Abstract
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.
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