• 제목/요약/키워드: Circumferential cracked pipe

검색결과 28건 처리시간 0.018초

유한요소 해석모델이 원자력 배관의 건전성 평가에 미치는 영향 (Effect of Finite Element Model on the Integrity Evaluation of Nuclear Piping)

  • 허남수;김영진;표창률;유영준
    • 한국안전학회지
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    • 제15권2호
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    • pp.51-58
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    • 2000
  • Recently, the J/T analysis based on elastic-plastic finite element analysis is popularly used in the nuclear industry to assess the integrity of a cracked pipe. The objective of this paper is to evaluate the effect of stress-strain curve for weld metal, variation of crack incremental length(${\delta}a$), and crack face pressure on the J/T analysis result. For this purpose, a parametric analysis was performed and the results calculated from finite element analysis were compared with those from the piping experimental data(stainless steel weldment pipe with circumferential through-wall crack). The numerical result using base metal material property is in agreement with the experimental one and the maximum load is decreased as the ${\delta}a$ for J/T analysis is increased.

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참조응력법에 입각한 표면균열배관의 파괴역학 해석 -참조하중의 영향 분석- (Effect of Reference Loads on Fracture Mechanics Analysis of Surface Cracked Pipe Based on Reference Stress Method)

  • 심도준;손범구;김윤재;김영진
    • 대한기계학회논문집A
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    • 제28권5호
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    • pp.524-531
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    • 2004
  • To investigate relevance of the definition of the reference stress to estimate J and $C^{*}$ for surface crack problems, this paper compares FE J and $C^{*}$ results for surface cracked pipes with those estimated according to the reference stress approach using various definitions of the reference stress. Pipes with part circumferential inner surface crack and finite internal axial crack are considered, subject to internal pressure and global bending. The crack depth and aspect ratio are systematically varied. The reference stress is defined in four different ways using (i) the local limit load, (ii) the global limit load, (iii) the global limit load determined from the FE limit analysis, and (iv) the optimized reference load. It is found that the reference stress based on the local limit load gives overall excessively conservative estimates of J and $^{*}$. Use of the global limit load clearly reduces the conservatism, compared to that of the local limit load, although it can provide sometimes non-conservative estimates of J and $^{*}$. The use of the FE global limit load gives overall non-conservative estimates of J and $^{*}$. The reference stress based on the optimised reference load gives overall accurate estimates of J and $^{*}$, compared to other definitions of the reference stress. Based on the present finding, general guidance on the choice of the reference stress for surface crack problems is given.

광범위 크리프 조건에 대한 관통균열 배관의 크리프 파괴역학 해석 (Creep Fracture Mechanics Analysis for Through-Wall Cracked Pipes under Widespread Creep Condition)

  • 허남수;김윤재;김영진
    • 대한기계학회논문집A
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    • 제27권6호
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    • pp.890-897
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    • 2003
  • This paper compares engineering estimation schemes of C* and creep COD for circumferential and axial through-wall cracked pipes at elevated temperatures with detailed 3-D elastic-creep finite element results. Engineering estimation schemes included the GE/EPRI method, the reference stress method where reference stress is defined based on the plastic limit load and the enhanced reference stress method where the reference stress is defined based on the optimized reference load. Systematic investigations are made not only on the effect of creep-deformation behaviour on C* and creep COD, but also on effects of the crack location, the pipe geometry, the crack length and the loading mode. Comparison of the FE results with engineering estimations provides that for idealized power law creep, estimated C* and COD rate results from the GE/EPRI method agree best with FE results. For general creep-deformation laws where either primary or tertiary creep is important and thus the GE/EPRI method is hard to apply, on the other hand, the enhanced reference stress method provides more accurate and robust estimations for C* and COD rate than the reference stress method.

원자력 배관의 공학적 파단전누설 해석을 위한 균열열림변위 계산 (Crack Opening Displacement Estimation for Engineering Leak-Before-Break Analyses of Pressurized Nuclear Piping)

  • 허남수;김윤재;장윤석;양준석;최재붕
    • 대한기계학회논문집A
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    • 제28권10호
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    • pp.1612-1620
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    • 2004
  • This study presents methods to estimate elastic-plastic crack opening displacement (COD) fur circumferential through-wall cracked pipes for the Leak-Before-Break (LBB) analysis of pressurized piping. Proposed methods are based not only on the GE/EPRI approach but also on the reference stress approach. For each approach, two different estimation schemes are given, one for the case when full stress-strain data are available and the other fur the case when only yield and ultimate tensile strengths are available. For the GE/EPRI approach a robust way of determining the Ramberg-Osgood (R-O) parameters is proposed, not only fur the case when detailed information on full stress-strain data is available but also for the case when only yield and ultimate tensile strengths are available. The COD estimates according to the GE/EPRI approach, using the R-O parameters determined from the proposed R-O fitting procedures, generally compare well with the published pipe test data. For the reference stress approach, the COD estimates according to the method based on both full stress-strain data and limited tensile properties are in good agreement with pipe test data. In conclusion, experimental validation given in the present study provides sufficient confidence in the use of the proposed method to practical LBB analyses even though when information on material's tensile properties is limited.

