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Helicity-injected current drive and open flux instabilities in spherical tokamaks

D P Brennan, P K Browning, J Gates, R A M Van der Linden2009年Plasma Physics and Controlled FusionIF 2.2出版社

The toroidal current driven by relaxation processes in a cylindrical spherical tokamak (ST) geometry with coaxial injected flux is estimated by use of the linear ideal stability boundary of equilibria with a high current on the open driven flux and a lower current on the closed flux. Instabilities with toroidal mode number n = 1 have been shown to play a vital role in the helicity injection current drive, being closely associated with the relaxation process which distributes current from a directly driven open flux to a closed flux. Previous results for spheromaks (1D and 2D equilibria) and STs (1D equilibria) have predicted stabilization, for a given open flux current, if the closed flux plasma current is sufficiently large, suggesting that the current drive mechanism is self-limiting. New results presented here for 2D ST equilibria are consistent with the 1D results, but new features appear in the stability maps as the axial length and toroidal field (TF) strength are varied in the equilibria. These include changes in the shape of stability boundaries and the estimated driven current, changes in the mode structure due to equilibrium changes and resonance effects which extend stability boundaries into the stable region. As the minimum and maximum of the safety factor q profile cross integer rational values, the resonant mode is destabilized, causing regions of enhanced instability in the current profile parameter space. The results show the effects on the stability of varying the geometric length ratio R/L and provide driven current estimates with varying imposed TF strengths; these results have implications both for existing STs and for the design of future devices.

日本語訳

緩和過程によって駆動されるトロイダル電流を、同軸注入を伴う円筒状球状トカマク(ST)幾何学配置において、開放磁束上の高電流と閉磁束上の低電流を有する平衡状態の線形安定性境界を用いて評価する。トロイダルモード数n = 1の不安定性は、ヘリシティ注入電流駆動において重要な役割を果たすことが示されており、直接駆動される開放磁束から閉磁束へ電流を再分布させる緩和過程と密接に関連している。スフェロマク(1次元および2次元平衡)とST(1次元平衡)に関する従来の結果では、所与の開放磁束電流に対して、閉磁束プラズマ電流が十分に大きければ安定化が予測され、電流駆動機構が自己制限的であることが示唆されている。本稿で提示する2次元ST平衡に関する新しい結果は、1次元の結果と整合的であるが、平衡状態における軸方向長さとトロイダル磁場(TF)強度を変化させると、安定性マップに新たな特徴が現れる。これには、安定性境界と推定駆動電流の形状変化、平衡変化によるモード構造の変化、および共鳴効果が安定領域まで及ぶことによる安定性境界の拡張が含まれる。安全係数qプロファイルの最小値および最大値が整数の有理値を横切ると、共鳴モードが不安定化され、電流プロファイルパラメータ空間において不安定性の増大した領域が生じる。これらの結果は、幾何学的長さ比R/Lの変化が安定性に及ぼす影響を示し、異なる印加TF強度に対する駆動電流の推定値を提供するものであり、既存のSTと将来の装置設計の両方に示唆を与える。

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Current driveSpherical tokamak
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