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
- Country of Publication:
- United States
- Language:
- English
Similar Records
Development and testing of an Integrated Signal Validation System for nuclear power plants: Annual report for the period September 30, 1987--September 29, 1988
Signal validation using simultaneous consistency checking of multivariable measurements
An integrated architecture for signal validation in power plants
Technical Report
·
Thu Sep 01 00:00:00 EDT 1988
·
OSTI ID:6628053
Signal validation using simultaneous consistency checking of multivariable measurements
Conference
·
Wed Jun 01 00:00:00 EDT 1988
·
OSTI ID:6720715
An integrated architecture for signal validation in power plants
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:7099472
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BREEDER REACTORS
BWR TYPE REACTORS
COMPUTER ARCHITECTURE
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DATA
DATA TRANSMISSION SYSTEMS
DATA-FLOW PROCESSING
DECISION MAKING
DOCUMENT TYPES
EBR-2 REACTOR
ELECTRONIC CIRCUITS
EPITHERMAL REACTORS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
EXPERT SYSTEMS
FAST REACTORS
FAULT TREE ANALYSIS
FBR TYPE REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
INFORMATION
INFORMATION VALIDATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOGIC CIRCUITS
MATHEMATICAL MODELS
MEASURING METHODS
NUMERICAL DATA
POWER REACTORS
PROGRAMMING
PROGRESS REPORT
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
SODIUM COOLED REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TECHNOLOGY TRANSFER
TESTING
TRANSIENTS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BREEDER REACTORS
BWR TYPE REACTORS
COMPUTER ARCHITECTURE
COMPUTERIZED CONTROL SYSTEMS
CONTROL SYSTEMS
DATA
DATA TRANSMISSION SYSTEMS
DATA-FLOW PROCESSING
DECISION MAKING
DOCUMENT TYPES
EBR-2 REACTOR
ELECTRONIC CIRCUITS
EPITHERMAL REACTORS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
EXPERT SYSTEMS
FAST REACTORS
FAULT TREE ANALYSIS
FBR TYPE REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
INFORMATION
INFORMATION VALIDATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOGIC CIRCUITS
MATHEMATICAL MODELS
MEASURING METHODS
NUMERICAL DATA
POWER REACTORS
PROGRAMMING
PROGRESS REPORT
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
SODIUM COOLED REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TECHNOLOGY TRANSFER
TESTING
TRANSIENTS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS