Engineering features of the fusion ignition research experiment (FIRE)

被引:1
|
作者
Thome, RJ
Heitzenroeder, PJ
机构
[1] Gen Atom, San Diego, CA 92121 USA
[2] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
关键词
engineering features; fusion ignition research experiment; tokamak;
D O I
10.1016/S0920-3796(01)00472-0
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 fusion ignition research experiment (FIRE) tokamak is an option for the next step in the US magnetic fusion energy program. It has a major radius of 2 m, and a minor radius of 0.525 m. The general requirements for FIRE are B(T) = 10 T; I(P) = 6.5 MA; minimum flat top time = 10 s, and maximum number of full-power, full-field pulses = 3000 with 30000 pulses at 2/3 full field. The baseline design is able to meet or exceed these objectives. All magnets are inertially cooled with liquid nitrogen and have the capability for an 18 s flat top at 10 T. The use of BeCu in the inner legs of the toroidal field (TF) coil also allows for a field of 12 T with a pulse length of 12 s. Extended pulse lengths at lower fields (e.g. 214 s at 4 T and 2 MA) will allow FIRE to explore advanced tokamak modes (Physics basis for the Fusion Ignition Research Experiment (FIRE) Plasma Facing Components, in: Twenty-first Symposium on Fusion Technology, Madrid, September, 2000). (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:797 / 801
页数:5
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