• 제목/요약/키워드: Wall-Thinned Piping

검색결과 44건 처리시간 0.029초

ESPI 를 이용한 곡관 감육 결함부의 변형률 분포 측정 (Strain Distribution Measurement for Wall Thinning Defect in Pipe Bends by ESPI)

  • 아흐터나심;김경석;정성욱;박종현;최정석;정현철
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회A
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    • pp.120-125
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    • 2007
  • Put Abstract text here The strain distribution measurement for wall thinned pipe bends by ESPI is presented. Defect types observed in the steel piping in the nuclear power plants (NPP) are the crack at the weld part and the wall thinning defect in the pipe bends. Especially, the wall thinning defects in the pipe bends due to the flow-accelerated corrosion (FAC) is a main type of defects observed in the carbon steel piping system. ESPI is one of the optical non-destructive testing methods and can measure the stress and the strain distribution of the object subjected by the tensile loading or the internal pressure. In this paper, the strain distribution of the wall thinned pipe bends due to the internal pressure will be measured by ESPI technique and the results are discussed. From the results, the size of the wall thinning defect can also be measured approximately.

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복합하중이 작용하는 국부감육배관 평가법 개발 (Development of Assessment Methodology for Locally Wall-Thinned Pipe Under Combined Loading)

  • 심도준;김윤재;김영진;박치용
    • 대한기계학회논문집A
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    • 제29권10호
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    • pp.1399-1406
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    • 2005
  • Recently authors have proposed a new method to estimate failure strength of a pipe with local wall thinning subject to either internal pressure or global bending. The proposed method was based on the equivalent stress averaged over the minimum ligament in the locally wall thinned region, and the simple scheme to estimate the equivalent stress in the minimum ligament was proposed, based on the reference stress concept. This paper extends the new method to combined internal pressure and global bending. The proposed method is validated against FE results for various geometries of local wall thinning under combined loading. The effect of internal pressure is also investigated in the present study. Comparison of maximum moments, predicted according to the proposed method, with published full-scale pipe test data fur locally wall-thinned pipes under combined internal pressure and global bending, shows good agreement.

감육배관 손상시험 결과를 이용한 국부손상기준 검증 (Validation of a Local Failure Criteria Using the Results of Wall-Thinned Pipe Failure Tests)

  • 김진원;이성호;박치용
    • 대한기계학회논문집A
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    • 제33권12호
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    • pp.1393-1400
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    • 2009
  • The objective of this study is to validate local failure criteria, which were proposed based on the notched-bar specimen tests combining with finite element (FE) simulations, using the results of real-scale pipe failure tests. This study conducted burst test using wall-thinned pipe specimens, which were made of 4 inch Sch.80 ASTM A106 Gr.B carbon steel pipe, under simple internal pressure at ambient temperature and performed associated FE simulations. Failure pressures were estimated by applying the failure criteria to the results of FE simulations and were compared with experimental failure pressures. It showed that the local stress based criterion, given as true ultimate tensile stress of material, accurately estimated the failure pressure of wall-thinned pipe specimens. However, the local strain based criterion, which is fracture strain of material as a function of stress tri-axiality, could not predict the failure pressure. It was confirmed that the local stress based criterion is reliably applicable to estimation of failure pressure of local wall-thinned piping components.

원전 급수가열기 동체 응력 해석 (A Stress Analysis of Feeedwater Heater Shell in Nuclear Power Plant)

  • 송석윤;김형남
    • 한국압력기기공학회 논문집
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    • 제11권1호
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    • pp.1-11
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    • 2015
  • Feedwater Heaters are important components in a nuclear power plant. As the age of heater increases, the maintenance cost required for continuous operation also increases. Most heaters have the carbon steel shells, tube support plates and flow baffles. The carbon steel is susceptible to flow-accelerated corrosion. This is especially true if the flow has a two-phase mixture of steam and condensate. The wall thinning around the wet steam entrance area of the shell is inevitable during some long term operation. The structural integrity of the feedwater heater shell affects the safe operation of the nuclear power plant. Therefore, it is needed for the thinned shell to be repaired. The maintenance method for preventing failure of the shell should be determined by investigating various factors including the stress distribution of thinned area. The stress analysis of the shell including the steam entrance region is studied in this paper. The results of thinned shell is compared with that of intact shell.

원전 배관 루프시스템의 냉각 위상잠금 적외선열화상을 이용한 결함 검출에 관한 연구 (A Study about Detection of Defects in the Nuclear Piping Loop System Using Cooling Lock-in Infrared Thermography)

  • 김상채;강성훈;윤나연;정현철;김경석
    • 비파괴검사학회지
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    • 제35권5호
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    • pp.321-331
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    • 2015
  • 냉각 위상잠금 적외선열화상 기법을 이용하여 원전 배관 루프시스템의 가열결함 검출의 선행연구를 통하여 냉각결함 검출조건의 적용에 관한 연구를 수행하였다. 배관의 결함가공은 감육 길이, 감육 깊이를 변화시켜 결함조건을 가공하여 루프시스템을 제작하였다. 사용된 장비는 적외선열화상 카메라와 냉각장치를 사용하였으며 냉각장치와 대상 루프시스템과의 거리는 2m로 고정시켜 실험을 수행하였다. 실험 결과의 분석을 위하여 냉각온도 분포, 위상데이터를 확보하고, 이를 분석하여 결함 길이를 측정하였다. 냉각결함 검출조건은 적외선열화상 데이터보다 위상잠금 적외선열화상 데이터가 측정 결과의 신뢰도가 높았다.

