• Title/Summary/Keyword: 감육 배관

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카메라를 이용한 고압 증기 배관 누설/진동 감시시스템 개발 (Development of Leak and Vibration Monitoring System for High Pressure Steam Pipe by Using a Camera)

  • 전형섭;서장수;채경선;손기성;김세오;이남희
    • 비파괴검사학회지
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    • 제36권6호
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    • pp.496-503
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    • 2016
  • 발전소나 석유화학 플랜트 구조물에 누설이 발생하면 인명 피해 및 경제적인 손실을 초래한다. 이러한 누설은 플랜트 배관의 진동으로 인한 피로파괴나 배관 감육으로 인해 발생한다. 플랜트 배관의 진동을 감시하기 위한 방법으로 주로 가속도센서나 레이저센서가 사용되지만 설치 및 운용의 어려움이 따르고 동시에 광범위 측정 시 비용 증가가 발생하게 된다. 이러한 문제점들을 해결하기 위해 최근 카메라를 이용한 누설 및 진동 변위 측정 방법에 대한 연구가 이루어지고 있다. 카메라를 이용한 누설 및 진동 변위 측정 방법은 설치가 간단하고 원거리 측정 및 넓은 범의의 측정이 가능한 장점을 가지고 있다. 따라서 본 연구에서는 카메라를 이용해 누설 및 진동 변위를 측정할 수 있는 시스템을 개발하였고 실험을 통해 성능을 검증하였다.

신뢰도지수 및 몬데카를로 시뮬레이션을 이용한 원전 감육배관의 확률론적 손상역학 평가 (Probabilistic Damage Mechanics Assessment of Wall-Thinned Nuclear Piping Using Reliability Method and Monte-Carlo Simulation)

  • 이상민;윤강옥;장윤석;최재붕;김영진
    • 대한기계학회논문집A
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    • 제29권8호
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    • pp.1102-1108
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    • 2005
  • The integrity of nuclear piping systems has to be maintained sufficiently all the times during operation. In order to maintain the integrity, reliable assessment procedures including fracture mechanics analysis, etc, are required. Up to now, the integrity assessment has been performed using conventional deterministic approach even though there are lots of uncertainties to hinder a rational evaluation. In this respect, probabilistic approach is considered as an appropriate method for piping system evaluation. The objectives of this paper are to develop a probabilistic assessment program using reliability index and simulation technique and to estimate the damage probability of wall-thinned pipes in secondary systems. The probabilistic assessment program consists of three evaluation modules which are first order reliability method, second order reliability method and Monte Carlo simulation method. The developed program has been applied to evaluate damage probabilities of wall-thinned pipes subjected to internal pressure, global bending moment and combined loading. The sensitivity analysis results as well as prototypal evaluation results showed a promising applicability of the probabilistic integrity assessment program.

감육현상을 고려한 가스배관의 파손확률 평가 (Failure Probability Assessment of Gas Pipelines Considering Wall-Thinning Phenomenon)

  • 이상민;윤강옥;장윤석;최재붕;김영진
    • 한국정밀공학회지
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    • 제22권10호
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    • pp.158-166
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    • 2005
  • Pressurized gas pipeline is subject to harmful effects both of the surrounding environment and of the materials transmitted in them. In order to maintain the integrity, reliable assessment procedures including tincture mechanics analysis etc are required. Up to now, the integrity assessment has been performed using conventional deterministic approaches even though there are many uncertainties to hinder a rational evaluation. In this respect, probabilistic approach is considered as an appropriate method for gas pipeline evaluation. The objectives of this paper are to estimate the failure probability of corroded pipeline in gas and oil plants and to propose limited operating conditions under different types of leadings. To do this, a probabilistic assessment program using reliability index and simulation techniques was developed and applied to evaluate failure probabilities of corroded API-5L-X52/X60 gas pipelines subjected to internal pressure, bending moment and combined loading. The evaluation results showed a promising applicability of the probabilistic integrity assessment program.

냉각수 배관 용접부 평가를 위한 유도초음파 기술의 적용 (Application of Guided Ultrasonic Wave Technology for Evaluation of Welding Part in Cooling Water Pipe)

  • 길두송;안연식;박상기
    • 동력기계공학회지
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    • 제14권5호
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    • pp.36-40
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    • 2010
  • The ultrasonic guided wave propagates along with the given structure's wall direction. Because of this specific character, the ultrasonic guided waves arc used in many other fields. Especially, it can be readily utilized for nondestructive inspection of various structures that are made up of gas pipes, heat exchanger tubes, and thin plates. Further, the guided wave technology can be readily utilized when inspecting pipes or thin plates which pose high risk of the accident but for which the nondestructive inspection itself is impossible because it is difficult to get to them since they are coated or buried underground. In the other hand, conventional ultrasonic testing such as thickness gauging uses bulk waves and only tests the region of structure immediately below the transducer. As a result of the application about inlet and outlet cooling water line using guided wave test, we conformed that the overall corrosions were in the lower side of the 304.8 mm inlet valve and these corrosions were engaged in not locally but through the lower side of the valve line. In the near future, we can expect that the detectable defect size is smaller than before along with the development of the sensing technology.