축방향 변위가 작용하는 가스 파이프라인 용접부에 존재하는 원주방향 외부표면균열의 변형률 기반 J-적분 및 CTOD 계산 (Estimations of Strain-Based J-integral and CTOD for Circumferential Outer Surface Crack in the Weld of Gas Pipeline Under Axial Displacement)

  • 김경민;박지수;문지희;장윤영;박승현;허남수
    • 한국압력기기공학회 논문집
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    • 제16권1호
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    • pp.100-109
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    • 2020
  • Pipelines subjected to ground movement would be easily exposed to large-scale deformation. Since such deformations may cause the pipeline failure, it is important to ensure the safety of pipelines in various operation conditions. However, crack in weld metal have been considered as one of the main causes that can deteriorate the structural integrity of the pipeline. For this reason, the structural integrity of the pipe containing the crack in the weld should be obtained. In order to assess cracked pipe, J-integral and crack-tip opening displacement(CTOD) have been applied widely as the elastic-plastic fracture mechanics parameters representing crack driving force. In this study, engineering solutions to calculate the J-integral and CTOD of pipes with a circumferential outer surface crack in the weld are proposed. For this purpose, 3-dimensional elastic-plastic finite element(FE) analyses have been performed considering the effect of overmatch and width of weld. The shape of the weld was simplified to I-groove, and axial displacement was employed as for loading condition. Based on FE results, the effects of crack size, material properties and width of weldment on J-integral and CTOD were investigated. Additionally, the J-integral and CTOD for I-groove were compared with those for V-groove to examine the effects of the weld shape, and a proportionality coefficient of J-integral and CTOD was calculated from the results of this paper.

LEAK-BEFORE-BREAK ANALYSIS OF THERMALLY AGED NUCLEAR PIPE UNDER DIFFERENT BENDING MOMENTS

  • LV, XUMING;LI, SHILEI;ZHANG, HAILONG;WANG, YANLI;WANG, ZHAOXI;XUE, FEI;WANG, XITAO
    • Nuclear Engineering and Technology
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    • 제47권6호
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    • pp.712-718
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    • 2015
  • Cast duplex stainless steels are susceptible to thermal aging during long-term service at temperatures ranging from $280^{\circ}C$ to $450^{\circ}C$. To analyze the effect of thermal aging on leak-before-break (LBB) behavior, three-dimensional finite element analysis models were built for circumferentially cracked pipes. Based on the elasticeplastic fracture mechanics theory, the detectable leakage crack length calculation and J-integral stability assessment diagram approach were carried out under different bending moments. The LBB curves and LBB assessment diagrams for unaged and thermally aged pipes were constructed. The results show that the detectable leakage crack length for thermally aged pipes increases with increasing bending moments, whereas the critical crack length decreases. The ligament instability line and critical crack length line for thermally aged pipes move downward and to the left, respectively, and unsafe LBB assessment results will be produced if thermal aging is not considered. If the applied bending moment is increased, the degree of safety decreases in the LBB assessment.

표면균열이 있는 직관에 대한 선형탄성 응력확대계수 유한요소해석 결과의 요소 및 균열형상 민감도 (Element and Crack Geometry Sensitivities of Finite Element Analysis Results of Linear Elastic Stress Intensity Factor for Surface Cracked Straight Pipes)

  • 류동일;배경동;제진호;안중혁;김윤재;송태광;김용범
    • 대한기계학회논문집A
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    • 제37권4호
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    • pp.521-527
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    • 2013
  • 본 논문에서는 3 차원 유한요소해석을 통해 표면균열이 있는 직관에 내압, 굽힘, 그리고 비틀림의 단일 또는 복합하중이 작용하는 경우의 응력확대계수를 연구하였다. 두 가지 결함평가코드(API-579-1, RCC-MR A16)를 각각 유한요소해석 결과와 비교하여 코드 간의 차이 및 해석의 신뢰성을 확인하였다. 응력확대계수는 적분 경로에 독립적이기 때문에 민감하지 않다고 알려져 있는데 3 차원 유한요소해석을 통해 요소 수에 대한 민감도를 확인하였다. 또한 균열형상의 정의방법에 따른 유한요소해석 결과의 차이와 두 가지 결함평가코드를 사용한 결과의 차이를 확인하였다.

Round Robin Analyses on Stress Intensity Factors of Inner Surface Cracks in Welded Stainless Steel Pipes

  • Han, Chang-Gi;Chang, Yoon-Suk;Kim, Jong-Sung;Kim, Maan-Won
    • Nuclear Engineering and Technology
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    • 제48권6호
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    • pp.1412-1422
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    • 2016
  • Austenitic stainless steels (ASSs) are widely used for nuclear pipes as they exhibit a good combination of mechanical properties and corrosion resistance. However, high tensile residual stresses may occur in ASS welds because postweld heat treatment is not generally conducted in order to avoid sensitization, which causes a stress corrosion crack. In this study, round robin analyses on stress intensity factors (SIFs) were carried out to examine the appropriateness of structural integrity assessment methods for ASS pipe welds with two types of circumferential cracks. Typical stress profiles were generated from finite element analyses by considering residual stresses and normal operating conditions. Then, SIFs of cracked ASS pipes were determined by analytical equations represented in fitness-for-service assessment codes as well as reference finite element analyses. The discrepancies of estimated SIFs among round robin participants were confirmed due to different assessment procedures and relevant considerations, as well as the mistakes of participants. The effects of uncertainty factors on SIFs were deducted from sensitivity analyses and, based on the similarity and conservatism compared with detailed finite element analysis results, the R6 code, taking into account the applied internal pressure and combination of stress components, was recommended as the optimum procedure for SIF estimation.