Condition Monitoring of a Nuclear Power Plant Check Valve Based on Acoustic Emission and a Neural Network

Author:

Lee Min-Rae1,Lee Joon-Hyun2,Kim Jung-Teak3

Affiliation:

1. Department of Mechanical Design Engineering, Pusan National University, Korea

2. School of Mechanical Engineering, Pusan National University, San 30 Jangjeon-dong, Kumjeong-gu, Pusan, 609-735, Korea

3. Man-Machine Interface System Team, Korea Atomic Energy Research Institute Yuseong, Daejeon, 305-600, Korea

Abstract

The analysis of acoustic emission (AE) signals produced during object leakage is promising for condition monitoring of the components. In this study, an advanced condition monitoring technique based on acoustic emission detection and artificial neural networks was applied to a check valve, one of the components being used extensively in a safety system of a nuclear power plant. AE testing for a check valve under controlled flow loop conditions was performed to detect and evaluate disk movement for valve degradation such as wear and leakage due to foreign object interference in a check valve. It is clearly demonstrated that the evaluation of different types of failure modes such as disk wear and check valve leakage were successful by systematically analyzing the characteristics of various AE parameters. It is also shown that the leak size can be determined with an artificial neural network.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference11 articles.

1. Haynes, H. D. , 1990, “Aging and Service Wear of Check Valves Used in Engineered Safety-Feature Systems of Nuclear Power Plants,” Technical Report No. NUREG/CR-4302, Vol. 2, U.S. Nuclear Regulatory Commission, Washington, DC. 20555.

2. U.S. Nuclear Regulatory Commission, 1988, “Nuclear Plant Aging Research (NPAR) Program Plan,” Technical Report No. NUREG-1144-Rev.2, NRC, June. 1991602-612.

3. Pool, A. J. and Porwit, A. J., 1982, “Prediction of Surge Pressure Form Check Valves for Nuclear,” ASME Paper No. 62-WA-219.

4. Gifford, A. P, Ronald, E. N. and Richard, E. D., 1953, “Characteristics of Various Check and Angle Stop Valves in an Eight-Inch Water Line,” Technical Report No. AECU-3180, U.S. Atomic Energy Commission, Schenectady, NY.

5. Analysis of Acoustic Emission Signals for Condition Monitoring of Check Valve at Nuclear Power Plants;Lee;Key Eng. Mater.

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