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@ARTICLE{Brezinsek:866013,
      author       = {Brezinsek, S. and Kirschner, A. and Mayer, M. and
                      Baron-Wiechec, A. and Borodkina, I. and Borodin, D. and
                      Coffey, I. and Coenen, J. and den Harder, N. and Eksaeva, A.
                      and Guillemaut, C. and Heinola, K. and Huber, Alexander and
                      Imrisek, M. and Jachmich, S. and Pawelec, E. and Rubel, M.
                      and Krat, S. and Sergienko, G. and Matthews, G. F. and
                      Meigs, A. G. and Wiesen, S. and Widdowson, A.},
      title        = {{E}rosion, screening, and migration of tungsten in the
                      {JET} divertor},
      journal      = {Nuclear fusion},
      volume       = {59},
      number       = {9},
      issn         = {1741-4326},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2019-05273},
      pages        = {096035 -},
      year         = {2019},
      abstract     = {The erosion of tungsten (W), induced by the bombardment of
                      plasma and impurity particles, determines the lifetime of
                      plasma-facing components as well as impacting on plasma
                      performance by the influx of W into the confined region. The
                      screening of W by the divertor and the transport of W in the
                      plasma determines largely the W content in the plasma core,
                      but the W source strength itself has a vital impact on this
                      process. The JET tokamak experiment provides access to a
                      large set of W erosion-determining parameters and permits a
                      detailed description of the W source in the divertor closest
                      to the ITER one: (i) effective sputtering yields and fluxes
                      as function of impact energy of intrinsic (Be, C) and
                      extrinsic (Ne, N) impurities as well as hydrogenic isotopes
                      (H, D) are determined and predictions for the tritium (T)
                      isotope are made. This includes the quantification of intra-
                      and inter-edge localised mode (ELM) contributions to the
                      total W source in H-mode plasmas which vary owing to the
                      complex flux compositions and energy distributions in the
                      corresponding phases. The sputtering threshold behaviour and
                      the spectroscopic composition analysis provides an insight
                      in the dominating species and plasma phases causing W
                      erosion. (ii) The interplay between the net and gross W
                      erosion source is discussed considering (prompt)
                      re-deposition, thus, the immediate return of W ions back to
                      the surface due to their large Larmor radius, and surface
                      roughness, thus, the difference between smooth bulk-W and
                      rough W-coating components used in the JET divertor. Both
                      effects impact on the balance equation of local W erosion
                      and deposition. (iii) Post-mortem analysis reveals the net
                      erosion/deposition pattern and the W migration paths over
                      long periods of plasma operation identifying the net W
                      transport to remote areas. This W transport is related to
                      the divertor plasma regime, e.g. attached operation with
                      high impact energies of impinging particles or detached
                      operation, as well as to the applied magnetic configuration
                      in the divertor, e.g. close divertor with good geometrical
                      screening of W or open divertor configuration with poor
                      screening.JET equipped with the ITER-like wall (ILW)
                      provided unique access to the net W erosion rate within a
                      series of 151 subsequent H-mode discharges (magnetic field:
                      T, plasma current: MA, auxiliary power MW) in one magnetic
                      configuration accumulating 900 s of plasma with particle
                      fluences in the range of 5– in the semi-detached inner and
                      attached outer divertor leg. The comparison of W
                      spectroscopy in the intra-ELM and inter-ELM phases with
                      post-mortem analysis of W marker tiles provides a set of
                      gross and net W erosion values at the outer target plate.
                      ERO code simulations are applied to both divertor leg
                      conditions and reproduce the erosion/deposition pattern as
                      well as confirm the high experimentally observed prompt W
                      re-deposition factors of more than $95\%$ in the intra- and
                      inter-ELM phase of the unseeded deuterium H-mode plasma.
                      Conclusions to the expected divertor conditions in ITER as
                      well as to the JET operation in the DT plasma mixture are
                      drawn on basis of this unique benchmark experiment.},
      cin          = {IEK-4},
      ddc          = {620},
      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:000478620300002},
      doi          = {10.1088/1741-4326/ab2aef},
      url          = {https://juser.fz-juelich.de/record/866013},
}