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@ARTICLE{Oelmann:890591,
      author       = {Oelmann, Jannis and Wüst, Erik and Brezinsek, Sebastijan
                      and Li, Cong and Zhao, Dongye and Rasinski, Marcin and
                      Dhard, Chandra Prakash and Mayer, Matej and Naujoks, Dirk
                      and Gao, Yu},
      title        = {{H}ydrogen content in divertor baffle tiles in
                      {W}endelstein 7-{X}},
      journal      = {Nuclear materials and energy},
      volume       = {26},
      issn         = {2352-1791},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2021-01057},
      pages        = {100943 -},
      year         = {2021},
      abstract     = {Plasma–wall interactions play a crucial role for the
                      performance of fusion devices and the lifetime of
                      plasma-facing components. In this work the results of some
                      plasma–wall interaction processes, namely the
                      erosion/deposition pattern and the fuel content of divertor
                      baffle tiles exposed in Wendelstein 7-X in the initial phase
                      of island divertor, are presented. Net-deposition of carbon
                      with co-deposited oxygen and hydrogen is determined on the
                      graphite tiles after about 1 hour of plasma operation in
                      hydrogen and helium in operation phase OP 1.2a. C is
                      predominately a result of net-erosion of the graphite target
                      plates and oxygen is the strongest intrinsic impurity in
                      Wendelstein 7-X in OP 1.2a. The hydrogen content
                      distribution on a set of tiles exposed in equivalent
                      positions in three of the five modules of the stellarator
                      was quantified for the first time. Ex-situ performed
                      laser-induced breakdown spectroscopy measurements show the
                      depth-resolved fuel content in deposited layers as well as
                      implantation and diffusion in the base material.
                      Complementary, gas analysis after laser-induced ablation
                      offers quantitative hydrogen content determination in the
                      deposited layers up to 1018 hydrogen atoms/cm that is
                      non-uniformly distributed over the 95 mm 125 mm sized tiles.
                      The results show a toroidal asymmetry with $60\%$ more
                      hydrogen in the stellarator module 2 with respect to module
                      1 as well as a slight top-down asymmetry for the baffle
                      tiles in upper and lower half modules. A clear dependence of
                      the hydrogen content on the surface temperature during
                      plasma exposition in stellarator discharges in standard
                      magnetic divertor configuration with edge transformation 5/5
                      was not observed.},
      cin          = {IEK-4},
      ddc          = {624},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
      pid          = {G:(DE-HGF)POF4-134},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000628782500060},
      doi          = {10.1016/j.nme.2021.100943},
      url          = {https://juser.fz-juelich.de/record/890591},
}