The Engineering Design of ITER has been conducted under an international joint effort aiming at realization of fusion energy. The remote maintenance of in-vessel components such as blanket and divertor is quite essential since personnel access to the core of ITER will be prohibited. The maintenance procedures and design concepts of the in-vessel remote handling system have been developed and the design feasibility has been validated through technology development. This paper describes the design outline developed for both blanket and divertor maintenance, the latest R&D status of the remote handling systems as well as the full-scale mock-up tests planned during the ITER EDA.
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