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@ARTICLE{delaCal:875291,
      author       = {de la Cal, E. and Losada, U. and de Aguilera, A Martín and
                      Shaw, A. and Solano, E. and Alegre, D. and Balboa, I. and
                      Carvalho, P. and Gaspar, J. and Borodkina, I. and Brezinsek,
                      S. and Douai, D. and Giroud, C. and Guillemaut, C. and
                      Hidalgo, C. and Huber, A. and Joffrin, E. and Loarer, T. and
                      de la Luna, E. and Manzanares, A. and Militello, F. and de
                      Pablos, L. and Wiesen, S.},
      title        = {{I}mpact of divertor configuration on recycling neutral
                      fluxes for {ITER}-like wall in {JET} {H}-mode plasmas},
      journal      = {Plasma physics and controlled fusion},
      volume       = {62},
      number       = {3},
      issn         = {1361-6587},
      address      = {Bristol},
      publisher    = {IOP Publ.},
      reportid     = {FZJ-2020-01922},
      pages        = {035006 -},
      year         = {2020},
      abstract     = {In recent years it has been well known that in JET, with
                      the ITER-like wall, the performance of high-power H-mode
                      plasmas depends strongly on the magnetic topology of the
                      divertor. This is generally attributed to the effect of the
                      magnetic field shaping on the neutral flux transport and
                      pumping, which—in high density H-mode plasmas—determine
                      the pedestal properties and the global confinement. In this
                      work we have analysed the spatial distribution and the
                      dynamic behaviour of the D α -emission for different
                      magnetic configurations. Experimental observations indicate
                      that for certain configurations, the surface temperature and
                      the D α —emission anomalously increase on top of the
                      inner divertor, which points to thermal outgassing there.
                      This is also the region where most beryllium co-deposits
                      accumulate and most deuterium becomes trapped. The
                      overheating at this region far from the strike point (SP) is
                      observed to happen in magnetic configurations with reduced
                      distance between the divertor material surface and the
                      separatrix (clearance). The neutral flux that appears at the
                      upper inner divertor during a few milliseconds after the
                      ELM-crash, is more than an order of magnitude larger than
                      the gas puffing rate and dominates over all other regions.
                      Finally, a preliminary study describes how this thermal fuel
                      outgassing from the co-deposited layers could be used
                      intentionally as a wall-conditioning in JET technique with
                      plasmas that focus their particle and heat flux there. This
                      could be used as a complementary wall isotope control
                      technique and more specifically for tritium recovery from
                      the upper inner divertor where most fuel-trapping beryllium
                      co-deposits accumulate in JET ITER-like wall.},
      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:000520981000001},
      doi          = {10.1088/1361-6587/ab5fb1},
      url          = {https://juser.fz-juelich.de/record/875291},
}