJ (490 kW on average) are also highlighted. The progress of LHD experiments in these two years is overviewed by highlighting IDB, high-beta and long pulse.
Takenaga, Hidenobu; Morisaki, Tomohiro*
Purazuma, Kaku Yugo Gakkai-Shi, 83(5), p.453 - 459, 2007/05
Status and prospect are reported for studies on an efficient fuelling scenario and on heat and particle control for realizing effective heat removal and particle cycle towards steady state operation in a fusion reactor. First, heat and particle balance expected in a fusion reactor are shown and issues on fuelling and heat/particle control are discussed. There are many common issues in torus plasmas. Next, following issues are highlighted with comparison of studies in tokamak and helical devices, i.e. (1) effect of ice pellet injection, which is considered as a fuelling method in a fusion reactor, on plasma performance, (2) reduction of heat load to the divertor plates for realizing effective heat removal and (3) tritium retention in the first wall, which affects tritium balance.
Motojima, Osamu*; Yamada, Hiroshi*; Komori, Akio*; Oyabu, Nobuyoshi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Muto, Takashi*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 12 Pages, 2007/03
The performance of net-current free Heliotron plasmas has been developed by findings of innovative operational scenarios in conjunction with an upgrade of the heating power and the pumping/fueling capability in the Large Helical Device (LHD). Consequently, the operational regime has been extended, in particular, with regard to high density, long pulse length and high beta. Diversified studies in LHD have elucidated the advantages of net-current free heliotron plasmas. In particular, an Internal Diffusion Barrier (IDB) by combination of efficient pumping of the local island divertor function and core fueling by pellet injection has realized a super dense core as high as 510m, which stimulates an attractive super dense core reactor. Achievements of a volume averaged beta of 4.5 % and a discharge duration of 54-min. with a total input energy of 1.6 GJ (490 kW in average) are also highlighted. The progress of LHD experiments in these two years is overviewed with highlighting IDB, high 
and long pulse.
Watanabe, Kiyomasa*; Suzuki, Yasuhiro*; Yamaguchi, Taiki; Narihara, Kazumichi*; Tanaka, Kenji*; Tokuzawa, Tokihiko*; Yamada, Ichihiro*; Sakakibara, Satoru*; Morisaki, Tomohiro*; Nakajima, Noriyoshi*; et al.
no journal, ,
no abstracts in English
