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@ARTICLE{DeTemmerman:910643,
      author       = {De Temmerman, Gregory and Heinola, Kalle and Borodin,
                      Dmitry and Brezinsek, Sebastijan and Doerner, Russell P. and
                      Rubel, Marek and Fortuna-Zaleśna, Elżbieta and Linsmeier,
                      Christian and Nishijima, Daisuke and Nordlund, Kai and
                      Probst, Michael and Romazanov, Juri and Safi, Elnaz and
                      Schwarz-Selinger, Thomas and Widdowson, Anna and Braams,
                      Bastiaan J. and Chung, Hyun-Kyung and Hill, Christian},
      title        = {{D}ata on erosion and hydrogen fuel retention in
                      {B}eryllium plasma-facing materials},
      journal      = {Nuclear materials and energy},
      volume       = {27},
      issn         = {2352-1791},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2022-04016},
      pages        = {100994 -},
      year         = {2021},
      abstract     = {ITER will use beryllium as a plasma-facing material in the
                      main chamber, covering a total surface area of about 620 m.
                      Given the importance of beryllium erosion and co-deposition
                      for tritium retention in ITER, significant efforts have been
                      made to understand the behaviour of beryllium under
                      fusion-relevant conditions with high particle and heat
                      loads. This paper provides a comprehensive report on the
                      state of knowledge of beryllium behaviour under
                      fusion-relevant conditions: the erosion mechanisms and their
                      consequences, beryllium migration in JET, fuel retention and
                      dust generation. The paper reviews basic laboratory studies,
                      advanced computer simulations and experience from laboratory
                      plasma experiments in linear simulators of plasma–wall
                      interactions and in controlled fusion devices using
                      beryllium plasma-facing components. A critical assessment of
                      analytical methods and simulation codes used in beryllium
                      studies is given. The overall objective is to review the
                      existing set of data with a broad literature survey and to
                      identify gaps and research needs to broaden the database for
                      ITER.},
      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:000670923000010},
      doi          = {10.1016/j.nme.2021.100994},
      url          = {https://juser.fz-juelich.de/record/910643},
}