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격납건물 국부누설률시험 표준절차 개발

Development of Standard Procedures for Local Leakage Rate Testing of Containment Vessel

  • 문용식 (한국수력원자력 중앙연구원) ;
  • 김창수 (한국수력원자력 중앙연구원)
  • 투고 : 2012.08.04
  • 심사 : 2012.08.24
  • 발행 : 2012.09.01

초록

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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