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K. Ushigusa, G. Kurita, N. Toyoshima,
K. Nagashima, Y. Neyatani, N. Miya, S. Ishiyama,
M. Kikuchi, A. Isayama, S. Ishida, H. Shirai,
M. Kuriyama, T. Itoh, T. Yamamoto, Y. Ikeda,
T. Imai, K. Hamamatsu, K. Tobita, M. Matsukawa,
H. Kubo, S. Nakagawa, K. Mori, T. Kitai,
S. Oguri, M. Otsuka1, K. Nakashima2,
S. Nakagawa3, R. Stambaugh4,
D. L. Sevier4, M. Nagami, H. Ninomiya,
M. Azumi, H. Kishimoto
Japan Atomic Energy Research Institute, Naka Fusion Research
Establishment Naka-machi, Naka-gun, Ibaraki-ken, 311-0193 Japan
1 Hitachi limited, Hitachi-shi, Ibaraki-ken Japan
2 Mitsubishi Fusion Center, Chiyoda-ku, Tokyo, Japan
3 Toshiba Corporation, Chiyoda-ku, Tokyo, Japan
4 General Atomics, San Diego, CA, USA
Abstract. Design optimization of JT-60SU has been done for a steady-state
advanced operation. A transport code simulation indicates that a fully
non-inductive reversed shear plasmas with fractions of 70% of the
bootstrap current and 30% of beam driven current can be sustained
for more than
1,000s without any additional control. Investigations have been progressed
on MHD stability, vertical positional stability and dynamics of the
vertical displacement events. Significant progress has been achieved
in the R&D of
Nb3Al superconducting wires, low induced activation material (Fe-Cr-Mn
steel). A design improvement has been made in TF coils to reduce a local
stress on radial disk. Dynamic behaviors of the tokamak machine have been
analyzed at emergency events such as an earthquake.
IAEA 2001
