1.国際熱核融合実験炉(ITER)の遠隔保守(<小特集>核融合炉用遠隔保守技術の開発)

概要

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This paper both describes the overall design concept of the ITER remote maintenance system, which has been developed mainly for use with in-vessel components such as divertor and blanket, and outlines of the ITER R&D program, which has been established to develop remote handling equipment/tools and radiation hard components. In ITER, the reactor structures inside cryostat have to be maintained remotely because of activation due to DT operation. Therefore, remote-handling technology is fundamental, and the reactor-structure design must be made consistent with remote maintainability. The overall maintenance scenario and design concepts of the required remote handling equipment/tools have been developed according to their maintenance classification. Technologies are also being developed to verify the feasibility of the maintenance design and include fabrication and testing of a full-scale remote-handling equipment/tools for in-vessel maintenance.
社団法人プラズマ・核融合学会の論文
1997-01-25