Process hypercube comparison for signal validation
Journal Article
·
· IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (United States)
- Arizona State Univ., Tempe, AZ (United States). Dept. of Electrical Engineering
The optimal control and safe operation of a nuclear power plant requires reliable information concerning the state of the process. Signal validation is the detection, isolation, and characterization of faulty signals. Properly validated process signals are beneficial from the standpoint of increased plant availability and reliability of operator actions. This paper reports on a signal validation technique utilizing a process hypercube comparison (PHC) originated during this research. The hypercube is merely a multidimensional joint histogram of the process conditions. The hypercube is created off-line during a learning phase using operational plant data. In the event that a newly observed plant state does not match with those in the learned hypercube, the PHV algorithm performs signal validation by progressively hypothesizing that one or more signals is in error. This assumption is then either substantiated or denied. In the case where many signals are found to be in error, a conclusion that the process conditions are abnormal is reached. The global data base contained within the hypercube provides a best estimate of the process conditions in the event a signal is deemed failed. The hypercube signal validation methodology was tested using operational data from a commercial pressurized water reactor (PWR) and the Experimental Breeder Reactor II (EBR-II). This research was part of a larger project aimed at the development of a comprehensive signal validation software system for application to nuclear power plants.
- OSTI ID:
- 5081469
- Journal Information:
- IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (United States), Journal Name: IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (United States) Vol. 38:2; ISSN 0018-9499; ISSN IETNA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
BREEDER REACTORS
COMPUTERS
CONTROL SYSTEMS
EBR-2 REACTOR
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HYPERCUBE COMPUTERS
INFORMATION VALIDATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL LOGIC
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
SIGNALS
SODIUM COOLED REACTORS
TESTING
THERMAL POWER PLANTS
THERMAL REACTORS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
BREEDER REACTORS
COMPUTERS
CONTROL SYSTEMS
EBR-2 REACTOR
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HYPERCUBE COMPUTERS
INFORMATION VALIDATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL LOGIC
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OPERATION
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR OPERATION
REACTORS
RESEARCH AND TEST REACTORS
SIGNALS
SODIUM COOLED REACTORS
TESTING
THERMAL POWER PLANTS
THERMAL REACTORS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS