Signal validation in nuclear power plants using redundant measurements
Conference
·
OSTI ID:5741250
This paper discusses the basic principles of a multivariable signal validation software system utilizing redundant sensor readings of process variables in nuclear power plants (NPPs). The technique has been tested in numerical experiments, and was applied to actual data from a pressurized water reactor (PWR). The simultaneous checking within one redundant measurement set, and the cross-checking among redundant measurement sets of dissimilar process variables, results in an algorithm capable of detecting and isolating bias-type errors. A case in point occurs when a majority of the direct redundant measurements of more than one process variable has failed simultaneously by a common-mode or correlated failures can be detected by the developed approach. 5 refs.
- Research Organization:
- Tennessee Univ., Knoxville, TN (USA). Dept. of Nuclear Engineering
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC02-86NE37959
- OSTI ID:
- 5741250
- Report Number(s):
- DOE/NE/37959-32; CONF-8906196--1; ON: DE89015746
- Country of Publication:
- United States
- Language:
- English
Similar Records
Generalized consistency checking of multivariable redundant measurements (GCCM) and common-mode failure detection
Signal validation using simultaneous consistency checking of multivariable measurements
Generalized consistency checking of multivariable redundant measurements and common-mode failure detection
Technical Report
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6457472
Signal validation using simultaneous consistency checking of multivariable measurements
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Transactions of the American Nuclear Society; (USA)
·
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Generalized consistency checking of multivariable redundant measurements and common-mode failure detection
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6125416
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
ALGORITHMS
COMPUTER CODES
M CODES
MATHEMATICAL LOGIC
MEASURING METHODS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
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THERMAL POWER PLANTS
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WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
ALGORITHMS
COMPUTER CODES
M CODES
MATHEMATICAL LOGIC
MEASURING METHODS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
SIGNALS
TESTING
THERMAL POWER PLANTS
VALIDATION
WATER COOLED REACTORS
WATER MODERATED REACTORS