Electrical Condition Monitoring of Low Voltage Nuclear Power Plant Cables: tanδ and Capacitance

Author(s):  
Angel Asipuela ◽  
Ehtasham Mustafa ◽  
Ramy.S.A. Afia ◽  
Tamus Zoltan Adam ◽  
Muhammad Yousaf Ali Khan
Author(s):  
Ki Sig Kang

The International Atomic Energy Agency (IAEA) organized an international Coordinated Research Project (CRP) on qualification, condition monitoring, and management of low voltage cables for life management in nuclear power plant. A total of 16 organizations from Technical Service Organizations (TSOs), and Research & Development Organization participated in the CRP and tested and presented their experimental results. The CRP members are actively engaged in providing cable samples, thermal and radiation ageing of cables, and electrical, mechanical, and chemical testing of cables samples. Preliminary analysis of the test data received show that, for some of the Condition Monitoring (CM) methods, good correlation is observed with ageing time and there is consistency in measurements between the different test labs carrying out the tests. The level of correlation with ageing time and the degree of variability between labs is dependent on the material being tested and the CM method being used.


2019 ◽  
Vol 64 (1) ◽  
pp. 20-32 ◽  
Author(s):  
Ehtasham Mustafa ◽  
Ramy S. A. Afia ◽  
Zoltán Ádám Tamus

The low voltage cables in the nuclear power plant have the same importance as veins have in the human body. Since, the cables inside the containment are under a number of environmental stress, out which the thermal and radiation stresses are important and become more effective with the presence of oxygen. These stresses cause the degradation of the insulation and hence may lead to insulation failure. To study the behavior of the cables under the nuclear power plant environmental stress, the cables are subjected to accelerated aging tests in laboratories which helps in determining their withstand capacity and degradation behavior in the harsh thermal-radiation environment. In this paper, the accelerated aging tests conditions are discussed with the focus on the role of certain uncertainty factors which effect the aging markers during the condition monitoring of the insulation material of cable after the accelerated aging tests. This review has been put into a framework to better understand the aging process in the low voltage nuclear power plant cables. In the conclusion part, some future directions in the field of the thermal-radiation multi-stress accelerated aging tests and condition monitoring techniques are also identified.


2005 ◽  
Vol 127 (3) ◽  
pp. 230-236 ◽  
Author(s):  
Min-Rae Lee ◽  
Joon-Hyun Lee ◽  
Jung-Teak Kim

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.


2013 ◽  
Vol 284-287 ◽  
pp. 1749-1753
Author(s):  
Kyung Nam Jang ◽  
Jong Soeg Kim ◽  
Sun Chul Jeong ◽  
Kyung Heum Park ◽  
Sung Yull Hong

In nuclear power plants, there are many cables that perform safety-related functions. These cables should implement condition monitoring during the operation period in the nuclear power plant, in order to assess the remaining qualified life and extend the qualified life. In this study we focused on the indenting method which can measure the hardness of the cable jacket. This method is selected because it is non-destructive and requires short testing time and small sized equipment. In order to address the problems with the existing indenting test equipment, we developed new indenting test equipment, which could automatically move on the surface of the object cable. The newly developed equipment is designed for a small-sized and light-weight robot using wireless communication in order to implement condition monitoring in a harsh environment or locations that are inaccessible to the tester. The developed wireless cable indenting robot is composed of three parts, which are mechanical and electrical hardware parts and remote-control part. In order to analyze the degradation tendency of the cable, we prepared four thermally aged specimens and one un-aged specimen. Using the developed robot, we measured the modulus of the cable jacket of each specimen. The test data showed that the modulus of the cable jacket increased linearly as the accelerated aging time increased. From these results, we can analyze the degradation trends pertaining to cables installed in nuclear power plant according to the operation period.


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