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@ARTICLE{Rasinski:827146,
      author       = {Rasinski, M. and Kreter, A. and Torikai, Y. and Linsmeier,
                      Ch.},
      title        = {{T}he microstructure of tungsten exposed to {D} plasma with
                      different impurities},
      journal      = {Nuclear materials and energy},
      volume       = {12},
      issn         = {2352-1791},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2017-01344},
      pages        = {302-306},
      year         = {2017},
      abstract     = {In this study the effect of impurities in deuterium plasma
                      on the tungsten microstructure is investigated. W samples
                      were exposed in the linear plasma generator PSI-2 at a
                      sample temperature of 500 K with an incident ion flux of
                      about 1022 m−2s−1, an incident ion fluence of 5 × 1025
                      m−2 and an incident ion energy of 70 eV. Samples were
                      exposed to pure D+ plasma and with additional impurities of
                      He $(3\%),$ Ar $(7\%),$ Ne $(10\%)$ or N $(5\%).$ After the
                      PSI-2 exposure a part of each sample was additionally loaded
                      with tritium to measure the tritium uptake using the imaging
                      plate technique.The surface morphology was investigated
                      using scanning electron microscope (SEM) combined with a
                      focused ion beam (FIB) utilized for cross-sectioning and
                      thin lamella preparation for the transmission electron
                      microscope (TEM) analysis.Blistering with grain orientation
                      dependence was observed on all exposed samples. Most
                      pronounced blistering is reported for grains with
                      orientation close to (111). The addition of Ar or Ne results
                      in surface erosion with different yields depending on grain
                      orientation. Highest erosion yield is observed for grains
                      with orientation close to (100). Large blisters are present
                      but show signatures of erosion. Less pronounced erosion is
                      visible when adding N. The highest uptake of tritium was
                      reported for the sample exposed to D+He plasma which
                      corresponds to the largest – 18 nm, near surface damage
                      zone revealed by TEM. Lowest tritium accumulation was
                      observed for samples exposed to D+Ar and D+Ne plasmas, which
                      corresponds to the shallowest near surface damage zone, as
                      confirmed by TEM.},
      cin          = {IEK-4},
      ddc          = {333.7},
      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:000417293300044},
      doi          = {10.1016/j.nme.2016.11.001},
      url          = {https://juser.fz-juelich.de/record/827146},
}