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ASDEX Upgrade, Start-up and Operation

  • O. Gruber
  • ASDEX Upgrade Project Group
Part of the Ettore Majorana International Science Series book series (EMISS)

Abstract

ASDEX Upgrade, the next step after ASDEX in IPP’s tokamak programme, is designed to handle the efflux of charged particles and energy to the wall using a reactor-relevant poloidal field (PF) system with all coils located outside the toroidal field (TF) magnet in combination with reactor-like parameters in the plasma boundary layer1. Two options are available for this problem in a tokamak plasma and will be investigated in situ: pump limiters and divertors. In the limiter tokamak the last closed magnetic surface is tangent to the limiter, while in a divertor tokamak the divertor plates are removed frgm the main plasma. In present-day poloidal divertor tokamaks like ASDEX2, the divertor plates are far removed into separate chambers and hidden from the main plasma by the divertor coils which are placed inside the vacuum vessel and the TF coils (“closed” divertor; see Fig. 3). For a power producing tokamak with superconducting coils it is mandatory to place the PF coils outside the toroidal ones producing vertically elongated plasmas with an “open” divertor, i.e. the target plates are in direct line of sight of the main plasma (see Fig.5). Normal conducting coils are used in ASDEX Upgrade and no tritium operation is foreseen.

Keywords

Plasma Current Plasma Boundary Toroidal Field Current Rise Poloidal Field 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Springer Science+Business Media New York 1986

Authors and Affiliations

  • O. Gruber
    • 1
  • ASDEX Upgrade Project Group
    • 1
  1. 1.Max-Planck-Institut für PlasmaphysikEURATOM AssociationGarchingFed.Rep. Germany

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