Computer control of power in a nuclear reactor

Asok Ray, David D. Lanning

Research output: Contribution to journalArticlepeer-review

1 Scopus citations


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
Issue number1
StatePublished - Feb 1983

All Science Journal Classification (ASJC) codes

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


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