Design of magnetic equilibrium for CFEDR

This study presents the design progress of the equilibrium configuration for the China fusion engineering demo reactor. A new equilibrium was developed using the TEQ code, incorporating both zero-dimensional physical parameters and the engineering specifications of the magnetic coils. Through iterative optimization of the divertor and blanket structures, the first viable single-null divertor (SND) plasma configuration was achieved. The METIS code was further used to efficiently calculate current and pressure profiles during the ramp-up and flattop phases, thereby validating the design of the poloidal field (PF) coils. Results indicate that the current PF coil system meets the requirements for the SND configuration but faces challenges in maintaining the quasi-snowflake plus shape.