• Title/Summary/Keyword: Nuclear valve

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A Study on the Frequency Analyzing of Leak Evaluation m Valve for Power Plant Using AE (AE법에 의한 발전용 밸브누설평가를 위한 주파수분석 연구)

  • LEE SANG-GUK
    • Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
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    • 2004.05a
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    • pp.360-364
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    • 2004
  • The objective of this study is to estimate the feasibility of acoustic emission method Jar the internal leak from the valves in nuclear power plants. The acoustic emission method was applied to the valves at the site, and the background noise was measured for the abnormal plant condition. From the comparison of background noise data with the experimental results as to relation between leak flow and acoustic signal, the minimum leak flow rates that am be detected by acoustic signal was suggested. When the background noise level are higher than the acoustic signal, the method described below was considered that the analysis the remainder among the background noise frequency spectrum and the acoustic signal spectrum.

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피동형 원자로의 Hydraulic Valve에 관한 연구

  • 김융석;김상녕
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.430-436
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    • 1997
  • 피동형 원자로에서 냉각수 펌프의 작동불능시나 계통 내의 강제 순환이 충분치 못할 경우, 냉각수와 분리된 비상 저온 고농축의 붕산수를 노심에 피동으로 주입시키고 자연 대류에 의한 잔열 제거가 이루어져야 한다. PIUS형 원자로나 SPWR형 원자로에서는 Honeycomb구조의 Density Lock을 사용하여 Shutdown 및 잔열 제거 기능을 수행하며 정상운전시에는Primary Coolant(고온, 저농축 붕산수)와 Pool Water(저온, 고농축 붕산수)를 분리하고 있다. Density Lock을 사용할 경우, 기동 운전이나 출력 변경과 같은 비정상 운전시 Density Lock을 통하여 노심으로 Pool Water가 유입될 수가 있다. 따라서 불필요한 Pool Water의 유입을 방지하고 피동형 원자로의 설계 개념을 만족시키며, 피동적으로 강제 순환으로부터 자연 순환으로의 경로를 열어 줄 수 있는 Hydraulic Valve에 대한 이론적 해석을 수행하여 실제 밸브를 제작하여 실험을 통해 이론과 비교하고 Valve의 특성곡선을 개발한다.

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Development of Reliability Analysis Program for Air Operated Valve (공기구동밸브 신뢰도 분석 모듈 개발)

  • 허태영;양상민;김봉호;송동섭;김찬용;이우준
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2003.06a
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    • pp.1080-1082
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    • 2003
  • To develop a reliability analysis program applied to the diagnosis for air operated valve's integrity. we collected, analyzed AOV failure data from foreign and domestic nuclear power plants, and classified whole subjects of this program into several groups according to type and size. We established a theoretical basis using Lognormal Distribution and Bayesian Theory to develop analysis methodology. The result of this program was applied to the calculation of operational unavailability of AOV, and the effect of AOV's failure. Also this program can be applied to the development of diagnostic technique considering AOV environment (temperature, pressure), and setting-up maintenance cycle.

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