Utilizing the TokaMaker code, this manuscript presents a scheme for determining the optimal locations of poloidal field coils in tokamak configurations, aimed at reducing the currents required to reproduce target equilibrium in future devices. The definition of the coil position space is described, as well as the cost function is to be minimized, which incorporates the constraints of the problem. The MANTA reactor design, featuring strong negative triangularity shaping, is considered as a test example, where preliminary results are obtained with a reduced number of degrees of freedom in order to highlight the procedure for finding local minima. Application of the optimization procedure, guided by a study of the electric current regularization parameter, results in new suggestions for the placement of each poloidal field (PF) coil. This leads to a reduction in the total current flowing through the PF coils by 37% while accurately reproducing the target plasma boundary compared to a baseline case.
Salm et al. (Mon,) studied this question.