Development and testing of an integrated signal validation system for nuclear power plants
Since the incident at Three Mile Island unit 2, computerized plant status display, implementation of human factors in control room design, and plant monitoring based on expert system technology have seen a tremendous growth. One such proposed operator assist device is a plant signal validation system. This system is used to check the consistency of redundant measurements (sensors) of selected process variables, estimate their expect values from plant-wide data, and detect, isolate and characterize the type of anomaly in the instrument channel outputs. In large process control systems signals from several hundred instrument channels are routed via data highways to control systems, protection (safety) systems and plant monitoring systems. The need of automated signal validation is necessary because of the large amount of information available, and as a result the operator's inability to validate information from many diverse sources. This is also useful for improved plant control (minimize challenges on control systems), minimizing plant downtime, and for predictive maintenance advising. 107 refs., 56 figs., 6 tabs.
- Research Organization:
- Combustion Engineering, Inc., Stamford, CT (USA); Tennessee Univ., Knoxville, TN (USA). Dept. of Nuclear Engineering
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC02-86NE37959
- OSTI ID:
- 5229987
- Report Number(s):
- DOE/NE/37959-34-Vol.1; ON: DE90003354; TRN: 90-002831
- Country of Publication:
- United States
- Language:
- English
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REACTOR INSTRUMENTATION
HTGR TYPE REACTORS
LMFBR TYPE REACTORS
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
INFORMATION VALIDATION
COMPUTER ARCHITECTURE
COMPUTERIZED CONTROL SYSTEMS
DATA TRANSMISSION SYSTEMS
DATA-FLOW PROCESSING
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EBR-2 REACTOR
EXPERIMENTAL DATA
EXPERT SYSTEMS
FAULT TREE ANALYSIS
LOGIC CIRCUITS
MATHEMATICAL MODELS
MEASURING METHODS
PROGRESS REPORT
REACTOR SAFETY
RESEARCH PROGRAMS
TECHNOLOGY TRANSFER
TRANSIENTS
BREEDER REACTORS
CONTROL SYSTEMS
DATA
DOCUMENT TYPES
ELECTRONIC CIRCUITS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
NUMERICAL DATA
POWER REACTORS
PROGRAMMING
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM COOLED REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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210300 - Power Reactors
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990200 - Mathematics & Computers
220900 - Nuclear Reactor Technology- Reactor Safety