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@ARTICLE{Kirschner:841761,
      author       = {Kirschner, A. and Tskhakaya, D. and Brezinsek, S. and
                      Borodin, D. and Romazanov, J. and Ding, R. and Eksaeva, A.
                      and Linsmeier, Ch},
      title        = {{M}odelling of plasma-wall interaction and impurity
                      transport in fusion devices and prompt deposition of
                      tungsten as application},
      journal      = {Plasma physics and controlled fusion},
      volume       = {60},
      number       = {1},
      issn         = {1361-6587},
      address      = {Bristol},
      publisher    = {IOP Publ.},
      reportid     = {FZJ-2018-00065},
      pages        = {014041 -},
      year         = {2018},
      abstract     = {Main processes of plasma-wall interaction and impurity
                      transport in fusion devices and their impact on the
                      availability of the devices are presented and modelling
                      tools, in particular the three-dimensional Monte-Carlo code
                      ERO, are introduced. The capability of ERO is demonstrated
                      on the example of tungsten erosion and deposition modelling.
                      The dependence of tungsten deposition on plasma temperature
                      and density is studied by simulations with a simplified
                      geometry assuming (almost) constant plasma parameters. The
                      amount of deposition increases with increasing electron
                      temperature and density. Up to $100\%$ of eroded tungsten
                      can be promptly deposited near to the location of erosion at
                      very high densities (~1 × 1014 cm−3 expected e.g. in the
                      divertor of ITER). The effect of the sheath characteristics
                      on tungsten prompt deposition is investigated by using
                      particle-in-cell (PIC) simulations to spatially resolve the
                      plasma parameters inside the sheath. Applying PIC data
                      instead of non-resolved sheath leads in general to smaller
                      tungsten deposition, which is mainly due to a density and
                      temperature decrease towards the surface within the sheath.
                      Two-dimensional tungsten erosion/deposition simulations,
                      assuming symmetry in toroidal direction but poloidally
                      spatially varying plasma parameter profiles, have been
                      carried out for the JET divertor. The simulations reveal,
                      similar to experimental findings, that tungsten gross
                      erosion is dominated in H-mode plasmas by the intra-ELM
                      phases. However, due to deposition, the net tungsten erosion
                      can be similar within intra- and inter-ELM phases if the
                      inter-ELM electron temperature is high enough. Also, the
                      simulated deposition fraction of about $84\%$ in between
                      ELMs is in line with spectroscopic observations from which a
                      lower limit of $50\%$ has been estimated.},
      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:000428752600003},
      doi          = {10.1088/1361-6587/aa8dce},
      url          = {https://juser.fz-juelich.de/record/841761},
}