Computer control of power in a nuclear reactor

Asok Ray, David D. Lanning

    Research output: Contribution to journalArticle

    1 Citation (Scopus)

    Abstract

    A signal validation methodology has been simultaneously applied to the on-line fault diagnosis of neutron flux detectors, primary 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.

    Original languageEnglish (US)
    Pages (from-to)820-824
    Number of pages5
    JournalIEEE Transactions on Nuclear Science
    Volume30
    Issue number1
    DOIs
    StatePublished - Jan 1 1983

    Fingerprint

    nuclear reactors
    Computer control
    Nuclear reactors
    sensors
    Sensors
    Neutron flux
    Cathode ray tubes
    Temperature sensors
    Coolants
    Failure analysis
    coolants
    temperature sensors
    flux (rate)
    Display devices
    Detectors
    Feedback
    controllers
    Controllers
    methodology
    detectors

    All Science Journal Classification (ASJC) codes

    • Nuclear and High Energy Physics
    • Nuclear Energy and Engineering
    • Electrical and Electronic Engineering

    Cite this

    Ray, Asok ; Lanning, David D. / Computer control of power in a nuclear reactor. In: IEEE Transactions on Nuclear Science. 1983 ; Vol. 30, No. 1. pp. 820-824.
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    Computer control of power in a nuclear reactor. / Ray, Asok; Lanning, David D.

    In: IEEE Transactions on Nuclear Science, Vol. 30, No. 1, 01.01.1983, p. 820-824.

    Research output: Contribution to journalArticle

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