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Plasma rotation and the radial electric field during off-axis NBI in the DIII - D tokamak

P Gohil, K H Burrell, A B Hassam, T H Osborne1996年Plasma Physics and Controlled FusionIF 2.2出版社

Experiments have been carried out on the DIII - D tokamak to investigate whether off-axis NBI can: (a) drive significant perpendicular flow to lead to increased suppression of turbulence and improved confinement, and (b) be used to control the radial electric field profile. Measurements of both impurity ion poloidal and toroidal rotation profiles were made using charge exchange recombination spectroscopy. These experiments used a low current, low elongation ( MA, ) plasma whose magnetic axis was shifted 36 cm vertically upward from the vessel midplane and then shifted downward to be centred on the midplane later in the discharge. 10.7 MW of beam power was applied to maximize the NBI effect whilst operating at low target densities and high temperature to minimize poloidal damping. Results from these experiments show a slight increase in impurity ion poloidal rotation velocity during the vertical shifted phase of off-axis NBI discharge. The toroidal rotation profile is more peaked during off-axis NBI. Both these effects lead to a change in the contribution to the radial electric field during off-axis NBI.

日本語訳

DIII-Dトカマクにおいて、オフ軸NBIが(a)有意な垂直方向の流れを駆動し、乱流の抑制増大と閉じ込めの改善をもたらすことができるか、また(b)径方向電場分布の制御に使用できるかを調べるための実験が実施された。不純物イオンのポロイダル回転分布とトロイダル回転分布の両方の測定は、電荷交換再結合分光法を用いて行われた。これらの実験では、低電流・低伸長率(MA、)のプラズマを使用し、その磁気軸は容器中央面から垂直方向に36cm上方へシフトされ、その後、放電の後期に中央面を中心とするように下方へシフトされた。NBI効果を最大化するために10.7MWのビーム出力が印加され、一方でポロイダル減衰を最小化するために低いターゲット密度と高い温度で運転された。これらの実験の結果は、オフ軸NBI放電の垂直シフト位相中に不純物イオンのポロイダル回転速度がわずかに増加することを示している。トロイダル回転分布はオフ軸NBI中によりピーク化される。これらの両方の効果は、オフ軸NBI中の径方向電場への寄与の変化をもたらす。

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Neutral beam injectionRadial electric fieldPlasma rotation
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