A divertor plasma configuration design method for tokamaks
Guo Yong1, Xiao Bing-Jia1, 2, Liu Lei1, †, , Yang Fei3, Wang Yuehang4, Qiu Qinglai1
       

(a) The TSC constructed plasma equilibrium with boundary flux ∼ −0.6962 Wb/rad (case 1 in Table 2), (b) the EFIT reconstructed shape (blue), which is compared with the TSC results (black).