• 제목/요약/키워드: Piping Stress Analysis

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이종재이종재료 Butt 용접에 대한 Overlay 용접의 잔류응력해석 (Residual Stress Analysis of the Overlay Weld on the Dissimilar Metal Butt Weld)

  • 김강수;이호진;이봉상;정인철;변진귀;박광수
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회A
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    • pp.534-537
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    • 2008
  • In recent years, the dissimilar metal, Alloy 82/182 welds used to connect stainless steel piping and low alloy steel or carbon steel components in nuclear reactor piping system have experienced cracking due to primary water stress corrosion(PWSCC). It is well known that one reason of the cracking is the residual stress by the weld. But, it is difficult to estimate exactly weld residual stress due to many parameters of welding. In this paper, the analysis of 3 FEM models made by ABAQUS Code is performed to estimate exactly the weld residual stress on the dissimilar metal weld. 3 FEM models are Butt model, Repair model and Overlay model and are the plane.strain 2D model. The thermal analysis and the stress analysis are performed on each model and the residual stresses on each model were calculated and compared respectively. Also, the specimen of Butt model was made and the residual stresses were measured by X-Ray method and Hole Drilling Technique. These results were compared with the FEM result of Butt model.

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지진 하중을 고려한 배관시스템의 지지 스팬 최적화에 관한 연구 (Study on Support Span Optimization of Pipeline System Considering Seismic Load)

  • 허관도;손인수
    • 한국산업융합학회 논문집
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    • 제23권4_2호
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    • pp.627-635
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    • 2020
  • In this study, the optimal support span determination of pipeline system was carried out in consideration of the effects of seismic loads. The theoretical support and structural analysis were used to determine the optimal support span of piping system according to pipe diameter using theoretical and structural deflection criteria. The reliability of the analysis results was secured by comparing the structural and theoretical results. In particular, the optimum support span of piping system was obtained by considering the effects of seismic load, and the optimal support span of pipe diameter and piping system tended to be proportional to each other. When considering the effects of earthquakes on different pipe diameters(300~2,500mm), the span length is reduced by up to 48% at the allowable stress criterion, and the pipe span length is reduced by up to 5.9% at the deflection criterion. It can be seen that the effect of the seismic load on the determination of the piping span length has a greater effect on the stress than the displacement.

라운드로빈 평가 결과에 기반한 국내 기관의 용접잔류응력 해석 분포의 불확실성 평가 (Uncertainty Quantification of Welding Residual Stress Analysis based on Domestic Organizations Round-Robin Evaluation)

  • 정성균;전준영;김찬규;오창식;강성식; 오창영
    • 한국압력기기공학회 논문집
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    • 제19권2호
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    • pp.130-139
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    • 2023
  • This paper examines the quantification of uncertainty for welding residual stresses in dissimilar metal welds used in nuclear power plants. A mock-up of a dissimilar metal weld pipe, consisting of carbon and stainless steel pipes, was fabricated to measure the residual stress. A Round-Robin analysis was conducted by Korean institutions to assess the welding residual stress. The analysis was carried out in the second order, and the data obtained by each institution was evaluated based on the information provided. Using the Round-Robin results, the distribution of uncertainty in welding residual stresses among Korean institutions was evaluated. The quantification of uncertainty for Korean institutions was found to have a wider range compared to the distribution of welding residual stresses observed in overseas institutions. This study is considered useful in the establishment of comprehensive strategies for evaluating welding residual stress analysis methods used by domestic institutions.

원전 안전 3 등급 고밀도 폴리에틸렌 매설 배관 맞대기 열 융착부의 인장 피로특성 평가 (Study on Tensile Fatigue Behavior of Thermal Butt Fusion in Safety Class III High-Density Polyethylene Buried Piping in Nuclear Power Plants)

