A generalized likelihood ratio approach to detecting and identifying failures in pressurizer instrumentation
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6768019
The generalized likelihood ratio (GLR) technique performs statistical tests on the innovations sequence of a Kalman filter state estimator. Using the results of these tests, failures in the sensors of a pressurized water reactor pressurizer are detected and identified. A third-order, linear model of the pressurizer dynamics, which is required by both the GLR and Kalman filter formulations, is developed from first principles. Using actual pressurizer data, the GLR method is employed to identify a bias in one of three level sensors.
- Research Organization:
- EG and G Idaho, Inc. P.O. Box 1625 Idaho Falls, Idaho 83415
- OSTI ID:
- 6768019
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 56:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Detection and identification of failures in PWR pressurizer instrumentation using generalized likelihood ratios
Bias identification in PWR pressurizer instrumentation using the generalized liklihood-ratio technique
Instrument failure monitoring in nuclear power systems
Technical Report
·
Fri May 01 00:00:00 EDT 1981
·
OSTI ID:5499549
Bias identification in PWR pressurizer instrumentation using the generalized liklihood-ratio technique
Conference
·
Wed Dec 31 23:00:00 EST 1980
·
OSTI ID:6551561
Instrument failure monitoring in nuclear power systems
Thesis/Dissertation
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6427188
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
DATA
DETECTION
DIGITAL FILTERS
ERRORS
EXPERIMENTAL DATA
FAILURE MODE ANALYSIS
FAILURES
INFORMATION
MATHEMATICAL MODELS
MATHEMATICS
MEASURING INSTRUMENTS
MONITORS
NUMERICAL DATA
PERFORMANCE TESTING
PRESSURIZERS
PROBABILITY
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
STATISTICS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
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
DATA
DETECTION
DIGITAL FILTERS
ERRORS
EXPERIMENTAL DATA
FAILURE MODE ANALYSIS
FAILURES
INFORMATION
MATHEMATICAL MODELS
MATHEMATICS
MEASURING INSTRUMENTS
MONITORS
NUMERICAL DATA
PERFORMANCE TESTING
PRESSURIZERS
PROBABILITY
PWR TYPE REACTORS
REACTOR INSTRUMENTATION
REACTORS
STATISTICS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS