Comparison benchmark between tokamak simulation code and TokSys for Chinese Fusion Engineering Test Reactor vertical displacement control design<xref rid="cpb_26_6_065205_fn1" ref-type="fn">*</xref> <fn id="cpb_26_6_065205_fn1"> <label>*</label> <p>Project supported by the National Natural Science Foundation of China (Grant Nos. 11305216, 11305209, and 11375191), the National Magnetic Confinement Fusion Research Program of China (Grant Nos. 2014GB103000 and 2014GB110003), and External Cooperation Program of BIC, Chinese Academy of Sciences (Grant No. GJHZ201303).</p> </fn>

Comparison benchmark between tokamak simulation code and TokSys for Chinese Fusion Engineering Test Reactor vertical displacement control design* *

Project supported by the National Natural Science Foundation of China (Grant Nos. 11305216, 11305209, and 11375191), the National Magnetic Confinement Fusion Research Program of China (Grant Nos. 2014GB103000 and 2014GB110003), and External Cooperation Program of BIC, Chinese Academy of Sciences (Grant No. GJHZ201303).

Qiu Qing-Lai¹, Xiao Bing-Jia^{1, 2}, Guo Yong^{1, †}, Liu Lei¹, Wang Yue-Hang³

(color online) Geometric model of CFETR. Contour lines denote flux surfaces of case 1 initial equilibrium reconstructed by TSC. Black thick line denotes plasma boundary computed by EFIT.