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@ARTICLE{Rubel:835980,
      author       = {Rubel, M. and Petersson, P. and Zhou, Y. and Coad, J. P.
                      and Lungu, C. and Jepu, I. and Porosnicu, C. and Matveev, D.
                      and Kirschner, A. and Brezinsek, S. and Widdowson, A. and
                      Alves, E.},
      title        = {{F}uel inventory and deposition in castellated structures
                      in {JET}-{ILW}},
      journal      = {Nuclear fusion},
      volume       = {57},
      number       = {6},
      issn         = {1741-4326},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2017-05105},
      pages        = {066027},
      year         = {2017},
      abstract     = {Since 2011 the JET tokamak has been operated with a metal
                      ITER-like wall (JET-ILW) including castellated beryllium
                      limiters and lamellae-type bulk tungsten tiles in the
                      divertor. This has allowed for a large scale test of
                      castellated plasma-facing components (PFC). Procedures for
                      sectioning the limiters into single blocks of castellation
                      have been developed. This facilitated morphology studies of
                      morphology of surfaces inside the grooves for limiters after
                      experimental campaigns 2011–2012 and 2013–2014. The
                      deposition in the 0.4–0.5 mm wide grooves of the
                      castellation is 'shallow'. It reaches 1–2 mm into the
                      12 mm deep gap. Deuterium concentrations are small (mostly
                      below 1  ×  1018 cm−2). The estimated total
                      amount of deuterium in all the castellated limiters does not
                      exceed the inventory of the plasma-facing surfaces (PFS) of
                      the limiters. There are only traces of Ni, Cr and Fe
                      deposited in the castellation gaps. The same applies to the
                      carbon content. Also low deposition of D, Be and C has been
                      measured on the sides of the bulk tungsten lamellae pieces.
                      Modelling clearly reflects: (a) a sharp decrease in the
                      measured deposition profiles and(b) an increase in
                      deposition with the gap width. Both experimental and
                      modelling data give a strong indication and information to
                      ITER that narrow gaps in the castellated PFC are essential.
                      X-ray diffraction on PFS has clearly shown two distinct
                      composition patterns: Be with an admixture of Be–W
                      intermetallic compounds (e.g. Be22W) in the deposition zone,
                      whilst only pure Be has been detected in the erosion zone.
                      The lack of compound formation in the erosion zone indicates
                      that no distinct changes in the thermo-mechanical properties
                      of the Be PFC might be expected.},
      cin          = {IEK-4},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000425870600001},
      doi          = {10.1088/1741-4326/aa6864},
      url          = {https://juser.fz-juelich.de/record/835980},
}