Artigo Revisado por pares

Design study of National Centralized Tokamak facility for the demonstration of steady state high-β plasma operation

2005; IOP Publishing; Volume: 45; Issue: 12 Linguagem: Inglês

10.1088/0029-5515/45/12/023

ISSN

1741-4326

Autores

H. Tamai, Masato Akiba, H. Azechi, T. Fujita, K. Hamamatsu, Hidetoshi Hashizume, N. Hayashi, Hiroshi Horiike, N. Hosogane, M. Ichimura, K. Ida, T. Imai, S. Ishida, Shintaro Itoh, Yoshihiro Kamada, H. Kawashima, M. Kikuchi, Akihiko Kimura, K. Kizu, H. Kubo, Y. Kudo, Kenichi Kurihara, G. Kurita, M. Kuriyama, K. Masaki, M. Matsukawa, M. Matsuoka, Y. Miura, Y. M. Miura, N. Miya, A. Morioka, K. Nakamura, H. Ninomiya, A. Nishimura, K. Okano, K. Okuno, A. Sagara, M. Sakamoto, S. Sakurai, K. Sato, Ryuichi Shimada, Akihiko Shimizu, T. Suzuki, H. Takahashi, Y. Takase, M. Takechi, Satoru Tanaka, Kunihiko Tsuchiya, Hiroaki Tsutsui, Y. Uesugi, K. Yatsu, N. Yoshida,

Tópico(s)

Fusion materials and technologies

Resumo

Design studies are shown on the National Centralized Tokamak facility, formerly called JT-60SC. The machine design is carried out to investigate the capability for flexibility in aspect ratio and shape controllability for the demonstration of the high-β 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 consistent with sufficient divertor pumping. Evaluations of the plasma performance towards the determination of the machine design are presented.

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