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@ARTICLE{Pintsuk:878797,
      author       = {Pintsuk, G. and Brezinsek, S. and Coenen, J. W. and Huber,
                      A. and Rubel, M. and Widdowson, A.},
      title        = {{M}etallography and mechanical parameters of plasma-exposed
                      plasma-facing materials and components},
      journal      = {Physica scripta},
      volume       = {T171},
      issn         = {1402-4896},
      address      = {Stockholm},
      publisher    = {The Royal Swedish Academy of Sciences},
      reportid     = {FZJ-2020-03050},
      pages        = {014042 -},
      year         = {2020},
      abstract     = {The performance of materials in a fusion environment is
                      strongly dependent on the loading history, potentially
                      leading to material modification due to thermal and particle
                      (charged and neutral) loads. One clear indication of
                      material modification by thermal loads is the modification
                      of the microstructure by recrystallization, which is
                      assessed by metallographic means as well as hardness
                      measurements. Thereby, the recrystallization behaviour of a
                      material strongly depends on its manufacturing route, the
                      impurity level and on plasma impact, i.e. processes related
                      to plasma–wall interactions. In this study, surface
                      roughness and morphology as well as metallographic
                      examinations and investigation by indentation techniques of
                      components coming from different joint European torus (JET)
                      experimental campaigns were performed for the first time on
                      tritium-containing and therefore radioactive materials and
                      components. This comprises on the one hand standard, marker
                      and dedicated melt tungsten lamellae obtained from the
                      divertor. On the other hand, beryllium components covered by
                      nickel/beryllium marker coatings from the inner wall of JET,
                      i.e. the inner wall guard limiter, wide poloidal limiter and
                      dump plate were investigated. These have undergone various
                      loading conditions and temperature excursions leading to
                      surface modifications like material erosion, deposition and
                      melting, and have also been assessed by scanning electron
                      microscopy and energy-dispersive x-ray spectroscopy in view
                      of the influence of the marker layers.},
      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:000520000600042},
      doi          = {10.1088/1402-4896/ab4d72},
      url          = {https://juser.fz-juelich.de/record/878797},
}