• DocumentCode
    864219
  • Title

    Computer Control of Power in a Nuclear Reactor

  • Author

    Ray, Asok ; Bernard, John A. ; Lanning, David D.

  • Author_Institution
    The Charles Stark Draper Laboratory, Inc. 555 Technology Square Cambridge, Massachusetts 02139
  • Volume
    30
  • Issue
    1
  • fYear
    1983
  • Firstpage
    820
  • Lastpage
    824
  • Abstract
    A signal validation methodology has been simultaneously applied to the on-line fault diagnosis of neutron flux detectors, primnary coolant flow and temperature sensors, and to the computer control of power in an operating nuclear reactor. A CRT display presents the validated data and sensor diagnostics. The feedback signal to the controller is a digitally processed, weighted average of several valid power sensor signals where the weights are not a priori fixed but dependent on the a posteriori probabilities of failure of individual sensors computed on the basis of past and current observations.
  • Keywords
    Cathode ray tubes; Coolants; Detectors; Fault detection; Fault diagnosis; Fission reactors; Neutrons; Signal processing; Temperature control; Temperature sensors;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.1983.4332384
  • Filename
    4332384