DocumentCode
485634
Title
Computerized Fault Diagnostics in a Nuclear Reactor via Analytic Redundancy
Author
Ray, Asok ; Geiger, Robert ; Desai, Mukund ; Deyst, John
Author_Institution
Staff Member, The Charles Stark Draper Laboratory, Inc. Cambridge, Massachusetts
fYear
1982
fDate
14-16 June 1982
Firstpage
784
Lastpage
791
Abstract
Computer-aided diagnostic techniques are successfully applied to on-line signal validation in an operating nuclear reactor. To avoid installation of additional redundant sensors for the sole purpose of fault isolation, a real-time model of nuclear instrumentation and the thermal-hydraulic process in the primary coolant loop is developed and experimentally validated. The model provides analytically redundant information sufficient for isolation of failed sensors as well as for detection of abnormal plant operation and component malfunctioning.
Keywords
Coolants; Energy measurement; Fluid flow measurement; Noise measurement; Position measurement; Power measurement; Q measurement; Redundancy; Thermal variables measurement; Time measurement;
fLanguage
English
Publisher
ieee
Conference_Titel
American Control Conference, 1982
Conference_Location
Arlington, VA, USA
Type
conf
Filename
4787962
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