中国物理B ›› 2016, Vol. 25 ›› Issue (11): 115201-115201.doi: 10.1088/1674-1056/25/11/115201

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

A divertor plasma configuration design method for tokamaks

Yong Guo(郭勇), Bing-Jia Xiao(肖炳甲), Lei Liu(刘磊), Fei Yang(杨飞), Yuehang Wang(汪悦航), Qinglai Qiu(仇庆来)   

  1. 1 Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031, China;
    2 School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China;
    3 Department of Computer Science, Anhui Medical University, Hefei 230026, China;
    4 CAS Key Laboratory of Basic Plasma Physics and Department of Modern Physics, University of Science and Technology of China, Hefei 230026, China
  • 收稿日期:2016-05-23 修回日期:2016-07-05 出版日期:2016-11-05 发布日期:2016-11-05
  • 通讯作者: Lei Liu E-mail:liulei@ipp.ac.cn
  • 基金资助:
    Project supported by the National Magnetic Confinement Fusion Research Program of China (Grant Nos. 2014GB103000 and 2014GB110003), the National Natural Science Foundation of China (Grant Nos. 11305216, 11305209, and 11375191), and External Cooperation Program of BIC, Chinese Academy of Sciences (Grant No. GJHZ201303).

A divertor plasma configuration design method for tokamaks

Yong Guo(郭勇)1, Bing-Jia Xiao(肖炳甲)1,2, Lei Liu(刘磊)1, Fei Yang(杨飞)3, Yuehang Wang(汪悦航)4, Qinglai Qiu (仇庆来)1   

  1. 1 Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031, China;
    2 School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230026, China;
    3 Department of Computer Science, Anhui Medical University, Hefei 230026, China;
    4 CAS Key Laboratory of Basic Plasma Physics and Department of Modern Physics, University of Science and Technology of China, Hefei 230026, China
  • Received:2016-05-23 Revised:2016-07-05 Online:2016-11-05 Published:2016-11-05
  • Contact: Lei Liu E-mail:liulei@ipp.ac.cn
  • Supported by:
    Project supported by the National Magnetic Confinement Fusion Research Program of China (Grant Nos. 2014GB103000 and 2014GB110003), the National Natural Science Foundation of China (Grant Nos. 11305216, 11305209, and 11375191), and External Cooperation Program of BIC, Chinese Academy of Sciences (Grant No. GJHZ201303).

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摘要： The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum chamber. It is important to construct the proper plasma equilibrium with a desired plasma configuration. In order to construct the target configuration, a shape constraint module has been developed in the tokamak simulation code (TSC), which controls the poloidal flux and the magnetic field at several defined control points. It is used to construct the double null, lower single null, and quasi-snowflake configurations for the required target shape and calculate the required PF coils current. The flexibility and practicability of this method have been verified by the simulated results.

关键词: plasma divertor configuration, tokamak simulation code, EAST, plasma shape design

Abstract: The efficient and safe operation of large fusion devices strongly relies on the plasma configuration inside the vacuum chamber. It is important to construct the proper plasma equilibrium with a desired plasma configuration. In order to construct the target configuration, a shape constraint module has been developed in the tokamak simulation code (TSC), which controls the poloidal flux and the magnetic field at several defined control points. It is used to construct the double null, lower single null, and quasi-snowflake configurations for the required target shape and calculate the required PF coils current. The flexibility and practicability of this method have been verified by the simulated results.

Key words: plasma divertor configuration, tokamak simulation code, EAST, plasma shape design

中图分类号:  (Tokamaks, spherical tokamaks)

  • 52.55.Fa
52.65.-y (Plasma simulation) 52.50.Nr (Plasma heating by DC fields; ohmic heating, arcs)