• DocumentCode
    814
  • Title

    Modeling and Analysis of the W7-X High Heat-Flux Divertor Scraper Element

  • Author

    Lumsdaine, A. ; Boscary, J. ; Clark, Eppie ; Ekici, K. ; Harris, J. ; McGinnis, D. ; Lore, J.D. ; Peacock, Andrew ; Tipton, J. ; Tretter, J.

  • Author_Institution
    Oak Ridge Nat. Lab., Oak Ridge, TN, USA
  • Volume
    42
  • Issue
    3
  • fYear
    2014
  • fDate
    Mar-14
  • Firstpage
    545
  • Lastpage
    551
  • Abstract
    The Wendelstein 7-X stellarator experiment is scheduled for the completion of device commissioning and the start of first plasma in 2015. At the completion of the first two operational phases, the inertially cooled test divertor unit will be replaced with an actively cooled high heat-flux divertor, which will enable the device to increase its pulse length to steady-state plasma performance. Plasma simulations show that the evolution of bootstrap current in certain plasma scenarios produce excessive heat fluxes on the edge of the divertor targets. It is proposed to place an additional scraper element in the 10 divertor locations to intercept some of the plasma flux and reduce the heat load on these divertor edge elements. Each scraper element may experience a 500-kW steady-state power load, with localized heat fluxes as high as 20 MW/m2. Computational analysis has been performed to examine the thermal integrity of the scraper element. The peak temperature in the carbon-carbon fiber composite, the total pressure drop in the cooling water, and the increase in water temperature must all be examined to stay within specific design limits. Computational fluid dynamics modeling is performed to examine the flow paths through the multiple monoblock fingers as well as the thermal transfer through the monoblock swirl tube channels.
  • Keywords
    fusion reactor divertors; fusion reactor targets; stellarators; W7-X high heat-flux divertor scraper element; Wendelstein 7-X stellarator experiment; actively cooled high heat-flux divertor; bootstrap current evolution; carbon-carbon fiber composite; certain plasma scenarios; computational fluid dynamics modeling; divertor edge elements; divertor locations; divertor targets; heat load; inertially cooled test divertor unit; monoblock swirl tube channels; multiple monoblock fingers; peak temperature; plasma flux; plasma simulations; power 500 kW; scraper element thermal integrity; steady-state plasma performance; steady-state power load; total pressure drop; Computational fluid dynamics; Computational modeling; Cooling; Electron tubes; Finite element analysis; Heating; Plasmas; Divertor; Wendelstein 7-X (W7-X); heat flux; stellarator;
  • fLanguage
    English
  • Journal_Title
    Plasma Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0093-3813
  • Type

    jour

  • DOI
    10.1109/TPS.2014.2304695
  • Filename
    6746651