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@ARTICLE{Hannappel:155044,
      author       = {Hannappel, Stephan and Balzer, Frederike and Groeneweg,
                      Joost and Zühlke, Sebastian and Schulz, Dietrich},
      title        = {{V}orkommen von {T}ierarzneimitteln im oberflächennahen
                      {G}rundwasser unter {S}tandorten mit hoher
                      {V}iehbesatzdichte in {D}eutschland},
      journal      = {Hydrologie und Wasserbewirtschaftung},
      volume       = {58},
      number       = {4},
      issn         = {1439-1783},
      address      = {Koblenz},
      publisher    = {Bundesanst. für Gewässerkunde},
      reportid     = {FZJ-2014-04235},
      pages        = {208-220},
      year         = {2014},
      abstract     = {The findings of the EU ‘Materials Assessment Group’
                      (MAG), within the 2012 EU Fusion Roadmap exercise, are
                      discussed. MAG analysed the technological readiness of
                      structural, plasma facing and high heat flux materials for a
                      DEMO concept to be constructed in the early 2030s, proposing
                      a coherent strategy for $R\&D$ up to a DEMO construction
                      decision.A DEMO phase I with a ‘Starter Blanket’ and
                      ‘Starter Divertor’ is foreseen: the blanket being
                      capable of withstanding ⩾2 MW yr m−2 fusion neutron
                      fluence (∼20 dpa in the front-wall steel). A second phase
                      ensues for DEMO with ⩾5 MW yr m−2 first wall neutron
                      fluence. Technical consequences for the materials required
                      and the development, testing and modelling programmes, are
                      analysed using: a systems engineering approach, considering
                      reactor operational cycles, efficient maintenance and
                      inspection requirements, and interaction with functional
                      materials/coolants; and a project-based risk analysis, with
                      $R\&D$ to mitigate risks from material shortcomings
                      including development of specific risk mitigation materials.
                      The DEMO balance of plant constrains the blanket and
                      divertor coolants to remain unchanged between the two
                      phases. The blanket coolant choices (He gas or pressurised
                      water) put technical constraints on the blanket steels,
                      either to have high strength at higher temperatures than
                      current baseline variants (above 650 °C for high
                      thermodynamic efficiency from He-gas coolant), or superior
                      radiation-embrittlement properties at lower temperatures
                      (∼290–320 °C), for construction of water-cooled
                      blankets. Risk mitigation proposed would develop these
                      options in parallel, and computational and modelling
                      techniques to shorten the cycle-time of new steel
                      development will be important to achieve tight $R\&D$
                      timescales. The superior power handling of a water-cooled
                      divertor target suggests a substructure temperature
                      operating window (∼200–350 °C) that could be realised,
                      as a baseline-concept, using tungsten on a copper-alloy
                      substructure. The difficulty of establishing design codes
                      for brittle tungsten puts great urgency on the development
                      of a range of advanced ductile or strengthened tungsten and
                      copper compounds.Lessons learned from Fission reactor
                      material development have been included, especially in
                      safety and licensing, fabrication/joining techniques and
                      designing for in-vessel inspection. The technical basis of
                      using the ITER licensing experience to refine the issues in
                      nuclear testing of materials is discussed.Testing with 14
                      MeV neutrons is essential to Fusion Materials development,
                      and the Roadmap requires acquisition of ⩾30 dpa (steels)
                      14 MeV test data by 2026. The value and limits of
                      pre-screening testing with fission neutrons on isotopically-
                      or chemically-doped steels and with ion-beams are evaluated
                      to help determine the minimum14 MeV testing programme
                      requirements.},
      cin          = {IBG-3},
      ddc          = {690},
      cid          = {I:(DE-Juel1)IBG-3-20101118},
      pnm          = {246 - Modelling and Monitoring Terrestrial Systems: Methods
                      and Technologies (POF2-246) / 255 - Terrestrial Systems:
                      From Observation to Prediction (POF3-255)},
      pid          = {G:(DE-HGF)POF2-246 / G:(DE-HGF)POF3-255},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000340219900001},
      doi          = {10.5675/HyWa_2014,4_1},
      url          = {https://juser.fz-juelich.de/record/155044},
}