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@ARTICLE{Zlobinski:864234,
      author       = {Zlobinski, M. and Sergienko, G. and Martynova, Y. and
                      Matveev, D. and Unterberg, B. and Brezinsek, S. and Spilker,
                      B. and Nicolai, D. and Rasinski, M. and Möller, S. and
                      Linsmeier, Ch. and Lungu, C. P. and Porosnicu, C. and Dinca,
                      P. and De Temmerman, G.},
      title        = {{L}aser-{I}nduced {D}esorption of co-deposited {D}euterium
                      in {B}eryllium {L}ayers on {T}ungsten},
      journal      = {Nuclear materials and energy},
      volume       = {19},
      issn         = {2352-1791},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2019-04068},
      pages        = {503 - 509},
      year         = {2019},
      abstract     = {For the development of the tritium monitoring system in
                      ITER the hydrogen isotope release by Laser-Induced
                      Desorption (LID) from Be layers is studied to determine the
                      laser parameters for a high desorption efficiency while
                      minimising dust production and surface modifications is also
                      pursued. Be layers of 1 µm thickness with 25–30 $at\%$
                      D and 3 × 1022 D/m2 comparable to JET-ILW areal
                      concentrations [1] have been produced by High Power Impulse
                      Magnetron Sputtering (HiPIMS) on ITER grade W. Laser pulses
                      of 1, 5 and 10 ms duration heat the layer in vacuum in the
                      Fuel REtention DIagnostic Setup (FREDIS) and release the
                      retained D thermally. By mass spectrometry in FREDIS and
                      subsequent Nuclear Reaction Analysis (NRA) inside the laser
                      spot the desorbed and remaining D is quantified. While a
                      pulse duration of 1 ms cannot fully desorb the deuterium,
                      it is found that a single 5 or 10 ms laser pulse with an
                      absorbed energy density of ca. 1.5 MJ/m2 corresponding to
                      a heat flux factor around 20 MW√s/m2 leads to nearly
                      complete desorption of the retained D. This encourages the
                      development of a useful tritium monitoring system, although
                      the present layers produce some dust due to local
                      delamination of the layer on at least $11\%$ of the heated
                      surface (at 1.4 MJ/m2 absorbed energy within 5 ms) and
                      lead to unavoidable crack formation.},
      cin          = {IEK-4 / IEK-1 / IEK-2},
      ddc          = {624},
      cid          = {I:(DE-Juel1)IEK-4-20101013 / I:(DE-Juel1)IEK-1-20101013 /
                      I:(DE-Juel1)IEK-2-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000470746100079},
      doi          = {10.1016/j.nme.2019.04.007},
      url          = {https://juser.fz-juelich.de/record/864234},
}