›› 2015, Vol. 24 ›› Issue (2): 25205-025205.doi: 10.1088/1674-1056/24/2/025205

• PHYSICS OF GASES, PLASMAS, AND ELECTRIC DISCHARGES • 上一篇    下一篇

Characterization of plasma current quench during disruption in EAST tokamak

陈大龙a, Granetz Robertc, 沈飙a, 杨飞a, 钱金平a, 肖炳甲a b   

  1. a Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China;
    b School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230031, China;
    c MIT Plasma Science and Fusion Center, Cambridge, MA 02139, USA
  • 收稿日期:2014-07-24 修回日期:2014-08-18 出版日期:2015-02-05 发布日期:2015-02-05
  • 基金资助:
    Project supported by the National Magnetic Confinement Fusion Science Program of China (Grant Nos. 2014GB103000 and 2013GB102000) and the National Natural Science Foundation of China (Grant No. 11205199 and 11205192).

Characterization of plasma current quench during disruption in EAST tokamak

Chen Da-Long (陈大龙)a, Granetz Robertc, Shen Biao (沈飙)a, Yang Fei (杨飞)a, Qian Jin-Ping (钱金平)a, Xiao Bing-Jia (肖炳甲)a b   

  1. a Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, China;
    b School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230031, China;
    c MIT Plasma Science and Fusion Center, Cambridge, MA 02139, USA
  • Received:2014-07-24 Revised:2014-08-18 Online:2015-02-05 Published:2015-02-05
  • Contact: Qian Jin-Ping E-mail:jpqian@ipp.ac.cn
  • Supported by:
    Project supported by the National Magnetic Confinement Fusion Science Program of China (Grant Nos. 2014GB103000 and 2013GB102000) and the National Natural Science Foundation of China (Grant No. 11205199 and 11205192).

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摘要： A preliminary analysis of plasma current quenching is presented in this paper based on the disruption database. It demonstrates that 26.8% of discharges have been disrupted in the last 2012 campaign, in addition, the plasma disruptive rate grows with the increase of plasma current. The best-fit linear and instantaneous plasma current quench rate is extracted from the recent EAST disruptions, showing that an 80%-30% interval of the maximum plasma current is well fit for the EAST device. The lowest area-normalized current quench time is 3.33 ms/m2 with the estimated plasma electron temperature being 7.3 eV～9.5 eV. In the disruption case the maximum eddy current goes up to 400 kA, and a fraction of currents are respectively driven on the upper and lower outer plate with nearly 100 MPa-200 MPa stress in the leg.

关键词: EAST, linear fit, area-normalized quench time, eddy current

Abstract: A preliminary analysis of plasma current quenching is presented in this paper based on the disruption database. It demonstrates that 26.8% of discharges have been disrupted in the last 2012 campaign, in addition, the plasma disruptive rate grows with the increase of plasma current. The best-fit linear and instantaneous plasma current quench rate is extracted from the recent EAST disruptions, showing that an 80%-30% interval of the maximum plasma current is well fit for the EAST device. The lowest area-normalized current quench time is 3.33 ms/m2 with the estimated plasma electron temperature being 7.3 eV～9.5 eV. In the disruption case the maximum eddy current goes up to 400 kA, and a fraction of currents are respectively driven on the upper and lower outer plate with nearly 100 MPa-200 MPa stress in the leg.

Key words: EAST, linear fit, area-normalized quench time, eddy current

中图分类号:  (Tokamaks, spherical tokamaks)

  • 52.55.Fa
52.35.Qz (Microinstabilities (ion-acoustic, two-stream, loss-cone, beam-plasma, drift, ion- or electron-cyclotron, etc.)) 52.65.Kj (Magnetohydrodynamic and fluid equation)