Global ideal MHD stability of plasmas with toroidal, helical and vertical field coils

被引：1
|
作者：
Ardelea, A [1 ]
Cooper, WA [1 ]
Villard, L [1 ]
机构：
[1] Ecole Polytech Fed Lausanne, Assoc Euratom Confederat Suisse, Ctr Rech Phys Plasmas, CH-1015 Lausanne, Switzerland
来源：
PLASMA PHYSICS AND CONTROLLED FUSION | 1998年 / 40卷 / 10期
关键词：
D O I：
10.1088/0741-3335/40/10/002
中图分类号：
O35 [流体力学]; O53 [等离子体物理学];
学科分类号：
070204 ; 080103 ; 080704 ;
摘要：
A simple configuration that consists of a set of toroidal, helical and vertical field coils is used to calculate free boundary equilibria with non-zero plasma current and approximately helically symmetric plasma boundary shape. The amount of helical boundary deformation is controlled by the ratio of the current in the helical field coils to the current in the toroidal field coils. When this ratio is increased, the (m, n) = (2, 1) external kink is stabilized at beta similar or equal to 1% for inverse rotational transform profiles in the region q < 2 and an aspect ratio A similar or equal to 10.
引用
收藏
页码：1679 / 1688
页数：10
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