Development of an integrated signal validation system in nuclear power plants: Annual report for the period September 30, 1986-September 29, 1987
Technical Report
·
OSTI ID:6157381
In large power generating stations, signals from various instrumentation systems are channeled to control systems, protection systems, and plant monitoring systems. Validation of these signals accomplishes the following goals: minimize plant downtime, increase the reliability of operator decisions, and as an aid for scheduling plant maintenance. The signal validation methods developed under this project are designed to perform various levels of signal processing, and to detect, isolate and characterize faulty signals. A central database stores information about sensors, history of signal validation results, plant data, and subsystem models. The signal validation architecture consists of parallel signal processing modules, each of which implements a diverse validation scheme. The software development and testing of all the modules is performed using IBM PC/AT computers. All the signal validation modules are ready for preliminary implementation and are tested using operational data from a pressurized water reactor (PWR) and PWR data from the Combustion Engineering Nuclear Transient Simulation code.
- Research Organization:
- Tennessee Univ., Knoxville (USA). Dept. of Nuclear Engineering; Combustion Engineering, Inc., Windsor, CT (USA)
- DOE Contract Number:
- AC02-86NE37959
- OSTI ID:
- 6157381
- Report Number(s):
- DOE/NE/37959-12; ON: DE88000187
- Country of Publication:
- United States
- Language:
- English
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Signal validation in nuclear power plants: Annual progress report for the period September 30, 1986-September 29, 1987
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Fri May 01 00:00:00 EDT 1987
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Development and testing of an Integrated Signal Validation System for nuclear power plants: Annual report for the period September 30, 1987--September 29, 1988
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210100 -- Power Reactors
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Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALGORITHMS
BWR TYPE REACTORS
COMMUNICATIONS
COMPUTER ARCHITECTURE
COMPUTER CODES
COMPUTERS
CONTROL SYSTEMS
DATA BASE MANAGEMENT
DATA COVARIANCES
DATA TRANSMISSION
DATA-FLOW PROCESSING
EXPERT SYSTEMS
FORTRAN
G CODES
IBM COMPUTERS
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MATHEMATICAL LOGIC
MATHEMATICS
MULTIVARIATE ANALYSIS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
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POWER PLANTS
PROGRAMMING
PROGRAMMING LANGUAGES
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR INSTRUMENTATION
REACTOR NOISE
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RESEARCH AND TEST REACTORS
SIGNALS
STATISTICS
STEADY-STATE CONDITIONS
TESTING
THERMAL POWER PLANTS
VALIDATION
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WATER MODERATED REACTORS