• DocumentCode
    790003
  • Title

    The use of a Gamma Sensitive Detector to Measure Thermal Reactor Power

  • Author

    Czaika, J. ; Kerr, W.

  • Author_Institution
    Department of Nuclear Engineering the University of Michigan Ann Arbor, Michigan 48105
  • Volume
    16
  • Issue
    1
  • fYear
    1969
  • Firstpage
    255
  • Lastpage
    259
  • Abstract
    A study was made of the feasibility of measuring power output of a thermal reactor with a gamma sensitive detector. Shielding was used to selectively attenuate gammas from fission products as compared to(n,r) reactions and prompt fission gammas. Measurements indicate agreement between detector response and reactor power output, determined independently, over more than three decades. There is evidence that effects of local neutron flux perturbations, seen by neutron chambers, are ignored by the gamma detector.
  • Keywords
    Delay; Electromagnetic wave absorption; Fission reactors; Gamma ray detection; Gamma ray detectors; Gamma rays; Inductors; Neutrons; Nuclear measurements; Power measurement;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.1969.4325115
  • Filename
    4325115