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@ARTICLE{Tsitrone:910629,
      author       = {Tsitrone, E. and Pegourie, B. and Gunn, J. P. and Bernard,
                      E. and Bruno, V. and Corre, Y. and Delpech, L. and Diez, M.
                      and Douai, D. and Ekedahl, A. and Fedorczak, N. and Gallo,
                      A. and Loarer, T. and Vartanian, S. and Gaspar, J. and Le
                      Bohec, M. and Rigollet, F. and Bisson, R. and Brezinsek, S.
                      and Dittmar, T. and De Temmerman, G. and Hakola, A. and
                      Wauters, T. and Balden, M. and Mayer, M. and WEST Team},
      title        = {{I}nvestigation of plasma wall interactions between
                      tungsten plasma facing components and helium plasmas in the
                      {WEST} tokamak},
      journal      = {Nuclear fusion},
      volume       = {62},
      number       = {7},
      issn         = {0029-5515},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2022-04007},
      pages        = {076028 -},
      year         = {2022},
      abstract     = {ITER will operate with a tungsten divertor, a material
                      featuring surface morphology changes when exposed to helium
                      plasmas, in particular the formation of the so called
                      tungsten fuzz under specific conditions. Investigating
                      interactions between tungsten plasma facing components and
                      helium plasmas in a tokamak environment is therefore a key
                      point to consolidate predictions for the ITER divertor
                      performance and lifetime. To this end, a dedicated helium
                      campaign was performed in the full tungsten WEST tokamak,
                      cumulating ∼2000 s of repetitive L mode discharges. It is
                      shown that conditions for tungsten fuzz formation, as
                      derived from linear devices experiments (incident helium
                      energy Einc > 20 eV, helium fluence >1024 He/m2, surface
                      temperature Tsurf > 700 °C), were met in the outer strike
                      point (OSP) area of the inertially cooled tungsten divertor
                      elements of WEST. Preliminary inspection of the components
                      after the campaign did not show visible signs of surface
                      modification, but points to significant net erosion in the
                      OSP area. An extensive post mortem analysis is now ongoing
                      to confirm these first indications. These results underline
                      that the complex balance between erosion/redeposition (in
                      particular linked to impurities) and tungsten fuzz formation
                      needs to be taken into account in tokamak conditions.},
      cin          = {IEK-4},
      ddc          = {620},
      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:000791566900001},
      doi          = {10.1088/1741-4326/ac2ef3},
      url          = {https://juser.fz-juelich.de/record/910629},
}