期刊论文

Li, Xinxia

英文

Fusion Engineering and Design

0920-3796

2021

172

112897

10.1016/j.fusengdes.2021.112897

The authors would like to thank Dr Yong Xiao, Dr Miaohui Li for fruitful discussions. The work was supported by the National Natural Science Foundation of China under Grant no. 11775108, and the National Key R&D Program of China under Grant no. 2017YFE0300406. The numerical computations were performed on the ShenMa High Performance Computing Cluster in the Institute of Plasma Physics, Chinese Academy of Sciences.

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The China Fusion Engineering Testing Reactor (CFETR) is a tokamak reactor and aims to eventually reach DEMO relevant fusion power level of 1 GW. A lower single null configuration of the divertor design is proposed for the machine. To obtain the high performance operation of the plasma, both the hybrid and steady-state operating scenarios are suggested. In these scenarios, the plasma beta of similar to 1.6% has been generally reached. In the paper, helicon wave propagation and current drive in CFETR are studied through GENRAY/CQL3D code. An analysis of the wave damping factor in CFETR plasma in...