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Return To: Session FT/2 - Engineering Design
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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. Yoshikawa10)
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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IAEA 2003