• DocumentCode
    1950504
  • Title

    Nuclear analysis in support of the design of ITER blanket modules

  • Author

    Sawan, Mohamed E.

  • Author_Institution
    Fusion Technol. Inst., Univ. of Wisconsin-Madison, Madison, WI, USA
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    Detailed profiles of nuclear heating and radiation damage parameters were determined in ITER blanket modules at different poloidal locations. The results indicate that the nuclear parameters are sensitive to the configuration and material composition with enhanced steel heating and helium production in regions with large water content.
  • Keywords
    CAD; Tokamak devices; fusion reactor blankets; fusion reactor design; heat treatment; nuclear engineering computing; plasma toroidal confinement; radiation effects; ITER blanket module design; helium production; nuclear analysis; nuclear heating parameters; nuclear parameters; poloidal locations; radiation damage parameters; steel heating; Heating; Loading; Materials; ITER; blanket; nuclear heating; radiation damage;
  • 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.2011.6052350
  • Filename
    6052350
    • Link To Document
    https://search.isc.ac/dl/search/defaultta.aspx?DTC=49&DC=1950504