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Plasma Sci. Technol. ›› 2018, Vol. 20 ›› Issue (3): 035102.doi: 10.1088/2058-6272/aa9e83

• Magnetically Confined Plasma • Previous Articles     Next Articles

Design of snowflake-diverted equilibria of CFETR

Hang LI (李航)1,2, Xiang GAO (高翔)1, Guoqiang LI (李国强)1, Zhengping LUO (罗正平)1, Damao YAO (姚达毛)1 and Yong GUO (郭勇)1   


  1. 1 Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031, People’s Republic of China 2 University of Science and Technology of China, Hefei 230029, People’s Republic of China
  • Received:2017-10-18 Published:2017-11-30
  • Supported by:

    This work was supported by the National Magnetic Confinement Fusion Program under grant nos 2014GB106001, 2014GB110003 and 2013GB111000, and by National Natural Science Foundation of China under grant no. 11675221.


The Chinese Fusion Engineering Test Reactor (CFETR) represents the next generation of full superconducting fusion reactors in China. Recently, CFETR was redesigned with a larger size and will be operated in two phases. To reduce the heat flux on the target plate, a snowflake (SF) divertor configuration is proposed. In this paper we show that by adding two dedicated poloidal field (PF) coils, the SF configuration can be achieved in both phases. The equilibria were calculated by TEQ code for a range of self-inductances li3. The coil currents were calculated at some fiducial points in the flattop phase. The results indicate that the PF coil system has the ability to maintain a long flattop phase in 7.5 and 10 MA inductive scenarios for the single null divertor (SND) and SF divertor configurations. The properties of the SF configuration were also analyzed. The connection length and flux expansion of the SF divertor were both increased significantly over the SND.

Key words: CFETR, equilibrium, PF coil, snowflake