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@ARTICLE{Klein:877428,
      author       = {Klein, Felix and Gilbert, Mark R. and Litnovsky, Andrey and
                      Gonzalez-Julian, Jesus and Weckauf, Sophie and Wegener,
                      Tobias and Schmitz, Janina and Linsmeier, Christian and
                      Bram, Martin and Coenen, Jan Willem},
      title        = {{T}ungsten–chromium–yttrium alloys as first wall armor
                      material: {Y}ttrium concentration, oxygen content and
                      transmutation elements},
      journal      = {Fusion engineering and design},
      volume       = {158},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2020-02183},
      pages        = {111667 -},
      year         = {2020},
      abstract     = {Tungsten (W) is a prime candidate as first wall armor
                      material of future fusion power plants as W withstands
                      extreme particle, heat, and radiation loads without forming
                      long-lived radioactive waste. The release of radioactive
                      material from the reactor to the environment should be
                      suppressed in case of an accident such as a loss of coolant
                      (LOCA) with simultaneous air ingress into the vacuum vessel.
                      W oxidizes and sublimates in case of a LOCA. Therefore,
                      oxidation resistant tungsten, chromium, yttrium (W–Cr–Y)
                      alloys are developed to provide intrinsic safety in case of
                      such an accident.In this paper, the optimization of the
                      yttrium (Y) concentration is presented on bulk samples
                      compacted by field assisted sintering technology (FAST). W
                      with 11.4 weight $(wt)\%$ Cr and $0.6 wt\%$ Y appears to
                      be an optimum regarding the oxidation resistance. Further,
                      first preparations for industrial upscaling, which may
                      increase the impurity level, are addressed. The oxygen (O)
                      content is varied systematically. It is shown that a good
                      oxidation resistance requires a low O level.The exposure of
                      the material to fusion neutrons is another issue addressed
                      on W–Cr–Y alloys. In a non-activated environment it is
                      shown that $1 wt\%$ rhenium (Re) dramatically changes the
                      oxidation kinetics: at 1273 K the mass gain of
                      W–Cr–Y–Re follows a cubic rate law while W–Cr–Y
                      follows a linear rate law for two days. Further, the
                      influence of the alloying elements on the neutron transport
                      and transmutation of W is studied by simulating the exposure
                      of spatially heterogeneous high-resolution models of the
                      W–Cr–Y alloys to 14 MeV fusion neutrons.},
      cin          = {IEK-4 / IEK-1},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013 / I:(DE-Juel1)IEK-1-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000569850500012},
      doi          = {10.1016/j.fusengdes.2020.111667},
      url          = {https://juser.fz-juelich.de/record/877428},
}