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. Otsuka 1, K. Nakashima 2,
S. Nakagawa 3, R. Stambaugh 4,
D. L. Sevier 4, 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
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 1999