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

被引:8
|
作者
Gohil, P [1 ]
Burrell, KH [1 ]
Hassam, AB [1 ]
Osborne, TH [1 ]
机构
[1] UNIV MARYLAND, COLLEGE PK, MD 20742 USA
关键词
D O I
10.1088/0741-3335/38/8/016
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
Experiments have been carried out on the DIII-D tokamak to investigate whether off-axis NBI can: (a) drive significant perpendicular Bow 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 (I-p = 0.5 MA, kappa = 1.2) 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 V x B contribution to the radial electric field during off-axis NBI.
引用
收藏
页码:1243 / 1247
页数:5
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