Published August 1992
| Version v1
Journal article
Construction and evaluation of fault detection network for signal validation
Creators
- 1. Dept. of Nuclear Engineering, National Tsing Hua Univ., Hsinchu (Taiwan, Province of China)
Description
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
Additional details
Publishing Information
- Journal Title
- IEEE Transactions on Nuclear Science
- Journal Volume
- 39
- Journal Issue
- 4
- Journal Page Range
- p. 943-947.
- ISSN
- 0018-9499
- CODEN
- IETNAE
Conference
- Title
- 1991 Institute of Electrical and Electronic Engineers (IEEE) nuclear science symposium and medical imaging conference.
- Dates
- 2-9 Nov 1991.
- Place
- Santa Fe, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24033346
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; AUTOMATION; COMPUTER NETWORKS; EVALUATION; FAULT TREE ANALYSIS; MICROPROCESSORS; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; REACTOR CONTROL SYSTEMS; REACTOR MONITORING SYSTEMS; SAFETY ENGINEERING; STEAM GENERATORS
- Descriptors DEC
- BOILERS; CONTROL SYSTEMS; ELECTRONIC CIRCUITS; ENRICHED URANIUM REACTORS; MICROELECTRONIC CIRCUITS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911106--.