• Title/Summary/Keyword: circumferential through-wall crack

Search Result 48, Processing Time 0.028 seconds

Effect of Restraint of Pressure Induced Bending on Crack Opening for Circumferential Crack (원주방향 균열의 균열열림에 미치는 압력유기굽힘의 구속 효과)

  • Kim, Jin-Weon;Park, Chi-Yong
    • Proceedings of the KSME Conference
    • /
    • 2000.11a
    • /
    • pp.849-855
    • /
    • 2000
  • This study evaluated the effect of restraint of pressure induced bending(PIB) on crack mouth opening displacement(CMOD) for circumferential through-wall crack in pipe by using both elastic and elastic-plastic finite element analyses. The analyses results showed the restraint of PIB was decreased crack opening for a given crack length and tensile stress, and the effect was considerable for large crack and short restraint length. Also, the restraint effect on CMOD was independent on the variation in pipe diameter and decreased with increasing pipe thickness, and it depended on not total restraint length but short restraint length for non-symmetrically restrained. Additionally, the effect of restraint of PIB was more significant in the elastic-plastic analysis results compared with in the elastic analysis results.

  • PDF

New Engineering Estimation Method of J-Integral and COD for Circumferential Through-Wall Cracked Pipes (원주방향 관통균열이 존재하는 배관의 J-적분 및 COD 계산을 위한 새로운 공학적 계산식)

  • Kim, Yun-Jae;Heo, Nam-Su;Kim, Yeong-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.25 no.3
    • /
    • pp.548-553
    • /
    • 2001
  • A new method to estimate the elastic-plastic J-integral and the crack tip opening displacement (COD) for circumferential through-wall cracked pipes under tension and under bending is proposed for Leak-Before-Break (LBB) analysis. Being based on the reference stress method with further modifications, the proposed method is simple to use and easy to be generalised in practice. Comparison of the CODs, predicted using the proposed method with published pipe test data show overall excellent agreement.

An Experimental Study on the Fracture Behavior of Nuclear Piping System with a Circumferential Crack(I) - Estimation of Crack Behavior in Straight Piping - (원주방향균열이 존재하는 원전 배관계통의 파괴거동에 관한 실험적 연구(I) - 직관부에서의 균열거동 평가 -)

  • Choi, Young-Hwan;Park, Youn-Won;Wilkowski, Gery
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.23 no.7 s.166
    • /
    • pp.1182-1195
    • /
    • 1999
  • The purpose of this study is to investigate experimentally the effects of both seismic loading and crack length on the fracture behavior of piping system with a circumferential crack in nuclear power plants. The experiments were performed using both large scale piping system facility and 4 points bending test machine under PWR operating conditions. The difference in the load carrying capacities between cracked piping and non-cracked piping was also investigated using the results from experiments and numerical calculations. The results obtained from the experiments and estimation are as follows : (1) The safety margin under seismic loading is larger than those under quasi static loading or simple cyclic loading. (2) There was no significant effect of crack length on tincture behavior of piping system with both a surface crack and a through-wall crack. (3) The load carrying capacity in cracked piping was reduced by factors of 7 to 46 compared to non-cracked piping.

Estimates of Partial Safety Factors of Circumferential Through-Wall Cracked Pipes Based on Elastic-Plastic Crack Initiation Criterion (탄소성 균열개시조건에 대한 원주방향 관통균열 배관의 부분안전계수 계산)

  • Lee, Jae-Bin;Huh, Nam-Su
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.38 no.11
    • /
    • pp.1257-1264
    • /
    • 2014
  • Efforts are presently underway for developing an optimal design methodology for GEN-IV nuclear reactors based on target failure probabilities. A typical example is the system-based code, in which the results are represented in the form of partial safety factors (PSFs). Thus, a PSF is one of the crucial elements in either component design or integrity assessment based on target failure probabilities during the operation period. In the present study, a procedure for calculating the PSF of a circumferential through-wall cracked pipe based on the elastic-plastic crack initiation criterion is established, in which the importance of each input variable is assessed. Elastic-plastic J-integrals are calculated using the GE/EPRI and reference stress methods, and the PSF values are calculated using both first- and second-order reliability methods. Moreover, the effect of statistical distributions of assessment variables on the PSF is also evaluated.

Investigation of Maximum External Pressure of Helically Coiled Steam Generator Tubes with Axial and Circumferential Through-Wall Cracks (축방향 및 원주방향 관통균열이 존재하는 나선형 전열관의 파손 외압 평가)

  • Lim, Eun-Mo;Huh, Nam-Su;Choi, Shin-Beom;Yu, Je-Yong;Kim, Ji-Ho;Choi, Suhn
    • Journal of the Korean Society of Manufacturing Technology Engineers
    • /
    • v.22 no.3_1spc
    • /
    • pp.573-579
    • /
    • 2013
  • Once-through helically coiled steam generator tubes subjected to external pressure are of interest because of their application to advanced small- and medium-sized integral reactors, in which a primary coolant with a relatively higher pressure flows outside the tubes, while secondary water with a relatively lower pressure flows inside the tubes. Another notable point is that the values of the mean radius to thickness ratio of these steam generator tubes are very small, which means that a thick-walled cylinder is employed for these steam generator tubes. In the present paper, the maximum allowable pressure of helically coiled and thick-walled steam generator tubes with through-wall cracks under external pressure is investigated based on a detailed nonlinear three-dimensional finite element analysis. In terms of the crack orientation, either circumferential or axial through-wall cracks are considered. In particular, in order to quantify the effect of the crack location on the maximum external pressure, these cracks are assumed to be located in the intrados, extrados, and flank of helically coiled cylinders. Moreover, an evaluation is also made of how the maximum external pressure is affected by the ovality, which might be inherently induced during the tube coiling process used to fabricate the helically coiled steam generator tubes.

