DESIGN PROCESS FOR THE CIT (COMPACT IGNITION TOKAMAK) POLOIDAL FIELD COIL SYSTEM.

The poloidal field (PF) system for the CIT consists of a central solenoid and ten ring coils which are external to the bore of the toroidal field coils, together with six ring coils which are located within the bore of the toroidal field coils. The baseline plasma carries 9 MA in a double null divertor configuration at an elongation of 2. 0 and a triangularity of 0. 3 (both at the 95% surface). The process used in selecting a PF coil set for CIT is outlined, and an example is given to demonstrate its capability. In particular, the plasma evolution for a case of interest is given together with system requirements in terms of coil size, power, and energy. The ability of the coil system to control dynamically the flux surface position on the divertor plates is illustrated.