Computer control of power in a nuclear reactor

Asok Ray, David D. Lanning

    Research output: Contribution to journalArticle

    1 Scopus citations

    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

    All Science Journal Classification (ASJC) codes

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

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