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@ARTICLE{Federici:836773,
      author       = {Federici, G. and Biel, W. and Gilbert, M. R. and Kemp, R.
                      and Taylor, N. and Wenninger, R.},
      title        = {{E}uropean {DEMO} design strategy and consequences for
                      materials},
      journal      = {Nuclear fusion},
      volume       = {57},
      number       = {9},
      issn         = {1741-4326},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2017-05824},
      pages        = {092002 -},
      year         = {2017},
      abstract     = {Demonstrating 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.},
      cin          = {IEK-4},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000407854600002},
      doi          = {10.1088/1741-4326/57/9/092002},
      url          = {https://juser.fz-juelich.de/record/836773},
}