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• This article describes the Remote Maintenance Strategy of the VNS Shielding Blanket. • Kinematic simulations confirm feasibility of independent SB segment removal. • Outboard SB segments can be replaced without removing the divertor. • Dedicated cutting and welding tools being designed for remote maintenance operations. • Integrated supports in the VV and port plug ensure the support of the SBs. A feasibility study of a new testing facility, i.e. the volumetric neutron source, VNS, in a tokamak configuration was initiated in 2023 and it is now under way with the purpose of addressing potential showstoppers. Key outcomes of the engineering activities are presented at this conference. The main goal of the VNS is to provide a realistic environment to test the in-vessel components of fusion reactors, in particular the tritium breeding blanket. The lessons learned during previous years of DEMO development point to the need for a thorough nuclear design integration already at level of the basic machine design, hence the issues related to the maintenance of the in-vessel components have been addressed at a basic level. The work presented here describes the remote maintenance strategy for VNS blankets, which is an adaptation of the concept proposed for DEMO. Consistent with the initial requirements of the machine, the remote replacement sequence of the blankets, the potential list of the required tools and transporter and the conceptual design of some of the main tools are presented and discussed in this article.
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Mozzillo et al. (2025) studied this question.
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