  • 김종성;이영주;오영진
    • 대한기계학회논문집A
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    • 제39권1호
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    • pp.11-17
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    • 2015
  • 최근에 원자력 발전소 안전 3 등급 배관에 적용되고 있는 고밀도 폴리에틸렌 배관은 융착표면을가열한 후 축방향으로 가압하는 열 융착 공정을 이용하여 맞대기 융착되어진다. 이러한 열 융착공정은 맞대기 융착부에 비드 형상을 발생시킨다. 이러한 비드 형상의 응력집중에 기인하여 피로수명이 줄어들 수 있다. 따라서 피로거동에 미치는 맞대기 열 융착부 비드의 효과를 고찰하는 것이 필요하다. 본 연구에서는 응력 제어 조건 하의 인장 피로 시험과 유한요소 탄성응력 해석을 수행하여 맞대기 열 융착부의 인장 피로 거동을 고찰하였다. 고찰 결과, 중주기 및 고주기 피로 영역에선 피로수명에 미치는 비드의 영향이 미미한 반면 저주기 피로 영역에선 비드의 존재가 피로 수명을 감소시킴을 확인하였다.

배관시스템 해석을 위한 벨로우즈 유한요소의 개발 (Development of a Bellows Finite Element for the Analysis of Piping System)

  • 고병갑;박경진;이완익
    • 대한기계학회논문집
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    • 제19권6호
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    • pp.1439-1450
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    • 1995
  • Bellows is a familiar component in piping systems as it provides a relatively simple means of absorbing thermal expansion and providing system flexibility. In routine piping flexibility analysis by finite element methods, bellows is usually considered to be straight pipe runs modified by an appropriate flexibility factor; maximum stresses are evaluated using a corresponding stress concentration factor. The aim of this study is to develop a bellows finite element, which similarly includes more complex shell type deformation patterns. This element also does not require flexibility or stress factors, but evaluates more detailed deformation and stress patterns. The proposed bellows element is a 3-D, 2-noded line element, with three degrees of freedom per node and no bending. It is formulated by including additional 'internal' degrees of freedom to account for the deformation of the bellows corrugation; specifically a quarter toroidal section of the bellows, loaded by axial force, is considered and the shell type deformation of this is include by way of an approximating trigonometric series. The stiffness of each half bellows section may be found by minimising the potential energy of the section for a chosen deformation shape function. An experiment on the flexibility is performed to verify the reliability for bellows finite element.

원주방향 관통균열이 존재하는 원통형 구조물의 인장하중에 의한 응력확대계수 비교 (Comparison of Stress Intensity Factors for Cylindrical Structure with Circumferential Through-Wall Cracks subjected to Tensile Load)

  • 정달우;오창균;김현수;권형도;양준석
    • 한국압력기기공학회 논문집
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    • 제17권2호
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    • pp.101-108
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    • 2021
  • To date, a number of stress intensity factor (SIF) solutions have been proposed for the cylindrical structure with circumferential through-wall cracks. However, each solution has a different format as well as applicable range. It is also known that there is a significant difference in predicted SIF values depending on the shape of the structure and the size of the crack. In this study, the applicability of various SIF solutions was analyzed by comparing the finite element analysis results for the case where a tensile load is applied to the cylindrical structure with circumferential through-wall crack. It is found that the calculated SIF gradually decreases and converges to a certain value with increasing length-to-radius ratio. Therefore, an appropriate length-to-radius ratio should be set in consideration of the dimensions of the actual cylindrical structure. For piping with sufficiently long cylinder, the ASME solution is found to be the most appropriate, and for a short cylinder, the API solution should be applied. On the other hand, the WEC solution requires careful attention to its application.

유도 가열 굽힘된 316 계열 오스테나이트 스테인리스 강 배관의 잔류응력 분포 고찰 (Investigation of Residual Stress Distributions of Induction Heating Bended Austenitic Stainless Steel (316 Series) Piping)

