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Return To: Session FTP - Fusion Technology (Wednesday, 21 October)
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Y. Murakami , K. Shinya
Nuclear Engineering Laboratory, Toshiba Corporation,
Kawasaki-shi, Kanagawa-ken
S. Nishio
Naka Fusion Research Establishment, Japan
Atomic Energy Research Institute, Naka-machi, Naka-gun, Ibaraki-ken Japan
Abstract
Very high aspect ratio (A) tokamak reactor is proposed as a future
power plant. Plasma size and operation performance are surveyed over a wide
range of A. To reduce the plasma minor radius, relatively high toroidal
magnetic field of 18T is adopted. When the plasma major and minor radii are 12
m and 1.5 m (A=8), steady-state operation with 3 GW of fusion power and large
fusion gain (
) is possible. 90 % of bootstrap current fraction is
achieved by optimizing the density profile for the given MHD
equilibrium. Toroidal field (TF) coil size is estimated by considering the
field ripple, NBI beam line and coil case stress. Although overall TF-coil
height and width are smaller than those of ITER , cross-sectional area of the
TF-coil leg becomes 4 times larger than that of ITER to compensate the
vertical force.
IAEA 1999