The effect of crack length on SIF and elastic COD for elbow with circumferential through wall crack

  • Kim, Min Kyu;Jeon, Jun Hyeok;Choi, Jae Boong;Kim, Moon Ki
    • Nuclear Engineering and Technology
    • /
    • v.52 no.9
    • /
    • pp.2092-2099
    • /
    • 2020
  • Many damages due to flow-accelerated corrosion and cracking have been observed during recent in-service inspections of nuclear power plants. To determine the operability or repair for damaged pipes, an integrity evaluation related to the damaged piping system should be performed by using already proven code and standards. One of them, the ASME Code Case is most popularly used to integrity assessment in nuclear power plants. However, the recent version of CC N-513 still recommends the simplified method which means a damaged elbow is assumed as an equivalent straight pipe. In addition, to enhance the accuracy integrity assessment in elbow, several previous studies recommend that the SIF and elastic COD values for an elbow with relatively large crack could be predicted by an interpolation technique. However, those estimates for elbow with relatively large crack might be derived to inaccurate results for crack growth analysis, such as for the allowable crack size and life estimation. Therefore, in this paper, the effect of crack length (0.3≤θ1/π≤0.5) on SIF and elastic COD for elbow is systematically investigated. Then, for large crack in elbow, accurate estimates for SIF and elastic COD, which are widely used to assess the integrity of elbows, are proposed. Those proposed solutions are expected to be the technical basis for revisions of CC N-513-4 through the validation.

Application of cohesive zone model to large scale circumferential through-wall and 360° surface cracked pipes under static and dynamic loadings

  • Moon, Ji-Hee;Jang, Youn-Young;Huh, Nam-Su;Shim, Do-Jun;Park, Kyoungsoo
    • Nuclear Engineering and Technology
    • /
    • v.53 no.3
    • /
    • pp.974-987
    • /
    • 2021
  • This paper presents ductile fracture simulation of full-scale cracked pipe for nuclear piping materials using the cohesive zone model (CZM). The main objective of this study is to investigate the applicability of CZM to predict ductile fracture of cracked pipes with various crack shapes and under quasi-static/dynamic loadings. The transferability of the traction-separation (T-S) curve from a small-scale specimen to a full-scale pipe is demonstrated by simulating small- and full-scale tests. T-S curves are calibrated by comparing experimental data of compact tension specimens with finite element analysis results. The calibrated T-S curves are utilized to predict the fracture behavior of cracked pipes. Three types of full-scale pipe tests are considered: pipe with circumferential through-wall crack under quasistatic/dynamic loadings, and with 360° internal surface crack under quasi-static loading. Computational results using the calibrated T-S curves show a good agreement with experimental data, demonstrating the transferability of the T-S curves from small-scale specimen.

Crack Opening Area Assessment of Circumferential Though Wall Crack in a Pipe Subjected to Tension and Bending (인장과 굽힘을 받는 배관의 원주방향 관통균열 개구면적 평가)

  • Kim, Sang-Cheol;Kim, Maan-Won
    • Journal of the Korean Society of Safety
    • /
    • v.23 no.5
    • /
    • pp.61-66
    • /
    • 2008
  • It is important to calculate the exact crack opening area in the cracked pipe subjected to axial force and bending moment. Among many solutions for obtaining the crack opening displacement, Paris-Tada's expression, which is derived from energy method, is open used in fracture analysis for piping crack problems because of its simplicity. But Paris-Tada's equation has conservativeness when radius over thickness ratio(R/t) is ten or less, for it is based on the stress intensity factor solution having a compliance function derived from a simple shell theory. In this paper we derived a new expression using a different stress intensity factor solution which is able to consider the variation of compliance through wall thickness in a cracked pipe. Conservativeness of both equations was examined and compared to finite element analysis results. Conservativeness of the new equation is decreased when R/t > 10 and increased slightly when R/t < 10 compared with Paris-Tada's. But Both equations were highly conservative when R/t < 10 compared with finite element analysis results.

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

  • Huh, Nam-Su;Kim, Yun-Jae;Kim, Young-Jin
    • Transactions of the Korean Society of Mechanical Engineers A
    • /
    • v.27 no.6
    • /
    • pp.890-897
    • /
    • 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.

On Relevant Ramberg-Osgood Fit to Engineering Non-Linear Fracture Mechanics Analysis (정확한 비선형 파괴역학 해석을 위한 새로운 Ramberg-Osgood 상수 결정법)

  • Kim, Yun-Jae;Huh, Nam-Su;Kim, Young-Jin;Choi, Young-Hwan;Yang, Jun-Seok
    • Proceedings of the KSME Conference
    • /
    • 2003.04a
    • /
    • pp.170-177
    • /
    • 2003
  • This paper proposes a robust method for the Ramberg-Osgood (R-O) fit to accurately estimate elastic-plastic J from engineering fracture mechanics analysis based on deformation plasticity. The proposal is based on engineering stress-strain data to determine the R-O parameters, instead of true stress-strain data. Moreover, for practical applications, the method is given not only for the case when full stress-strain data are available but also for the case when only yield and tensile strengths are available. Reliability of the proposed method for the R-O fit is validated against detailed 3-D Finite Element (FE) analyses for circumferential through-wall cracked pipes under global bending using five different materials, three stainless steels and two ferritic steels. Taking the FE J results based on incremental plasticity using actual stress-strain data as reference, the FE J results based on deformation plasticity using various R-O fits are compared with reference J values. Comparisons show that the proposed R-O fit provides more accurate J values for all cases, compared to existing methods for the R-O fit. Advantages of the proposed R-O fit in practical applications are discussed, together with its accuracy.

  • PDF