• DocumentCode
    1949724
  • Title

    Improved geometrical design of the US DCLL ITER test blanket module

  • Author

    Marriott, E. ; Sawan, M. ; Dagher, M. ; Wong, C.

  • Author_Institution
    Fusion Technol. Inst., Univ. of Wisconsin-Madison, Madison, WI, USA
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    Computational fluid dynamics simulations have demonstrated flow problems within the helium flow path in the current US DCLL ITER test blanket module design. New geometry for the helium flow path has been designed that will improve flow evenness and simplify the overall helium flow path within the test blanket module while maintaining the overall test blanket module geometry. Global changes to the test blanket module geometry can be implemented based on these improvements.
  • Keywords
    Tokamak devices; computational fluid dynamics; fusion reactor blankets; fusion reactor design; US DCLL ITER test blanket module; computational fluid dynamics; flow problem; geometrical design; helium flow path; Assembly; Heating; Helium; CFD; ITER; blanket; test blanket module;
  • 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.2011.6052310
  • Filename
    6052310
    • Link To Document
    https://search.isc.ac/dl/search/defaultta.aspx?DTC=49&DC=1949724