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@ARTICLE{Romazanov:862583,
      author       = {Romazanov, J. and Brezinsek, S. and Borodin, D. and Groth,
                      M. and Wiesen, S. and Kirschner, A. and Huber, Alexander and
                      Widdowson, A. and Airila, M. and Eksaeva, A. and Borodkina,
                      I. and Linsmeier, Ch.},
      title        = {{B}eryllium global erosion and deposition at {JET}-{ILW}
                      simulated with {ERO}2.0},
      journal      = {Nuclear materials and energy},
      volume       = {18},
      issn         = {2352-1791},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2019-02852},
      pages        = {331 - 338},
      year         = {2019},
      abstract     = {The recently developed Monte-Carlo code ERO2.0 is applied
                      to the modelling of limited and diverted discharges at JET
                      with the ITER-like wall (ILW). The global beryllium (Be)
                      erosion and deposition is simulated and compared to
                      experimental results from passive spectroscopy. For the
                      limiter configuration, it is demonstrated that Be
                      self-sputtering is an important contributor (at least
                      $35\%)$ to the Be erosion. Taking this contribution into
                      account, the ERO2.0 modelling confirms previous evidence
                      that high deuterium (D) surface concentrations of up to
                      $ ∼ 50\%$ atomic fraction provide a reasonable
                      estimate of Be erosion in plasma-wetted areas. For the
                      divertor configuration, it is shown that drifts can have a
                      high impact on the scrape-off layer plasma flows, which in
                      turn affect global Be transport by entrainment and lead to
                      increased migration into the inner divertor. The modelling
                      of the effective erosion yield for different operational
                      phases (ohmic, L- and H-mode) agrees with experimental
                      values within a factor of two, and confirms that the
                      effective erosion yield decreases with increasing heating
                      power and confinement.},
      cin          = {IEK-4 / JARA-HPC},
      ddc          = {624},
      cid          = {I:(DE-Juel1)IEK-4-20101013 / $I:(DE-82)080012_20140620$},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174) / 3D Monte-Carlo
                      simulations of plasma-wall interaction and impurity
                      transport in fusion devices $(jiek43_20170501)$},
      pid          = {G:(DE-HGF)POF3-174 / $G:(DE-Juel1)jiek43_20170501$},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000460107500056},
      doi          = {10.1016/j.nme.2019.01.015},
      url          = {https://juser.fz-juelich.de/record/862583},
}