Construction and evaluation of fault detection network for signal validation
Conference
·
· IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (United States)
OSTI ID:7145006
- Dept. of Nuclear Engineering, National Tsing Hua Univ., Hsinchu (Taiwan, Province of China)
The paper presents a methodology which performs evaluation and construction of a sensor failure detection network for nuclear power plant signal validation. The network is arranged in a fault tree structure which consists of sensors, mathematical models for sensor relations and decision/estimators derived form parity relations. The evaluation scheme performs a logic state analysis to categorize critical signals and the associated sensors. The construction scheme cooperates with the evaluation scheme to build a detection network automatically using a rule-based algorithm. The package is implemented on a microcomputer and is demonstrated for the nuclear steam supply system of a PWR.
- OSTI ID:
- 7145006
- Report Number(s):
- CONF-911106--
- Conference Information:
- Journal Name: IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (United States) Journal Volume: 39:4
- Country of Publication:
- United States
- Language:
- English
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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
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALGORITHMS
AUTOMATION
BOILERS
COMPUTER NETWORKS
COMPUTERS
CONTROL SYSTEMS
ELECTRONIC CIRCUITS
ENGINEERING
ENRICHED URANIUM REACTORS
EVALUATION
FAULT TREE ANALYSIS
MATHEMATICAL LOGIC
MICROELECTRONIC CIRCUITS
MICROPROCESSORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR MONITORING SYSTEMS
REACTORS
SAFETY ENGINEERING
STEAM GENERATORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
THERMAL REACTORS
VAPOR GENERATORS
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
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALGORITHMS
AUTOMATION
BOILERS
COMPUTER NETWORKS
COMPUTERS
CONTROL SYSTEMS
ELECTRONIC CIRCUITS
ENGINEERING
ENRICHED URANIUM REACTORS
EVALUATION
FAULT TREE ANALYSIS
MATHEMATICAL LOGIC
MICROELECTRONIC CIRCUITS
MICROPROCESSORS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR CONTROL SYSTEMS
REACTOR MONITORING SYSTEMS
REACTORS
SAFETY ENGINEERING
STEAM GENERATORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS