Power and particle control in JT-60SA to support and supplement ITER and DEMO

Sakurai, Shinji

JT-60U will be modified as a fully superconducting coil tokamak JT-60SA. Divertor cassettes are introduced to be maintained by remote handling for high dose rate due to a substantial annual neutron production. A monoblock type carbon fibre composite divertor target will be used to withstand a heat load of 15 MW/m. All of the plasma facing components are water-cooled to handle heat load during 100s or more. Divertor heat load and pumping efficiency for an ITER-like configuration has been evaluated, using 2D plasma fluid (SOLDOR) and neutral Monte-Carlo (NEUT2D) code. In the simulation for the divertor with a "V-shaped corner" like as that in ITER, the plasma detachment occurs near the outer-strike point within the "V-shaped corner", as well as near the inner-strike point, which results in low peak heat flux density 5.8 MW/m for the case with additional gas puff of 5 10/s compared to 11.4 MW/m for the case without "V-shaped corner".