Optimization of Plasma Shape of the CFETR by Static Equilibrium Calculation

The zero-dimension parameter of the CFETR has been updated in 2018. The calculation of equilibria must give the operating space of the plasma configurations in extreme status, so as to provide a reference to other design issues, such as the physical study of the divertor and optimum design of the poloidal field (PF) coils. By using the TEQ, a sequence of standard H-mode equilibria with a wide range of internal self-inductance (li) and triangularity were established. The iteration of the equilibrium and divertor structure progressed until the result met the requirements in physics and engineering. A comparison of PF-coil designs from different coil positions was performed to demonstrate that it is indeed possible to sustain significant flux for the current flattop phase while PF coil currents are all under their limits. With additional PF coils inside the vacuum vessel, currents in some PF coils decreased, we then show that it is possible to build advanced diverted plasma configurations which would be beneficial for reducing high-power load on divertor targets.