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
Link To Document :
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