000836773 001__ 836773 000836773 005__ 20240711113559.0 000836773 0247_ $$2doi$$a10.1088/1741-4326/57/9/092002 000836773 0247_ $$2ISSN$$a0029-5515 000836773 0247_ $$2ISSN$$a1741-4326 000836773 0247_ $$2Handle$$a2128/15134 000836773 0247_ $$2WOS$$aWOS:000407854600002 000836773 0247_ $$2altmetric$$aaltmetric:20925652 000836773 037__ $$aFZJ-2017-05824 000836773 082__ $$a530 000836773 1001_ $$0P:(DE-HGF)0$$aFederici, G.$$b0$$eCorresponding author 000836773 245__ $$aEuropean DEMO design strategy and consequences for materials 000836773 260__ $$aVienna$$bIAEA$$c2017 000836773 3367_ $$2DRIVER$$aarticle 000836773 3367_ $$2DataCite$$aOutput Types/Journal article 000836773 3367_ $$0PUB:(DE-HGF)16$$2PUB:(DE-HGF)$$aJournal Article$$bjournal$$mjournal$$s1502348842_22524 000836773 3367_ $$2BibTeX$$aARTICLE 000836773 3367_ $$2ORCID$$aJOURNAL_ARTICLE 000836773 3367_ $$00$$2EndNote$$aJournal Article 000836773 520__ $$aDemonstrating the production of net electricity and operating with a closed fuel-cycle remain unarguably the crucial steps towards the exploitation of fusion power. These are the aims of a demonstration fusion reactor (DEMO) proposed to be built after ITER. This paper briefly describes the DEMO design options that are being considered in Europe for the current conceptual design studies as part of the Roadmap to Fusion Electricity Horizon 2020. These are not intended to represent fixed and exclusive design choices but rather 'proxies' of possible plant design options to be used to identify generic design/material issues that need to be resolved in future fusion reactor systems. The materials nuclear design requirements and the effects of radiation damage are briefly analysed with emphasis on a pulsed 'low extrapolation' system, which is being used for the initial design integration studies, based as far as possible on mature technologies and reliable regimes of operation (to be extrapolated from the ITER experience), and on the use of materials suitable for the expected level of neutron fluence. The main technical issues arising from the plasma and nuclear loads and the effects of radiation damage particularly on the structural and heat sink materials of the vessel and in-vessel components are critically discussed. The need to establish realistic target performance and a development schedule for near-term electricity production tends to favour more conservative technology choices. The readiness of the technical (physics and technology) assumptions that are being made is expected to be an important factor for the selection of the technical features of the device. 000836773 536__ $$0G:(DE-HGF)POF3-174$$a174 - Plasma-Wall-Interaction (POF3-174)$$cPOF3-174$$fPOF III$$x0 000836773 588__ $$aDataset connected to CrossRef 000836773 7001_ $$0P:(DE-Juel1)129967$$aBiel, W.$$b1 000836773 7001_ $$0P:(DE-HGF)0$$aGilbert, M. 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