Overview of the National Centralized Tokamak programme

Authors :: Kikuchi, M.
Tamai, H.
Matsukawa, M.
Fujita, T.
Takase, Y.
Sakurai, S.
Kizu, K.
Tsuchiya, K.
Kurita, G.
Morioka, A.
Hayashi, N.
Miura, Y.
Itoh, S.
Bialek, J.
Navratil, G.
Ikeda, Y.
Fujii, T.
Kurihara, K.
Kubo, H.
Kamada, Y.
Miya, N.
Suzuki, T.
Hamamatsu, K.
Kawashima, H.
Kudo, Y.
Masaki, K.
Takahashi, H.
Takechi, M.
Akiba, M.
Okuno, K.
Ishida, S.
Ichimura, M.
Imai, T.
Hashizume
Miura, Y. M.
Horiike, H.
Kimura, A.
Tsutsui, H.
Matsuoka, M.
Uesugi, Y.
Sagara, A.
Nishimura, A.
Shimizu, A.
Sakamoto, M.
Nakamura, K.
Sato, K.
Okano, K.
Ida, K.
Shimada, H.R.
Kishimoto, Y.
Azechi, H.
Tanaka, S.
Yatsu, K.
Yoshida, N.
Inutake, M.
Fujiwara, M.
Inoue, N.
Hosogane, N.
Kuriyama, M.
Ninomiya, H.
Source :: Nuclear Fusion; March 2006, Vol. 46 Issue: 3 pS29-S38, 10p
Publication Year :: 2006
Abstract: An overview is given of the National Centralized Tokamak (NCT) programme as a research programme for advanced tokamak research to succeed JT-60U. The mission of NCT is to establish high beta steady-state operation for DEMO and to contribute to ITER. The machine flexibility is pursued in aspect ratio and shape controllability for the demonstration of the high-? steady-state, feedback control of resistive wall modes, wide current and pressure profile control capability and also very long pulse steady-state operation. Existing JT-60 infrastructure such as the heating and current drive system, power supplies and cooling systems will be best utilized for this modification.

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