Fault diagnosis and severity estimation in nuclear power plants - 196
Creators
- 1. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory Harbin Engineering University Harbin (China)
- 2. Nuclear Power Plant Development Directorate, Nigeria Atomic Energy Commission, Abuja (Nigeria)
- 3. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin (China)
Description
Signed Directed Graph (SDG) is a type of fault diagnosis method with a capability to display the complex relationship between plant parameters and reveal the potential danger and the propagation path when a fault occurs in a nuclear plant. However, the fault diagnosis method based on qualitative SDG model inevitably has a number of disadvantages, and some of these disadvantages include its inability to identify reoccurring faults; ambiguous reasoning that can result in low resolution; performance that relies on the accuracy of the model; slow diagnosis rate for large systems and poor real-time diagnosis, among others. In this paper, we propose an SDG fault diagnosis methodology based on Granular Computing Theory, referred to as Granular Computing Signed Directed Graph (GCSDG). This paper shows how knowledge reduction nature of granular computing based fault diagnosis can simplify the decision table, reduce the allocation of resources, scale-down the complexity of the problem and improve the efficiency of data processing. Then, we estimate the severity of the fault using Back Propagation (BP) neural network approach. The proposed methodology was verified by considering certain faults in the primary loop of a PWR, using PCTRAN. The result shows a considerable improvement in fault diagnosis and the severity estimated serves as a useful information for the operator, providing a firm foundation for further intervention. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 12 p.
Conference
- Title
- 10. International Conference on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
- Acronym
- NPIC and HIMIT 2017
- Dates
- 11-15 Jun 2017
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52075697
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA PROCESSING; DIAGNOSIS; FAULT TREE ANALYSIS; NEURAL NETWORKS; NUCLEAR POWER PLANTS; PERFORMANCE; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RESOLUTION
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PROCESSING; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)