19th IAEA Fusion Energy Conference

Objectives and Design of the JT-60 Superconducting Tokamak

S. Ishida¹⁾, K. Abe²⁾, A. Ando²⁾, T. Cho³⁾, T. Fujii¹⁾, T. Fujita¹⁾, S. Goto⁴⁾, K. Hanada⁵⁾, A. Hatayama⁶⁾, T. Hino⁷⁾, H. Horiike⁴⁾, N. Hosogane¹⁾, M. Ichimura³⁾, S. Tsuji-Iio⁸⁾, S. Itoh⁵⁾, Y. Kamada¹⁾, M. Katsurai⁹⁾, M. Kikuchi¹⁾, A. Kitsunezaki¹⁾, A. Kohyama¹⁰⁾, H. Kubo¹⁾, M. Kuriyama¹⁾, M. Matsukawa¹⁾, M. Matsuoka¹¹⁾, Y. Miura¹⁾, Y.M. Miura¹⁾, N. Miya¹⁾, T. Mizuuchi¹⁰⁾, Y. Murakami¹²⁾, K. Nagasaki¹⁰⁾, H. Ninomiya¹⁾, N. Nishino¹³⁾, Y. Ogawa⁹⁾, K. Okano¹⁴⁾, T. Ozeki¹⁾, M. Saigusa¹⁵⁾, M. Sakamoto⁵⁾ , A. Sakasai¹⁾, M. Satoh¹⁾, M.Shimada¹⁶⁾, R. Shimada⁸⁾, M. Shimizu¹⁾, T. Takagi²⁾, Y. Takase⁹⁾, S. Takeji¹⁾, T. Tanabe¹⁷⁾, K. Toi¹⁸⁾, Y. Ueda⁴⁾, Y. Uesugi¹⁶⁾, K. Ushigusa¹⁾, M. Wakatani¹⁰⁾, Y. Yagi¹⁹⁾, K. Yamaguchi¹⁾, T. Yamamoto¹⁾, K. Yatsu³⁾, and K. Yoshikawa¹⁰⁾
1) Japan Atomic Energy Research Institute, 2) Tohoku University, 3) University of Tsukuba, 4) Osaka University, 5) Kyushu University, 6) Keio University, 7) Hokkaido University, 8) Tokyo Institute of Technology, 9) the University of Tokyo, 10) Kyoto University, 11) Mie University, 12) Toshiba Corporation Power Systems and Services Company, 13) Hiroshima University, 14) Central Research Institute of Electric Power Industry, 15) Ibaraki University, 16) ITER JCT, 17) Nagoya University, 18) National Institute for Fusion Science, 19) National Institute of Advanced Industrial Science and Technology, Japan

Abstract.
A fully superconducting tokamak named as JT-60SC is designed for the modification program of JT-60 to enhance economical and environmental attractiveness in tokamak fusion reactors. JT-60SC aims at realizing high-beta steady-state operation in the use of low radio-activation ferritic steel in low ν^* and ρ^* regime relevant to the reactor plasmas. Objectives, research issues, plasma control schemes and a conceptual design for JT-60SC are presented.