Affiliations: [a] School of Electrical Engineering and Automation, Hefei University of Technology, Hefei, China | [b] Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, China
Correspondence:
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Corresponding author: Xiaohua Bao, School of Electrical Engineering and Automation Hefei University of Technology, Hefei, China. Tel.: +86 0551 62905883; Fax: +86 0551 62905883; E-mail: [email protected]
Abstract: This paper studies the impact of Poloidal Field (PF) coil current disturbance on plasma shape in Experimental Advanced Superconductive Tokamak (EAST). First, the concept of the free-boundary equilibrium problem is studied. Based on the non-rigid plasma model, a free-boundary equilibrium solver developed in MATLAB software is presented to calculate the flux distribution and plasma profile of EAST plasma equilibrium, and the results are validated against the experiments. Second, given a typical double-null plasma equilibrium, the responses of plasma shape to the lower PF coil currents are computed using the orthogonal test method. The dependences of the elongation and triangularity of plasma shape on PF coil currents are obtained, showing that the currents in PF6 and PF8 have the greatest impact on triangularity and elongation for lower single-null (LSN) divertor configuration, respectively. And for double-null (DN) divertor plasma configuration, PF5 and PF7 play equally important roles due to the up-down symmetry. The conclusions will be useful for the design of EAST plasma shape feedback control.
Keywords: EAST tokamak, plasma shape response, free-boundary equilibrium calculation, orthogonal test method
