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(FT/2-5) 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⁾, K. Yoshikawa^10)
 
1) Japan Atomic Energy Research Institute, Japan
²⁾ Tohoku University, Japan
³⁾ University of Tsukuba, Japan
⁴⁾ Osaka University, Japan
⁵⁾ Kyushu University, Japan
⁶⁾ Keio University, Japan
⁷⁾ Hokkaido University, Japan
⁸⁾ Tokyo Institute of Technology, Japan
⁹⁾ the University of Tokyo, Japan
¹⁰⁾ Kyoto University, Japan
¹¹⁾ Mie University, Japan
¹²⁾ Toshiba Corporation Power Systems and Services Company, Japan
¹³⁾ Hiroshima University, Japan
¹⁴⁾ Central Research Institute of Electric Power Industry, Japan
¹⁵⁾ Ibaraki University, Japan
¹⁶⁾ ITER JCT, Japan
¹⁷⁾ Nagoya University, Japan
¹⁸⁾ National Institute for Fusion Science, Japan
¹⁹⁾ National Institute of Advanced Industrial Science and Technology, Japan

Abstract.  The modification of JT-60U to a large and fully superconducting tokamak (JT-60SC) is proposed to demonstrate the high beta operation of the reactor relevant steady-state plasma and the applicability of the low activation ferritic steel characterized by a ferromagnetic property to plasma confinement devices. In order to improve economic and environmental suitability of tokamak fusion reactors, crucially important are the accomplishment of low circulating power operation in accord with a high pressure plasma and the establishment of utilization technology of low radio-activation materials to minimize the influence of radioactive waste to the environment. The JT-60SC device is designed to implement the steady-state research in a high performance plasma regime of a break-even class for a long duration ($\sim$100 s or longer) sufficiently exceeding a current diffusion time. Physics and engineering design of JT-60SC is presented to address the issues of high beta plasma control, steady state plasma control and divertor heat & particle control with high performance steady-state plasmas non-dimensionally similar to the future reactor plasma and surrounded by ferritic steel.

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