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@ARTICLE{Brezinsek:202205,
      author       = {Brezinsek, Sebastijan},
      title        = {{P}lasma-surface interaction in the {B}e/{W} environment:
                      {C}onclusions drawn from the {JET}-{ILW} for {ITER}},
      journal      = {Journal of nuclear materials},
      volume       = {463},
      issn         = {0022-3115},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier Science},
      reportid     = {FZJ-2015-04494},
      pages        = {11 - 21},
      year         = {2015},
      abstract     = {The JET ITER-Like Wall experiment (JET-ILW) provides an
                      ideal test bed to investigate plasma-surface interaction
                      (PSI) and plasma operation with the ITER plasma-facing
                      material selection employing beryllium in the main chamber
                      and tungsten in the divertor. The main PSI processes:
                      material erosion and migration, (b) fuel recycling and
                      retention, (c) impurity concentration and radiation have
                      be1en studied and compared between JET-C and JET-ILW. The
                      current physics understanding of these key processes in the
                      JET-ILW revealed that both interpretation of previously
                      obtained carbon results (JET-C) and predictions to ITER need
                      to be revisited. The impact of the first-wall material on
                      the plasma was underestimated.Main observations are: (a) low
                      primary erosion source in H-mode plasmas and reduction of
                      the material migration from the main chamber to the divertor
                      (View the MathML sourcefactor7) as well as within the
                      divertor from plasma-facing to remote areas (View the MathML
                      sourcefactor30-50). The energetic threshold for beryllium
                      sputtering minimises the primary erosion source and inhibits
                      multi-step re-erosion in the divertor. The physical
                      sputtering yield of tungsten is low as 10-510-5 and
                      determined by beryllium ions. (b) Reduction of the long-term
                      fuel retention (View the MathML sourcefactor10-20) in
                      JET-ILW with respect to JET-C. The remaining retention is
                      caused by implantation and co-deposition with beryllium and
                      residual impurities. Outgassing has gained importance and
                      impacts on the recycling properties of beryllium and
                      tungsten. (c) The low effective plasma charge
                      (Zeff=1.2Zeff=1.2) and low radiation capability of beryllium
                      reveal the bare deuterium plasma physics. Moderate nitrogen
                      seeding, reaching Zeff=1.6Zeff=1.6, restores in particular
                      the confinement and the L-H threshold behaviour.
                      ITER-compatible divertor conditions with stable
                      semi-detachment were obtained owing to a higher density
                      limit with ILW. Overall JET demonstrated successful plasma
                      operation in the Be/W material combination and confirms its
                      advantageous PSI behaviour and gives strong support to the
                      ITER material selection.},
      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:000358467200003},
      doi          = {10.1016/j.jnucmat.2014.12.007},
      url          = {https://juser.fz-juelich.de/record/202205},
}