Abstract
The JT-60SA (Super Advanced) project is a joint project of the ITER Satellite Tokamak program and the National Centralized Tokamak program in Japan with missions of supporting ITER, complementing ITER and exploring advanced issues toward DEMO. JT-60SA is a tokamak with superconducting coils, equipped with a poloidal field coil system with wide plasma shape controllability, upper and lower divertors with different shapes, NBI and ECRF with heating power 41 MW and various heating methods, in-vessel coils for suppressing MHD instabilities. With these functions, possibilities of producing ELMy H-mode with improved confinement, full non-inductive current drive of high beta plasmas (βN=3.7 at IP=3.5 MA, βN =4.4 at IP=2.4 MA) and break-even class plasmas necessary for accomplishing the mission have been confirmed. The engineering design of JT-60SA is being done taking large annual neutron production into account. Double skin walls filled with borated water or boron doped concrete are employed for the vacuum vessel and cryostat, respectively, for neutron shield. Divertors structures and first walls are being designed so as to be changed with remote handling systems in the high radiation circumference.
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