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@ARTICLE{Huber:904052,
      author       = {Huber, A. and Chankin, A. V.},
      title        = {{S}caling of impurity fractions for divertor detachment in
                      high-density high-power operation scenarios},
      journal      = {Nuclear fusion},
      volume       = {61},
      number       = {3},
      issn         = {0029-5515},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2021-05622},
      pages        = {036049 -},
      year         = {2021},
      abstract     = {For future reactor designs and for planning of operational
                      scenarios in the present and future machines, impurity
                      fractions in the tokamak divertor plasma, cZ, is an
                      essential input for predictive scalings of divertor
                      detachment. A new quantitative scaling law for cZ, averaged
                      over the scrape-off layer (SOL), required to attain
                      detachment is developed for high power H-mode plasmas
                      operated at high densities close to the density limit. It is
                      based on a simple SOL radiation model which uses the
                      combination of the empirical scaling laws for the H-mode
                      power threshold and the separatrix density limit imposed by
                      MHD instabilities. Additionally, it assumes, in agreement
                      with experimental observations that the width of the power
                      conducting layer outside of the separatrix scales
                      approximately with the ion poloidal gyro-radius. The derived
                      expression for cZ scales strongly with toroidal magnetic
                      field, B, major radius R, the factor of access of the power
                      flow through the separatrix over that required for the L–H
                      transition, fLH, and isotope mass A: ${c}_{Z}\propto
                      {B}^{1.47}{R}^{1.59}{f}_{\mathrm{L}\mathrm{H}}^{1.38}/{A}^{1.38}$.
                      Estimates of required impurity fractions for divertor
                      detachment for an number of impurity species (N2, Ne and Ar)
                      in future tokamak reactors ITER and DEMO are made in the
                      paper.},
      cin          = {IEK-4},
      ddc          = {620},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {1232 - Power-based Fuels and Chemicals (POF4-123) / 134 -
                      Plasma-Wand-Wechselwirkung (POF4-134)},
      pid          = {G:(DE-HGF)POF4-1232 / G:(DE-HGF)POF4-134},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000621477800001},
      doi          = {10.1088/1741-4326/abdded},
      url          = {https://juser.fz-juelich.de/record/904052},
}