• DocumentCode
    3172220
  • Title

    The importance of using the mixed neutron flux in activation analysis of D-3He fueled reactors

  • Author

    Khater, H.Y. ; Sawan, M.E.

  • Author_Institution
    Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    613
  • Abstract
    It is emphasized that the mixed neutron source should always be used in any activation and safety analysis performed for D-3He reactors. It is noted that performing any activation analysis by using the two components of the neutron source (D-D and D-T) separately leads to overestimating the induced activity. The overestimation is determined by the destruction rate of the parent atoms, the magnitude of the neutron flux, the reactor operation time, and the radionuclide half-life. The overestimation was found to be more pronounced for short and intermediate lived nuclides. In a typical D- 3He reactor, the overestimation in the calculated activity and decay heat was as high as 40% after 30 years of reactor operation. In the meantime, the offsite dose was overestimated by 27%
  • Keywords
    Tokamak devices; fusion reactor safety; 3He; D; D-3He fueled reactors; decay heat; mixed neutron source; neutron flux; radionuclide half-life; reactor operation time; safety analysis; Accidents; Activation analysis; Atomic measurements; Deuterium; Helium; Inductors; Isotopes; Neutrons; Plasma sources; Steel;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-0132-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1991.218846
  • Filename
    218846