Modeling of PWR plant by multilevel flow model and its application in fault diagnosis
- 1. Kyoto Univ., Graduate School of Energy Science, Kyoto (Japan)
- 2. Power and Nuclear Engineering College of Harbin Engineering Univ., Harbin (China)
Description
The paper describes the application of Multilevel Flow Modeling (MFM) - a modeling method in means-end and part-whole way, in interface design of supervisory control of Pressurized Water Reactor (PWR) plant, and automatic real-time fault diagnosis of PWR accident. The MFM decomposes the complex plant process from the main goal to each component at multiple levels to represent the contribution of each component to the whole system to make clear how the main goal of the system is achieved. The plant process is described abstractly in function level by mass, energy and information flows, which represent the interaction between different components and enable the causal reasoning between functions according to the flow properties. Thus, in the abnormal status, a goal-function-component oriented fault diagnosis can be performed with the model at a very quick speed and abnormal alarms can be fully explained by the reasoning relationship of the model. In this paper, an interface design of the PWR plant is built by the conception of means-end nad part-whole by using MFM, and several simulation cases are used for evaluating the fault diagnosis performance. The results show that the system has a good ability to detect and diagnose accidents timely before reactor trip. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 42
- Journal Issue
- 8
- Journal Page Range
- p. 695-705
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36112172
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALGORITHMS; DIAGNOSTIC TECHNIQUES; ENERGY; FAULT TREE ANALYSIS; FLOW MODELS; FLOWSHEETS; HUMAN FACTORS; INFORMATION; MAN-MACHINE SYSTEMS; MASS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR OPERATORS; SIMULATION
- Descriptors DEC
- ACCIDENTS; DIAGRAMS; ENRICHED URANIUM REACTORS; INFORMATION; MATHEMATICAL LOGIC; MATHEMATICAL MODELS; PERSONNEL; POWER REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 19 refs., 14 figs., 6 tabs.