Spherical torus concept as power plants - the ARIES-ST study

被引:108
作者
Najmabadi, F
机构
[1] Univ Calif San Diego, Dept Elect & Comp Engn, La Jolla, CA 92093 USA
[2] Univ Calif San Diego, Fus Energy Res Program, La Jolla, CA 92093 USA
关键词
spherical torus; spherical tokamark; fusion power plants;
D O I
10.1016/S0920-3796(02)00302-2
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Recent experimental achievements and theoretical studies have generated substantial interest in the spherical torus concept. The ARIES-ST study was undertaken as a national US effort to investigate the potential of the spherical tokamak concept as a fusion power plant. This 1000 MWe fusion power plant conceptual design has an aspect ratio of 1.6, a major radius of 3.2 m, a plasma elongation (at 95% flux surface) of 3.4 and triangularity of 0.64. This configuration attains a plasma beta(T) of 50% (which is 90% of theoretical limit). While the plasma current is 28 MA, the almost perfect alignment of bootstrap and equilibrium current density profiles results in a current-drive power of only 28 MW. The on-axis toroidal field of 2.1 T and the peak field at the TF coil of 7.4 T led to 329 MW of Joule losses in the normal-conducting TF system. The power core uses an advanced 'dual-cooled' breeding blanket with flowing PbLi breeder and He-cooled ferritic steel structures that can achieve a thermal conversion efficiency of similar to 45%. The ARIES-ST study has highlighted many areas where trade-off among physics and engineering systems are critical in determining the optimum regime of operation for ST power plants. (C) 2002 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:143 / 164
页数:22
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