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@PHDTHESIS{Blommaert:829752,
      author       = {Blommaert, Maarten},
      title        = {{A}utomated {M}agnetic {D}ivertor {D}esign for {O}ptimal
                      {P}ower {E}xhaust},
      volume       = {365},
      school       = {RWTH Aachen},
      type         = {Dr.},
      address      = {Jülich},
      publisher    = {Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag},
      reportid     = {FZJ-2017-03386},
      isbn         = {978-3-95806-216-0},
      series       = {Schriften des Forschungszentrums Jülich Reihe Energie $\&$
                      Umwelt / Energy $\&$ Environment},
      pages        = {xxiv, 219 S.},
      year         = {2017},
      note         = {RWTH Aachen University, Diss., 2016n},
      abstract     = {The so-called divertor is the standard particle and power
                      exhaust system of nuclear fusion tokamaks. In essence, the
                      magnetic configuration hereby `diverts' the plasma to a
                      specific divertor structure. The design of this divertor is
                      still a key issue to be resolved to evolve from experimental
                      fusion tokamaks to commercial power plants. The focus of
                      this dissertation is on one particular design requirement:
                      avoiding excessive heat loads on the divertor structure. The
                      divertor design process is assisted by plasma edge transport
                      codes that simulate the plasma and neutral particle
                      transport in the edge of the reactor. These codes are
                      computationally extremely demanding, not in the least due to
                      the complex collisional processes between plasma and
                      neutrals that lead to strong radiation sinks and macroscopic
                      heat convection near the vessel walls. One way of improving
                      the heat exhaust is by modifying the magnetic confinement
                      that governs the plasma flow. In this dissertation,
                      automated design of the magnetic configuration is pursued
                      using adjoint based optimization methods. A simple and fast
                      perturbation model is used to compute the magnetic field in
                      the vacuum vessel. A stable optimal design method of the
                      nested type is then elaborated that strictly accounts for
                      several nonlinear design constraints and code limitations.
                      Using appropriate cost function deffnitions, the heat is
                      spread more uniformly over the high-heat load plasma-facing
                      components in a practical design example. Furthermore,
                      practical in-parts adjoint sensitivity calculations are
                      presented that provide a way to an efficient optimization
                      procedure. Results are elaborated for a fictituous JET
                      (Joint European Torus) case [...]},
      cin          = {IEK-4},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)3 / PUB:(DE-HGF)11},
      url          = {https://juser.fz-juelich.de/record/829752},
}