Poloidal Field Coil and Current Distribution Study for the Toroidal Fusion Core Experiment (TFCX). Draft

摘要

The Toroidal Fusion Core Experiment (TFCX) is a proposed concept for an ignited, long-pulse, current-driven, ''next step'' tokamak device. The poloidal field (PF) coil configuration has major impact on the size and cost of a tokamak machine. The purpose of this trade study was to determine the achievable values of plasma triangularity and elongation consistent with mechanical configuration and plasma performance requirements. The study was made with three sets of PF coil configurations: (1) PF coils external to the (TF) coil, (2) all PF coils inside the TF coil bore, and (3) a hybrid configuration with some coils inside and some outside of the TF coil bore. The impact of plasma shape, profile, and coil locations on the distance between the plasma boundary and separatrix are presented. It is concluded that the plasma scrape-off requirements for removing impurities with a single null limiter can only be satisfied if the triangularity is limited to approx. 0.30 for an elongation of 1.6. (ERA citation 10:035711)