Objectives
The mission of the JT-60SA project is to contribute to the early realization of fusion energy by addressing key physics issues for ITER and DEMO.
JT-60SA is a fully superconducting tokamak capable of confining break-even equivalent high-temperature deuterium plasmas.
It is designed to allow the optimisation of configurations for ITER and DEMO by operating with a wide range of plasma shapes (elongations and triangularities) and aspect ratios (A=R/a down to ~ 2.5) including that of ITER, with the capability to operate in both single and double null divertor configurations.
The machine will allow the exploration of ITER-relevant high density plasma regimes well above the H-mode power threshold with up to 41 MW of high power electron cyclotron (EC) resonance and positive and negative ion neutral beam (NB) heating.
JT-60SA is designed to study power and particle handling for 100s at high power with water-cooled divertors compatible with maximum heat fluxes of 15MW/m2.
The machine will be able to explore full non-inductive steady-state operation with 10MW/500keV tangential NB current drive (CD) and 7MW of ECCD.
It will be able to explore high beta plasma regimes by using a stabilizing shell covered with ferritic plates, internal resistive wall mode (RWM) stabilizing coils, and a high power H&CD system.
JT-60SA will be equipped with a remote handing system to allow maintenance of in-vessel components compatibly with the planned annual yield of 1.5x1021neutrons/year.