Conceptual design study of exchange of the in-vessel components by remote handling system for JT-60SA

Hayashi, Takao; Sakurai, Shinji; Masaki, Kei; Tamai, Hiroshi ; Yoshida, Kiyoshi; Matsukawa, Makoto

JT-60SA equipped with fully superconducting magnets is now being designed as a combined project of the Japanese national project toward DEMO reactor and a satellite tokamak project for ITER in a Broader approach with Japan and EU collaboration. Because the expected dose rate at the vacuum vessel (VV) may exceed 1 mSv/hr after 10 years operation and three month cooling, the human access inside the VV is prohibited. This indicates a remote handling (RH) system is necessary for the maintenance and repair of in-vessel components. This study described the RH system of JT-60SA to exchange or repair the in-vessel components such as first wall tiles and divertor modules. First wall armor tiles fully cover the plasma-side surface of the VV to protect from the plasma. Bolted armor tiles, made by graphite or ferritic steel, on a heat-sink can be replaced by LWM in the VV.