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@ARTICLE{Linsmeier:834315,
      author       = {Linsmeier, Ch. and Rieth, M. and Aktaa, J. and Chikada, T.
                      and Hoffmann, J. and Houben, A. and Kurishita, H. and Jin,
                      X. and Li, M. and Litnovsky, A. and Matsuo, S. and von
                      Müller, A. and Nikolic, V. and Palacios, T. and Pippan, R.
                      and Qu, D. and Reiser, J. and Riesch, J. and Shikama, T. and
                      Stieglitz, R. and Weber, T. and Wurster, S. and You, J.-H.
                      and Zhou, Z. and Hoffmann, A.},
      title        = {{D}evelopment of advanced high heat flux and plasma-facing
                      materials},
      journal      = {Nuclear fusion},
      volume       = {57},
      number       = {9},
      issn         = {0029-5515},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2017-04294},
      pages        = {092007},
      year         = {2017},
      abstract     = {Plasma-facing materials and components in a fusion reactor
                      are the interface between the plasma and the material part.
                      The operational conditions in this environment are probably
                      the most challenging parameters for any material: high power
                      loads and large particle and neutron fluxes are
                      simultaneously impinging at their surfaces. To realize
                      fusion in a tokamak or stellarator reactor, given the proven
                      geometries and technological solutions, requires an
                      improvement of the thermo-mechanical capabilities of
                      currently available materials. In its first part this
                      article describes the requirements and needs for new,
                      advanced materials for the plasma-facing components.
                      Starting points are capabilities and limitations of
                      tungsten-based alloys and structurally stabilized materials.
                      Furthermore, material requirements from the fusion-specific
                      loading scenarios of a divertor in a water-cooled
                      configuration are described, defining directions for the
                      material development. Finally, safety requirements for a
                      fusion reactor with its specific accident scenarios and
                      their potential environmental impact lead to the definition
                      of inherently passive materials, avoiding release of
                      radioactive material through intrinsic material properties.
                      The second part of this article demonstrates current
                      material development lines answering the fusion-specific
                      requirements for high heat flux materials. New composite
                      materials, in particular fiber-reinforced and laminated
                      structures, as well as mechanically alloyed tungsten
                      materials, allow the extension of the thermo-mechanical
                      operation space towards regions of extreme steady-state and
                      transient loads. Self-passivating tungsten alloys,
                      demonstrating favorable tungsten-like plasma-wall
                      interaction behavior under normal operation conditions, are
                      an intrinsic solution to otherwise catastrophic consequences
                      of loss-of-coolant and air ingress events in a fusion
                      reactor. Permeation barrier layers avoid the escape of
                      tritium into structural and cooling materials, thereby
                      minimizing the release of tritium under normal operation
                      conditions. Finally, solutions for the unique bonding
                      requirements of dissimilar material used in a fusion reactor
                      are demonstrated by describing the current status and
                      prospects of functionally graded materials.},
      cin          = {IEK-4 / PTJ-DEQ},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013 / I:(DE-Juel1)PTJ-DEQ-20110722},
      pnm          = {113 - Methods and Concepts for Material Development
                      (POF3-113)},
      pid          = {G:(DE-HGF)POF3-113},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000407854600007},
      doi          = {10.1088/1741-4326/aa6f71},
      url          = {https://juser.fz-juelich.de/record/834315},
}