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On locating the poloidal field coils for tokamak vertical position control

J.B. Lister, Y. Martin, J.-M. Moret1996年被引用 28Nuclear FusionIF 3出版社

The TCV tokamak has 16 poloidal field coils for plasma shaping, distributed around the vacuum vessel. Experiments are described that determine the relative merits of different coil positions for controlling the unstable vertical movement of elongated plasmas. The results show over an order of magnitude variation in the amplitude of the plasma vertical position response to voltages applied to the different coils. The currents induced in the vessel, the required reactive feedback power and the ohmic power dissipated in the vessel all depend strongly on the coil location. Coils on the inboard, small major radius, side of the vacuum vessel are particularly effective at producing fast vertical displacements. A comparison of the results of two separate experiments with the predictions of a rigid current displacement model shows that the relative merits of the different coil positions are adequately explained by this model

日本語訳

TCVトカマクは、真空容器の周囲に分布した16個のポロイダル磁場コイルを有し、プラズマ形状を制御する。本実験では、細長いプラズマの不安定な垂直方向の運動を制御するための、異なるコイル位置の相対的な利点を決定する。結果は、異なるコイルに印加された電圧に対するプラズマ垂直位置応答の振幅が、一桁以上の範囲で変化することを示している。容器に誘起される電流、必要な無効電力、および容器内で消費されるジュール熱は、すべてコイルの位置に強く依存する。真空容器の内側(小半径側)に位置するコイルは、高速の垂直変位を生成するのに特に効果的である。2つの実験結果と剛体電流モデルによる予測との比較は、異なるコイル位置の相対的な利点がこのモデルによって適切に説明されることを示している。

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