• DocumentCode
    807510
  • Title

    Preparation of a Standard Technique for Determination of Neutron Equivalence for Bulk Damage in Silicon

  • Author

    Green, M.L. ; Thatcher, R.K.

  • Author_Institution
    Battelle Columbus Laboratories Columbus, Ohio 43201
  • Volume
    19
  • Issue
    6
  • fYear
    1972
  • Firstpage
    200
  • Lastpage
    208
  • Abstract
    This report defines how a neutron energy (1 MeV) equivalence should be calculated and the limitations of its utility. The differences in the l-MeV equivalence obtained by using Messenger´s expression for the damage curve is examined. An experiment was performed to verify the adequacy and utility of using l-MeV equivalence units to compare different neutron spectra. It is shown that for fission spectra close to a bare reactor that l-MeV equivalence provides a slight improvement in the correlation of data taken from devices irradiated at different reactors. However, this improvement in correlation did not extend to devices irradiated with 14 MeV neutrons. The devices irradiated in this experiment showed a fission/fusion fluence ratio for equal damage of about 1.7 rather than the expected value of 2.5.
  • Keywords
    Accuracy; Design engineering; Dosimetry; Inductors; Laboratories; Mathematical model; Neutrons; Performance evaluation; Silicon; System testing;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.1972.4326833
  • Filename
    4326833