中国物理B ›› 2009, Vol. 18 ›› Issue (12): 5406-5413.doi: 10.1088/1674-1056/18/12/047

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Mitigation and prediction of disruption on the HL-2A Tokamak

郑永真, 邱银, 张鹏, 黄渊, 崔正英, 孙平, 杨青巍   

  1. Southwestern Institute of Physics, Chengdu 610041, China
  • 收稿日期:2008-06-26 修回日期:2009-03-06 出版日期:2009-12-20 发布日期:2009-12-20
  • 基金资助:
    Project supported by the National Natural Science Foundation of China (Grant No 10475023).

Mitigation and prediction of disruption on the HL-2A Tokamak

Zheng Yong-Zhen(郑永真)†, Qiu Ying(邱银), Zhang Peng(张鹏),Huang Yuan(黄渊), Cui Zheng-Ying(崔正英),Sun Ping(孙平), and Yang Qing-Wei(杨青巍)   

  1. Southwestern Institute of Physics, Chengdu 610041, China
  • Received:2008-06-26 Revised:2009-03-06 Online:2009-12-20 Published:2009-12-20
  • Supported by:
    Project supported by the National Natural Science Foundation of China (Grant No 10475023).

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摘要： Injection of high-Z impurities into plasma has been proved to be able to reduce the localized thermal load and mechanical forces on the in-vessel components and the vacuum vessel, caused by disruptions in Tokamaks. An advanced prediction and mitigation system of disruption is implemented in HL-2A to safely shut down plasmas by using the laser ablation of high-Z impurities with a perturbation real-time measuring and processing system. The injection is usually triggered by the amplitude and frequency of the MHD perturbation field which is detected with a Mirnov coil and leads to the onset of a mitigated disruption within a few milliseconds. It could be a simple and potential approach to significantly reducing the plasma thermal energy and magnetic energy before a disruption, thereby achieving safe plasma termination. The plasma response to impurity injection, a mechanism for improving plasma thermal and current quench in major disruptions, the design of the disruption prediction warner, and an evaluation of the mitigation success rate are discussed in the present paper.

Abstract: Injection of high-Z impurities into plasma has been proved to be able to reduce the localized thermal load and mechanical forces on the in-vessel components and the vacuum vessel, caused by disruptions in Tokamaks. An advanced prediction and mitigation system of disruption is implemented in HL-2A to safely shut down plasmas by using the laser ablation of high-Z impurities with a perturbation real-time measuring and processing system. The injection is usually triggered by the amplitude and frequency of the MHD perturbation field which is detected with a Mirnov coil and leads to the onset of a mitigated disruption within a few milliseconds. It could be a simple and potential approach to significantly reducing the plasma thermal energy and magnetic energy before a disruption, thereby achieving safe plasma termination. The plasma response to impurity injection, a mechanism for improving plasma thermal and current quench in major disruptions, the design of the disruption prediction warner, and an evaluation of the mitigation success rate are discussed in the present paper.

Key words: disruption, current quench, electro-magnetic load, thermal load, mitigation and prediction of disruption

中图分类号:  (Tokamaks, spherical tokamaks)

  • 52.55.Fa
28.52.Fa (Materials) 52.25.Vy (Impurities in plasmas) 52.30.Cv (Magnetohydrodynamics (including electron magnetohydrodynamics)) 52.38.Mf (Laser ablation) 52.55.Rk (Power exhaust; divertors)