Prospective analysis for high performance plasmas in JT-60SA

Tamai, Hiroshi ; Fujita, Takaaki; Kurita, Genichi; Tsuchiya, Katsuhiko; Matsukawa, Makoto

JT-60SA is positioned as the satellite tokamak of ITER to perform the ITER-relevant research through the optimisation of the operation scenario, as well as the steady-state high-beta plasma research oriented to DEMO. The design of the poloidal field magnet is optimised to realise the same aspect ratio and plasma shape as those in ITER. For the extension of operational regime towards high performance plasma, heating power is increased to 41 MW with 100 s. The prospect of plasma performance, analysed by equilibrium code and by transport code, indicates the high density and high plasma current sustainability with the ITER similar shape due to the increases in the electron temperature, beam driven current and bootstrap current.