  • 김종성;김경수;오영진;장현영;박흥배
    • 대한기계학회논문집A
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    • 제38권7호
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    • pp.809-815
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    • 2014
  • 최근들어 원자력 발전소에 유도 가열 공정으로 굽힌 배관을 적용하려는 동향이 있다. 이러한 유도 가열 굽힘 공정 동안의 열-기계적 메커니즘에 의해 잔류응력이 발생할 수 있다. 잔류응력은 균열 발생과 성장에 중요한 영향을 미치는 균열 구동력들 중의 하나이다. 그러나, 기존 연구들은 두께 변화, 타원도와 같은 기하학적 형상 변이에 집중하고 있는 반면 공정 변수가 잔류응력에 미치는 영향과 관련된 연구는 찾아보기 힘들다. 본 연구에서는 316 오스테나이트 스테인리스 강으로 제작된 유도 가열 굽힘 배관의 잔류응력 분포에 미치는 공정 변수의 영향을 유한요소 변수 해석을 통해 고찰하였다. 고찰결과, 굽힘 모멘트와 굽힘 각도는 잔류응력에 미치는 영향이 미미한 반면 유도 가열률과 이송 속도는 잔류응력에 상당한 영향을 미침을 확인하였다.

SURGE LINE STRESS DUE TO THERMAL STRATIFICATION

  • Jhung, Myung-Jo;Choi, Young-Hwan
    • Nuclear Engineering and Technology
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    • 제40권3호
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    • pp.239-250
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    • 2008
  • If there is a water flow with a range of temperature inside a pipe, the wanner water tends to float on top of the cooler water because it is lighter, resulting in the upper portion of the pipe being hotter than the lower portion. Under these conditions, such thermal stratification can play an important role in the aging of nuclear power plant piping because of the stress caused by the temperature difference and the cyclic temperature changes. This stress can limit the lifetime of the piping, even leading to penetrating cracks. Investigated in this study is the effect of thermal stratification on the structural integrity of the pressurizer surge line, which is reported to be one of the pipes most severely affected. Finite element models of the surge line are developed using several element types available in a general purpose structural analysis program and stress analyses are performed to determine the response characteristics for the various types of top-to-bottom temperature differentials due to thermal stratification. Fatigue analyses are also performed and an allowable environmental correction factor is suggested.

보수용접 모사 방법에 따른 원자로 배관 이종금속 맞대기 용접부 응력 분포 (Stress Distribution in the Dissimilar Metal Butt Weld of Nuclear Reactor Piping due to the Simulation Technique for the Repair Welding)

  • 이휘승;허남수;김진수;이진호
    • 대한기계학회논문집A
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    • 제37권5호
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    • pp.649-655
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    • 2013
  • 이종금속용접부에 대한 실제 용접 공정 중 용접부에서 결함이 발견되면 이를 제거하고 보수용접이 수행된다. 일반적으로 보수용접을 수행하면 용접부에서 인장 잔류응력이 크게 증가될 수 있는 것으로 알려져 있다. 따라서 Alloy 82/182를 사용하여 보수용접이 수행된 이종금속용접부의 일차수 응력부식 균열 현상을 평가하기 위해서는 보수용접에 의한 용접부의 응력 변화를 정확하게 평가해야 한다. 본 논문에서는 비선형 유한요소해석을 수행하여 보수용접에 의한 원자력 이종금속 맞대기 용접부의 응력 분포를 평가하였다. 특히 보수용접 공정 모사를 위한 여러 유한요소 해석방법이 이종금속용접부의 응력분포에 미치는 영향을 평가하였다.

Development for Life Assessment System for Pipes of Thermal Power Plants

  • Hyun, Jung-Seob;Heo, Jae-Sil;Kim, Doo-Young;Park, Min-Gyu
    • KEPCO Journal on Electric Power and Energy
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    • 제2권4호
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    • pp.583-588
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    • 2016
  • The high-temperature steam pipes of thermal power plants are subjected to severe conditions such as creep and fatigue due to the power plant frequently being started up and shut down. To prevent critical pipes from serious damage and possible failure, inspection methods such as computational analysis and online piping displacement monitoring have been developed. However, these methods are limited in that they cannot determine the life consumption rate of a critical pipe precisely. Therefore, we set out to develop a life assessment system, based on a three-dimensional piping displacement monitoring system, which is capable of evaluating the life consumption rate of a critical pipe. This system was installed at the "M" thermal power plant in Malaysia, and was shown to operate well in practice. The results of this study are expected to contribute to the increase safety of piping systems by minimizing stress and extending the actual life of critical piping.