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@ARTICLE{Gaspar:904047,
      author       = {Gaspar, J. and Corre, Y. and Fedorczak, N. and Gunn, J. P.
                      and Bourdelle, C. and Brezinsek, S. and Bucalossi, J. and
                      Chanet, N. and Dejarnac, R. and Firdaouss, M. and Gardarein,
                      J.-L. and Laffont, G. and Loarer, T. and Pocheau, C. and
                      Tsitrone, E. and Team, the WEST},
      title        = {{D}ivertor power loads and scrape off layer width in the
                      large aspect ratio full tungsten tokamak {WEST}},
      journal      = {Nuclear fusion},
      volume       = {61},
      number       = {9},
      issn         = {0029-5515},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2021-05617},
      pages        = {096027 -},
      year         = {2021},
      abstract     = {WEST is a full W tokamak with an extensive set of
                      diagnostics for heat load measurements especially in the
                      lower divertor. It is composed by infrared thermography,
                      thermal measurement with thermocouples and fibre Bragg
                      grating embedded few mm below the surface and flush mounted
                      Langmuir probes. A large database including different
                      magnetic equilibrium and input power is investigated to
                      compare the heat load pattern (location, amplitude of the
                      peak and heat flux decay length) on the inner and outer
                      strike point regions: from the first ohmic diverted plasma
                      (obtained during the second experimental campaign C2 in
                      2018) up to the high power (8 MW total injected) and high
                      energy (up to 90 MJ injected energy in lower single null
                      configuration) experiments performed in the last
                      experimental campaign (C4 in 2019). Concerning the peak
                      location, a good agreement (<1 cm) is obtained between
                      thermal inversions and flush-mounted LP measurements. The
                      peak heat flux from the whole set of diagnostics is in good
                      agreement and mainly in the $±20\%$ range, while the heat
                      flux decay length reported on the target shows significant
                      discrepancy between diagnostics and location in the machine
                      $(±40\%$ range). Despite such discrepancy, heat flux decay
                      length at target is found to scale mainly with the magnetic
                      flux expansion through the variation of the X-point height,
                      as expected. The improved plasma performances achieved
                      during C4 enabled to reach significant heat load in the
                      divertor, up to 6 MW m−2 with 4 MW of additional heating
                      power showing the capability to reach the ITER relevant heat
                      load (10 MW m−2 steady state) with about 7 MW of
                      additional power in L-mode discharge. The heat load
                      distribution is clearly asymmetric with a 3/4 and 1/4
                      distribution on the outer and inner strike point region
                      respectively for the parallel heat flux.},
      cin          = {IEK-4},
      ddc          = {620},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
      pid          = {G:(DE-HGF)POF4-134},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000684701900001},
      doi          = {10.1088/1741-4326/ac1803},
      url          = {https://juser.fz-juelich.de/record/904047},
}