Physics basis for the advanced tokamak fusion power plant, ARIES-AT

被引:41
作者
Jardin, SC
Kessel, CE
Mau, TK
Miller, RL
Najmabadi, F
Chan, VS
Chu, MS
LaHaye, R
Lao, LL
Petrie, TW
Politzer, P
St John, HE
Snyder, P
Staebler, GM
Turnbull, AD
West, WP
机构
[1] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[2] Univ Calif San Diego, Fus Energy Res Program, La Jolla, CA 92093 USA
[3] Gen Atom Co, San Diego, CA 92186 USA
关键词
reactor studies; fusion power plant; advanced tokamak; physics basis;
D O I
10.1016/j.fusengdes.2005.06.352
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
The advanced tokamak is considered as the basis for a fusion power plant. The ARIES-AT design has an aspect ratio of A R/a = 4.0, an elongation and triangularity of K = 2.20, delta = 0.90 (evaluated at the separatrix surface), a toroidal beta of beta = 9.1% (normalized to the vacuum toroidal field at the plasma center), which corresponds to a normalized beta beta(N) equivalent to 100 x beta/(I-p(MA)/a(m)B(T)) = 5.4. These beta values are chosen to be 10% below the ideal MHD stability limit. The bootstrap-current fraction is f(BS) equivalent to I-Bs/I-P = 0.91. This leads to a design with total plasma current I-P = 12.8 MA, and toroidal field of 11.1 T (at the coil edge) and 5.8 T (at the plasma center). The major and minor radii are 5.2 and 1.3 m. The effects of H-mode edge gradients and the stability of this configuration to non-ideal modes is analyzed. The current drive system consists of ICRF/FW for on-axis current drive and a Lower Hybrid system for off-axis. Transport projections are presented using the drift-wave based GLF23 model. The approach to power and particle exhaust using both plasma core and scrape-off-layer radiation is presented. (c) 2005 Elsevier B.V. All rights reserved.
引用
收藏
页码:25 / 62
页数:38
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