감육배관의 요한요소해석에 의한 파괴거동 평가 (Fracture Behavior Evaluation of Wall Thinned pipes by Finite Element Analysis)

  • 안석환;남기우;김진욱;이수식;윤자문
    • 한국해양공학회:학술대회논문집
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    • 한국해양공학회 2004년도 학술대회지
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    • pp.320-325
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    • 2004
  • Fracture behaviors and strength of pipes with local wall thinning are very important Jar the integrity of energy plants. In pipes of energy plants, sometimes, the local wall thinning may result from severe erosion-corrosion damage. Recently, the effects of local wall thinning on strength and fracture behaviors of piping system have been well studied. In this paper, the elasto-plastic analysis is performed by FE code ANSIS. We evaluated the failure mode, fracture strength and fracture behavior from FE analysis.

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감육된 증기발생기 전열관의 유한요소 해석 (Finite Element Analysis for Wall Thinned Steam Generator Tubes)

  • 성기용;안석환;남기우
    • 동력기계공학회지
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    • 제10권3호
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    • pp.38-44
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    • 2006
  • Failure assessment of steam generator tube are very important for the integrity of energy plants. In pipes of energy plants, sometimes, the local wall thinning may result from severe erosion-corrosion damage. Recently, the effects of local wall thinning on fracture strength and fracture behavior of piping system have been well studied. In this paper, the elasto-plastic analysis is performed by FE code ANSIS on steam generator tube with wall thinning. We evaluated the failure mode, fracture strength and fracture behavior from FE analysis. It was possible to predict the crack initiation point by estimating true fracture ductility under multi-axial stress conditions at the center of the thinned area.

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탄소강배관 다중 UT 측정두께를 활용한 감육여부 판별법 개발 (Development of Wall Thinning Distinction Method using the Multi-inspecting UT Data of Carbon Steel Piping)

  • 황경모;윤훈;이찬규
    • Corrosion Science and Technology
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    • 제11권5호
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    • pp.173-178
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    • 2012
  • To manage the wall thinning of carbon steel piping in nuclear power plants, the utility of Korea has performed thickness inspection for some quantity of pipe components during refueling outages and determined whether repair or replacement after evaluating UT (Ultrasonic Test) data. When the existing UT data evaluation methods, such as Band, Blanket, PTP (Point to Point) Methods, are applied to a certain pipe component, unnecessary re-inspecting situations may be generated even though the component does not thinned. In those cases, economical loss caused by repeated inspection and problems of maintaining the pipe integrity followed by decreasing of newly inspected components may be generated. EPRI (Electric Power Research Institute) in USA has suggested several statistical methods, TPM (Total Point Method), LSS (Least Square Slope) Method, etc. to distinguish whether multiple inspecting components have thinned or not. This paper presents the analysis results for multiple inspecting components over three times based on both NAM (Near Area of Minimum) Method developed by KEPCO-E&C and the other methods suggested by EPRI.

TES 소성하중 기준의 감육엘보 기기건전성 평가 (Integrity Evaluation of Thinned Elbow Based on TES Plastic Load)

  • 이성호;박치용;이정근;박재학
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회A
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    • pp.281-286
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    • 2008
  • Wall thinning defect due to flow accelerated corrosion is one of major aging phenomena in most power plant industries, and it results in reducing load carrying capacity of the piping systems. A failure testing system was set up for real scale elbows containing various simulated wall thinning defects, and monotonic in-plane bending tests were performed under internal pressure to find out the failure behavior of thinned elbows. Various finite element models were generated and analysed to figure out and simulate the behavior for other thinning shapes and loading conditions. This paper presents the decreasing trends of load carrying capacity according to the thinning dimensions which were revealed from the investigation of finite element analysis results. A mechanical integrity evaluation model for thinned elbows was proposed, also. This model can be used to calculate the TES plastic load of thinned elbows for general internal pressure, thinning location, and in-plane bending direction.

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원전 배관 감육 결함 검사를 위한 IR 열화상시험 조건 결정 (Determination of an Test Condition for IR Thermography to Inspect a Wall-Thinning Defect in Nuclear Piping Components)

  • 김진원;윤경원;정현철;김경석
    • 비파괴검사학회지
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    • 제32권1호
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    • pp.12-19
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    • 2012
  • 본 논문에서는 적외선 열화상 기법을 원전 배관에 적용하여 감육결함을 검사하기 위한 시험 조건을 파악하기 위해서, 인공 결함이 가공된 배관 시편과 평판 시편을 이용하여 적외선 열화상 시험을 수행하였다. 시험에는 할로겐램프를 사용하여 시편을 가열하였으며, 램프의 출력과 시편과 램프의 거리를 변수로 실험을 수행하였다. 시험 결과 시편과 램프의 거리가 1~2 m 이고 램프의 출력이 정격출력의 60 % 이상일 때, 적외선 열화상 기법은 1회 촬영으로 최소한 500 mm 범위 내에 존재하는 원주방향 폭이 $2{\Theta}=90^{\circ}$이고 깊이와 길이가 각각 d/t=0.5와 $L/D_o=0.25$인 배관내 인공 감육 결함들을 검출하였다. 평판 시편과 배관 시편에서 시편과 램프의 거리에 관계없이 램프 출력이 높을수록 결함에 대한 이미지가 선명하였다. 평판 시편과 배관 시편에서 적외선 열화상 방법의 결함 검출 능력은 유사하지만, 최적의 시험 조건은 시편에 따라 다르게 나타났다.