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

A Ardelea, W A Cooper, L Villard1998年Plasma Physics and Controlled FusionIF 2.2出版社

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 for inverse rotational transform profiles in the region q < 2 and an aspect ratio .

日本語訳

トロイダル、ヘリカル、およびポロイダル磁場コイルの集合からなる単純な配位を用いて、非ゼロのプラズマ電流と近似的にヘリカル対称なプラズマ境界形状を有する自由境界平衡を計算する。ヘリカル境界変形の大きさは、ヘリカル磁場コイルの電流とトロイダル磁場コイルの電流との比によって制御される。この比を増加させると、(m, n) = (2,1) 外部キンクモードは、q < 2 の領域における逆回転変換プロファイルおよびアスペクト比 に対して安定化される。

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MagnetohydrodynamicsMHD stabilityIdeal MHD
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