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首页> 外文期刊>Nuclear fusion >Plasma current ramp-up assisted by outer verticla field coils in a high aspect ratio tokamak
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Plasma current ramp-up assisted by outer verticla field coils in a high aspect ratio tokamak

机译：外部垂直磁场线圈在高纵横比托卡马克条件下辅助等离子体电流的上升

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摘要

Plasma current ramp-up assisted by outer vertical field coils with non-inductively driven current is studied during the ignition access phase ion a high aspect ratio tokamak such as ITER-FEAT class tokamak reactor. In a tokamak without the Ohmic transformer, the pllasma current ramp-up to 8 MA could be achieved by the vertical field with the heating/current drive power of 100 MW. The current ramp-up time can be chosen arbitrarily, as shorter than that expected in the usual, non-inductive current drive operation analyses, and it depends on the fusion power ramp-up time. This makes the reactor operation flexible. Experimental evidence showing the current drive by a vertical field in JT-60U has also been presented with plasma circuit theory.
机译：在点火通道阶段，研究了高纵横比托卡马克（例如ITER-FEAT类托卡马克电抗器）在外部垂直场线圈的辅助下，通过非感应驱动电流辅助的等离子体电流的上升。在没有Ohmic变压器的托卡马克中，可以通过垂直场以100 MW的加热/电流驱动功率实现等离子电流提升至8 MA。电流上升时间可以任意选择，比通常的非感应电流驱动操作分析中预期的时间短，并且取决于熔断功率上升时间。这使得反应器操作灵活。用等离子电路理论还提供了实验证据，表明在JT-60U中由垂直场驱动电流。

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