九州・沖縄・山口支部
支部特別講演会

最終更新日:2010.7.28


日 時:2010年8月20日(金)10:30-12:00

場 所:九州大学 筑紫キャンパス 応用力学研究所高温プラズマ力学研究センター

講 演:QIAN, Jin ping, Institute of Plasma Physics Chinese Academy of Sciences (ASIPP), Assistant Professor

題 目:Progress in System Development and Experiments on EAST

要 旨:

Experimental Advanced Superconducting Tokamak (EAST) is a non-circular device that is intended to develop a steady-state-capable superconducting tokamak to establish the scientific and technological basis for future reactors. EAST has some new features different from the conventional tokamaks, particularly, the general feature of superconducting PF magnets with the limitation of current varying rate or voltage. The compromise between the plasma current ramp up and position control has to be adapted to achieve reliable plasma operation. To achieve long pulse diverted plasma discharges, new capabilities including the fully actively water cooled in-vessel components, current drive and heating systems, diagnostics and real-time plasma control algorithm were developed. Pre-programmed shape and feedback control of plasma position and current (RZIP) produced a variety of shaped plasma configurations, covering most of the configurations foreseen at the design stage of the machine. Control algorithm based on real-time equilibrium reconstruction and iso-flux control for the last closed magnetic flux surface (RTEFIT/ISOFLUX) has also been realized. LHCD experiments demonstrated long pulse discharges longer than 60 s and fully non inductive current drive.


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