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@ARTICLE{Wiesen:857060,
      author       = {Wiesen, S. and Brezinsek, S. and Bonnin, X. and Delabie, E.
                      and Frassinetti, L. and Groth, M. and Guillemaut, C. and
                      Harrison, J. and Harting, D. and Henderson, S. and Huber,
                      Alexander and Kruezi, U. and Pitts, R. A. and Wischmeier,
                      M.},
      title        = {{O}n the role of finite grid extent in {SOLPS}-{ITER} edge
                      plasma simulations for {JET} {H}-mode discharges with
                      metallic wall},
      journal      = {Nuclear materials and energy},
      volume       = {17},
      issn         = {2352-1791},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2018-06328},
      pages        = {174 - 181},
      year         = {2018},
      abstract     = {The impact of the finite grid size in SOLPS-ITER edge
                      plasma simulations is assessed for JET H-mode discharges
                      with a metal wall. For a semi-horizontal divertor
                      configuration it is shown that the separatrix density is at
                      least $30\%$ higher when a narrow scrape-off layer (SOL)
                      grid width is chosen in SOLPS-ITER compared to the case for
                      which the SOL grid width is maximised. The density increase
                      is caused by kinetic neutrals being not confined inside the
                      divertor region because of the reduced extent of the plasma
                      grid. In this case, an enhanced level of reflections of
                      energetic neutrals at the low-field side (LFS) metal
                      divertor wall is observed. This leads to a shift of the
                      ionisation source further upstream which must be accounted
                      for as a numerical artefact. An overestimate in the cooling
                      at the divertor entrance is observed in this case,
                      identified by a reduced heat flux decay parameters λqdiv.
                      Otherwise and further upstream the mid-plane heat decay
                      length λq parameter is not affected by any change in
                      divertor dissipation. This confirms the assumptions made for
                      the ITER divertor design studies, i.e. that λq upstream is
                      essentially set by the assumptions for the ratio radial to
                      parallel heat conductivity. It is also shown that even for
                      attached conditions the decay length relations
                      λne > λTe > λq hold in the near-SOL upstream.
                      Thus for interpretative edge plasma simulations one must
                      take the (experimental) value of λne into account, rather
                      than λq, as the former actually defines the required
                      minimum upstream SOL grid extent.},
      cin          = {IEK-4 / ICS-4},
      ddc          = {624},
      cid          = {I:(DE-Juel1)IEK-4-20101013 / I:(DE-Juel1)ICS-4-20110106},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000454165000023},
      doi          = {10.1016/j.nme.2018.10.013},
      url          = {https://juser.fz-juelich.de/record/857060},
}