Signal processing method based on energy ratio for detecting leakage of SG using EVFM

Xu Wei; Xu Ke-Jun; Yan Xiao-Xue; Yu Xin-Long; Wu Jian-Ping; Xiong Wei

doi:10.1016/j.net.2020.01.023

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자료유형: 학술저널

저자정보: Xu Wei (School of Electrical and Automation Engineering Hefei University of Technology) Xu Ke-Jun (School of Electrical and Automation Engineering Hefei University of Technology) Yan Xiao-Xue (School of Electrical and Automation Engineering, Hefei University of Technology) Yu Xin-Long (School of Electrical and Automation Engineering Hefei University of Technology) Wu Jian-Ping (School of Electrical and Automation Engineering, Hefei University of Technology) Xiong Wei (School of Electrical and Automation Engineering Hefei University of Technology)

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제8호

발행연도: 2020.8

수록면: 1,677 - 1,688 (12page)

DOI: 10.1016/j.net.2020.01.023

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In the sodium-cooled fast reactor, the steam generator is a heat exchange device between sodium and water, which may cause leakage, resulting in a sodium-water reaction accident, which in turn affects the safe operation of the entire nuclear reactor. To this end, the electromagnetic vortex flowmeter is used to detect leakage of the steam generator and its signal processing method is studied in this paper. The hydraulic experiment was carried out by using water instead of liquid sodium, and the sensor output signal of the electromagnetic vortex flowmeter under different gas injection volumes was collected. The bubble noise signal is reflected by the base line of the sensor output signal. According to the relationship between the proportion of the bubble noise signal in the sensor output signal and the gas injection volume, a signal processing method based on the energy ratio calculation is proposed to detect whether the water contains bubbles. The gas injection experiment of liquid sodium was conducted to verify the effectiveness of the signal processing method in the detection of bubbles in sodium, and the minimum detectable leak rate of water in the steam generator was detected to be 0.2 g/s.

#Sodium-cooled fast reactor #Steam generator #Leak detection #Electromagnetic vortex flowmeter #Signal processing method

참고문헌 (34)

참고문헌 신청

K.K. Rajan / 2016 / Sodium flow measurement in large pipelines of sodium cooled fast breeder reactors with bypass type flow meters / Ann. Nucl. Energy 87:74~80

S. Kishore / 2012 / An experimental study on impingement wastage of Mod 9Cr 1Mo steel due to sodium water reaction / Nucl. Eng. Des 243:49~55

D. J. Hayes / 1978 / Water leaks in sodium-heated fast reactor boilers / Phys. Technol 9(3):96

B. Raj / 2002 / Development of fuels and structural materials for fast breeder reactors / Sadhana 27(5):527~558

Ji-Young Jeong / 2009 / Analysis of micro-leak sodium-water reaction phenomena in a sodium-cooled fast reactor steam generator / Korean Journal of Chemical Engineering 26(4):1004~1008

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