• DocumentCode
    1949476
  • Title

    A proposed scraper element to protect the end of the W7-X divertor target elements

  • Author

    Peacock, A. ; Kisslinger, J. ; Boscary, J. ; Geiger, J. ; Hurd, F. ; König, R. ; Krychowiak, M. ; Stadler, R. ; Smirnow, M. ; Tretter, J. ; Werner, A.

  • Author_Institution
    Eur. Comm., EURATOM Assoc., Garching, Germany
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    The three main areas of the W7-X divertor target are: the horizontal target, the vertical target and the high iota tail, with a pumping gap between the horizontal and vertical targets. For each of the standard operational scenarios the target has been designed so that, based on vacuum field calculations, the plasma strike points lie away from the ends of the target. Each target consists of CFC armoured water cooled poloidally running target elements capable of operating reliably in these central regions at up to 10MW/m2 in steady state operation, as necessary for the standard configurations. Due to the U-turn shape of the cooling channel at the pumping gap end of the elements the cooling is not optimal and a reduced performance is expected. However, recent studies of experiment scenarios, also now taking into account the influence of bootstrap currents, showed that the strike point drifts over the ends of the target elements adjacent to the pumping gap on the L/R time scale; potentially leading to damage of the elements in these scenarios. Various operational methods have been studied to satisfactorily avoid this situation without success. The paper describes design changes being made to improve the ability of the end of the elements to accept reasonable power levels, however it is not expected that the elements in these regions will meet the full power requirements. Hence, this paper also describes the design of a protection element; the purpose of this so-called “scraper element” is to intercept the power to the targets before the full power reaches the sensitive end of the elements. This is done without reducing significantly the pumping at the pumping gap and addresses issues such as how to control local impurity flows. The programme of work concerning design and technology qualification still needed to realise this scraper element is described.
  • Keywords
    fusion reactor design; fusion reactor divertors; fusion reactor targets; plasma impurities; plasma toroidal confinement; plasma transport processes; stellarators; CFC armoured water cooled poloidally running target elements; W7-X divertor target element; bootstrap current; high iota tail; horizontal target; local impurity flow control; plasma strike point; pumping gap; scraper element analysis; steady state operation; vacuum field calculations; vertical target; Cooling; Heating; Divertor; W7-X; plasma target;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
  • Conference_Location
    Chicago, IL
  • ISSN
    1078-8891
  • Print_ISBN
    978-1-4577-0669-1
  • Electronic_ISBN
    1078-8891
  • Type

    conf

  • DOI
    10.1109/SOFE.2011.6052300
  • Filename
    6052300