유동형태 변화가 배관 곡관부 대류열전달에 미치는 영향 (Effects of the Changes in Flow Pattern on Convective Heat Transfer in the Vicinity of Pipe Elbow)

  • 송승현;유호선
    • 플랜트 저널
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    • 제15권1호
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    • pp.25-30
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    • 2019
  • 본 연구에서는 배관 곡관부의 유동가속부식을 일으키는 인자 중 수력학적 인자인 유동형태 변경에 따른 영향을 분석하고 부식을 저감시키는 연구를 추진하였다. 열전달과 물질전달, 물질전달과 유동가속부식의 상사성에 대해 이론적 분석을 통해 확인하고 상용 수치해석 프로그램을 이용하여 국소대류열전달계수를 해석함으로써 곡관부의 물질전달 특성에 대해 고찰하였다. 곡관부 상류의 직관부 내표면 안쪽과 바깥쪽에 요철을 설치하였을 때 최대 국소열전달계수는 기본유동에 비하여 현저히 감소하여 요철의 위치와 형태에 따라 차이가 있으나 24.9%까지 감소함을 확인하였으며, 곡관부 상류의 직관부에 가인드 베인을 삽입하면 가이드 베인에 의한 배관 내측면적 크기에 따라 차이가 있으나 최대 국소열전달계수가 기본유동에 비해 12.5%까지 감소함을 확인하였다.

원전 2차계통의 출력증강 운전에 따른 배관감육 영향 분석 (Analysis of Wall-Thinning Effects Caused by Power Uprates in the Secondary System of a Nuclear Power Plant)

  • 윤훈;황경모;이효승;문승재
    • Corrosion Science and Technology
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    • 제15권3호
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    • pp.135-140
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    • 2016
  • Piping and equipment are degraded by flow-accelerated corrosion (FAC) in nuclear power plants. FAC causes numerous problems and nuclear utilities maintain programs to control FAC. The key parameters influencing FAC are hydrodynamic conditions, water chemistry, and effect of materials. Recently, a nuclear utility has planned slight power uprates in Korea. Operating conditions need to be changed in the secondary system according to power uprates. This study analyzed the effect of wall-thinning caused by power uprates. The change of operation data in the secondary cycle is reviewed, and wall-thinning rates are analyzed in the main lines. As a result, two phase (mixture of water and steam) lines have a greater impact than a water line under power uprate conditions. Also, the quality of steam is the most important factor for FAC in two phase lines.

배관감육관리에 활용되는 CHECWORKS 프로그램의 열수력해석 방법론 검증에 관한 연구 (A Study on the Verification of Network Flow Analysis Methodology of CHECWORKS Program used in Pipe Wall Thinning Management)

  • 서혁기;황경모
    • Corrosion Science and Technology
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    • 제12권2호
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    • pp.79-84
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    • 2013
  • In general, pipelines at nuclear power plants are affected by various types of degradation mechanisms and may be ruptured after gradually thinning. FAC (Flow-Accelerated Corrosion) is typical aging mechanism affecting the secondary side piping system. In Korea nuclear power plants, CHECWORKS program have been used for management of wall thinning damages. However, sometimes, CHECWORKS program shows wrong results at the stage of NFA (Network Flow Analysis) in case of complex pipelines. This paper describes the calculation results of pressure drop in a complex pipeline and single line by using the CHECWORKS program and the analysis results are compared with those of engineering calculation results including errors between them.

원전 2차계통의 수화학 변화가 배관감육에 미치는 영향 분석 (Analysis of Pipe Wall-thinning Caused by Water Chemistry Change in Secondary System of Nuclear Power Plant)

  • 윤훈;황경모;문승재
    • Corrosion Science and Technology
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    • 제14권6호
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    • pp.325-330
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    • 2015
  • Pipe wall-thinning by flow-accelerated corrosion (FAC) is a significant and costly damage of secondary system piping in nuclear power plants (NPPs). All NPPs have their management programs to ensure pipe integrity from wall-thinning. This study analyzed the pipe wall-thinning caused by changing the amine, which is used for adjusting the water chemistry in the secondary system of NPPs. The pH change was analyzed according to the addition of amine. Then, the wear rate calculated in two different amines was compared at the steam cycle in NPPs. As a result, increasing the pH at operating temperature (Hot pH) can reduce the rate of FAC damage significantly. Wall-thinning is affected by amine characteristics depending on temperature and quality of water.

SH파 분산특성 변화를 이용한 배관 점진감육 진단 기법 (Gradual pipe wall thinning diagnosis through the variation of dispersion characteristics of SH waves)

  • 조승현;권휴상;안봉영;이승석
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2009년도 춘계학술대회 논문집
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    • pp.258-259
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    • 2009
  • Pipe wall thinning is one of severe problems on structural safety in nuclear power plants. A guided wave can be a proper tool for the fast evaluation or monitoring. As for gradual wall thinnings, however, low sensitivity caused by the low reflection coefficient limits the use of the guided wave. In this work, instead of the guided wave reflection at the wall thinning, the variation of dispersion characteristics is concerned. SH waves were employed due to several advantages and the magnetostrictive patch transducers were used for the excitation and sensing of the SH waves. The proposed method were verified with some experiments and showed the feasibility as an effective tool for the inspection of gradual wall thinning.

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주복수기 냉각해수배관의 직각 엘보 내부유동특성에 관한 연구 (Experimental study of internal flow field about 90degree elbow for cooling seawater pipe at the main condenser)

  • 오승진;조대환;봉태근;김옥석
    • 한국마린엔지니어링학회:학술대회논문집
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    • 한국마린엔지니어링학회 2012년도 전기공동학술대회 논문집
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    • pp.152-153
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    • 2012
  • While engine room arranging pipe which is used from the vessel, It measured the internal flow of 90 degree elbow which is used from the main condenser. Fluid flow in elbow of 90 degree is measured by PIV and Dewetron system. The Reynolds number adopts 50000 and experimental study of flow field in the elbow.

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