Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)
- Volume 8 Issue 2
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- Pages.42-47
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- 2012
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- 1738-8333(pISSN)
DOI QR Code
Development of Standard Procedures for Local Leakage Rate Testing of Containment Vessel
격납건물 국부누설률시험 표준절차 개발
- Received : 2012.08.04
- Accepted : 2012.08.24
- Published : 2012.09.01
Abstract
The containment local leakage rate testing in nuclear power plants is performed in accordance with ANSI/ANS 56.8-1994 in Korea. Two methods, the make-up flow rate and the pressure decay, are used for local leakage rate testing. Though ANSI/ANS 56.8-1994 does not define clearly the minimum test duration for the make-up flow rate method, it requires obtaining the data after reaching the stable condition. Thus the prerequisite stable condition for data acquisition and the testing time is differently applied to each NPPs. Therefore, this study presents a standardized test procedure for data stabilization and testing time through experiments to improve the test reliability.
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