• Title/Summary/Keyword: 역지밸브

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Recycling of Safety Check Valves Contaminated with Radioactivity by Chemical Decontamination (化學除染에 의한 逆止밸브의 再使用)

  • 정종헌;최왕규;원휘준;심준보;오원진
    • Resources Recycling
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    • v.10 no.1
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    • pp.56-65
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    • 2001
  • Chemical decontamination techniques have been employed to reuse the high cost check valves contaminated with radioactivity and to reduce the radiation exposure during the inspection and maintenance work of safety injection system containing check valves. After chemical decontamination, an ultrasonic treatment was conducted to remove the fine solid particles retained in the crevices of check valves. The decontamination process conditions and the amount of chemical reagents were determined from the results of a pre-test, using the (list arm holder. The decontamination factors (DF), estimated from the activity in the solution, ranged from 14.5 to 18.5 corresponding to the activity removal of 93-95ft. The corrosion test data indicated that the general corrosion rate during a chemical decontamination-ultrasonic treatment process are low for type 304 S tainless steel, Inconel -600 and Stellite-6 materials $ (2.1\times10^{-2}$ $6.0\times10^{-2}$ and$ 1.7\times10^{-2}$ mil, respectively).

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Analysis of Failure Causes for Check Valves (역지밸브의 고장 원인 분석)

  • Song, Seok-Yoon;Yoo, Seong-Yeon
    • 유체기계공업학회:학술대회논문집
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    • 2005.12a
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    • pp.607-612
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    • 2005
  • Check valves playa vital role in the operation and protection of nuclear power plants. Check valves failure in nuclear power plants often lead to a plant transient or trip. An overview of the failure history of check valves needs to identify key area where resources can be best applied to further improve their reliability, and provide cost effective means for failure reduction. The analysis of historical failure data gives information on the populations of various types of check valves, the systems they are installed in, failure modes, effects, methods of detection, and the mechanisms of the failures. The results presented are based on information derived from operating records, nuclear industry reports, manufacturer supplied information. A majority of check valve failures are caused by improper application. Failure modes are identified for swing and lift check valves. Failures involving improper seating and valve disc stuck comprised the largest percentage of failures.

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Experimental Investigation of the Effect of Upstream Disturbances on Swing Check Valves (스윙형 역지 밸브에 미치는 상류측 교란요소 영향에 관한 실험적 연구)

  • Song, Seok-Yoon;Kim, Yang-seok;Park, Sung-keun
    • 유체기계공업학회:학술대회논문집
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    • 2004.12a
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    • pp.309-314
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    • 2004
  • The experimental loop was designed and installed to measure the disc positions, disc back stop load and differential pressure with flow velocity for 3 inch and 6 inch swing check valves. The tests were performed at various conditions of upstream flow disturbance source and distance from the tested check valves to investigate the effect of the upstream flow conditions on the disc stability of the swing check valves. The selected disturbance sources were elbow, globe valve, and orifice. The experimental results are presented herein.

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Improvement of the Model for Predicting Swing Check Valve Opening (스윙형 역지 밸브 개도 예측 모델 개선)

  • Kim, Yang-seok;Song, Seok-yoon;Kim, Dae-woong;Park, Sung-keun
    • 유체기계공업학회:학술대회논문집
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    • 2004.12a
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    • pp.315-320
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    • 2004
  • Swing check valves are the most common type of check valve in nuclear power plant and need to be operated property to perform their functions and to keep the valve internals stable. However, for a swing check valve disc to remain stable, the opening characteristics should be identified and the upstream flow velocity should be enough to hold the disc fully open and without motion. Thus it is necessary to develop a model for predicting the flow velocity for a given disc opening. In the present study, the disc positions with mean flow velocity were measured for 3 inch and 6 inch swing check valves. Comparison of the measurements with the existing models showed that the models underestimate the mean flow velocity for a given disc position. Therefore, the existing model for predicting swing check valve disc position was improved with the realistic disc impingement area perpendicular to the flow stream and the experimental data. The result showed that the improved model with the best estimate of kb = 0.04 predicts well the disc openings of 6 inch swing check valve, especially in the low velocity region. For better prediction of the disc opening at high flow velocity, however, it is recommended to develop a kb correlation with the disc angle.

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Experimental Study on the Opening Characteristics for Swing Check Valves (스윙형 역지 밸브의 열림 특성에 관한 실험적 연구)

  • Song, Seok-Yoon;Kim, Yang-Seok;Park, Sung-Keun;Hong, Sung-Yull
    • 유체기계공업학회:학술대회논문집
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    • 2003.12a
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    • pp.555-561
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    • 2003
  • The experimental apparatus is designed and installed to measure the disc positions with flow velocity, $V_{open}\;and\;V_{min}$ for 3 inch and 6 inch swing check valves. The minimum flow velocity necessary to just open the disc at a full open position is referred to as $V_{open}\;and\;V_{min}$ is defined as the minimum velocity to fully open the disc and hold it without motion. In the experiments, $V_{min}$ is determined as the minimum flow velocity at which the back stop load begins to increase after the disc is idly opened or the oscillation level of disc is reduced below $1^{\circ}$. The results show that the $V_{min}$ velocities for 3 inch and 6 inch swing check valves are about 15.6% and 4.8% higher than the $V_{open}$ velocities, respectively. Although the experiments were done with the stable uniform flow, additional experiments will be performed to determine the effects of the upstream disturbances.

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Present State and Tendency of the Preventive Maintenance for Major Components in Nuclear Power Plants (원전 주요기기의 예방정비 현황 및 연구 동향)

  • Park, Sung-Keun
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2008.04a
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    • pp.407-412
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    • 2008
  • 원자력발전소의 안전성 확보를 위해서, 설비의 유지 관리 기법은 고장이 발생했을 때 조치하는 고장정비에서부터 고장을 미연에 방지하기 위한 예방정비, 예측정비 그리고 상태기반정비로 진행되어 가고 있다. 국내 원자력발전소에서는 고장정비와 예방 정비가 적용되고 있으며, 예측정비와 상태기반정비에 대한 연구가 수행되고 있다. 본 논문에서는 모터구동밸브, 공기구동밸브, 역지밸브 그리고 펌프에 대한 예방정비 현황과 기술 개발 동향에 대해 살펴보았다.

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