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Structural Integrity Evaluation of Steam Generator Tube with Two Parallel Axial Through-Wall Cracks 원문보기

Journal of the Korean Nuclear Society = 원자력학회지, v.36 no.4, 2004년, pp.327 - 337  

Moon Seong In (Sungkyunkwan University) ,  Kim Young Jin (Sungkyunkwan University) ,  Lee Jin Ho (Korea Institute of Nuclear Safety) ,  Song Myung Ho (Korea Institute of Nuclear Safety) ,  Park Youn Won (Korea Institute of Nuclear Safety)

Abstract AI-Helper 아이콘AI-Helper

It is commonly required that tubes with defects exceeding $40\%$ of wall thickness in depth should be plugged; however, this criterion is too conservative for some locations and for some types of defects. Many studies have been done with the aim of developing an alternative plugging crite...

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제안 방법

  • The investigation of interaction effects shows that when a pair of axial crgu:ks is 이。sy spaced, it is less detrimental to structural integrity than a single crack. By taking into account the experimental observation that crack tip tearing and burst in steam generator tubes with multiple parallel axial cracks take place without ligament failure, COD values were selected as an appropriate parameter with which to predict the failure pressure. It was assumed that the failure of the tube with parallel cracks takes place when each COD value is equal to the COD obtained at the failure pressure of the tbe with a single crack.
  • In this paper, 3D finite element analyses were carried out, and a new failure model of the steam generator tube with two parallel axial through- wall cracks was proposed. To explain the deformation behavior of cracked tubes, interaction effects between two adjacent cracks were investigated.
  • In this study, both elastic analyses based on K and elastic-plastic analyses based on J-integration were carried out. We defined the factors to explain the degree of interaction in the elastic analysis and the elastic-plastic analysis as Kratio and Jrotio as follows:
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참고문헌 (20)

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  2. USNRC,' Regulatory guide 1.121, Bases for Plugging Degraded PWR Steam Generator Tubes' (1976) 

  3. ASME,' Rules for Construction of Nuclear Power Plant Components,' ASME Code, Sec. III (1998) 

  4. Cochet, B. and Flesch, B.,' Crack Stability Criteria in Steam Generator Tubes,' 9th Int. Conference on SMiRT, Vol. D, pp.413-419 (1987) 

  5. Yu, Y.J., Kim, J.H., Kim, Y., and Kim, Y.J.,' Development of Steam Generator Tube Plugging Criteria for Axial Crack,' ASME PVP, Vol. 280, pp.79-83 (1994) 

  6. Gorman, J. A., Harris, J. E., and Lowenstein, D.B., Steam Generator Tube Fitness-for-Service Guidelines, AECB Report No. 2.228.2 (1995) 

  7. Lee, J.H., Park, Y.W., Song, M.H., Kim, Y.J. and Moon, S.I.,' 'Determination of Equivalent Single Crack based on Coalescence Criterion of Collinear Axial Cracks,' Nuclear Engineering and Design, Vol. 205, pp. 1-11 (2001) 

  8. Kim, J.S. et al.,' Investigation Report for Steam Generator Tubes Pulled out from Ulchin Unit 1' (1999) 

  9. Knag, S.C. et al.,' Regulatory Technical Report on the Steam Generator Tubes Safety of Nuclear Power Plants,' KINS/AR-669 (1999) 

  10. Erdogan, F.,' Ductile Failure Theories for Pressurized Pipes and Containers,' Int. J. PVP, Vol. 4 (1976) 

  11. Kiefner, J. F., Maxey, W. A., Eiber, R. J., and Duffy, A. R., 'Failure Stress Levels of Flaws in Pressurized Cylinders,' ASTM STP536, pp.461-481 (1973) 

  12. Majumdar, S., Shack, W. J., Diercks, D. R., Mruk, K., Franklin, J., and Knoblich, L.,' Failure Behavior of Internally Pressurized Flawed and Unflawed Steam Generator Tubing at High Temperatures ? Experiments and Comparison with Model Predictions,' NUREG/CR-6575, ANL-97/17 (1998) 

  13. Kim, Y. J., Choy, Y. S., and Lee, J. H.,' Development of Fatigue Life Prediction Program for Multiple Surface Cracks,' ASTM STP 1189, pp.536-550 (1993) 

  14. Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T., and Miyazono, S.,' Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (I),' J. Japanese Nuclear Society, Vol. 27, No. 3 pp.250-262 (1985) 

  15. Shibata, K., Yokoyama, N., Ohba, T., Kawamura, T., and Miyazono, S.,' Growth Evaluation of Fatigue Cracks from Multiple Surface Flaws (II),' J. Japanese Nuclear Society, Vol. 28, No. 3, pp.258-265 (1986) 

  16. Murakami, Y.,' Stress Intensity Factors Handbook,' pp.204-205 (1987) 

  17. Cho, Y.J.,' A Study on the Interaction Effect of Adjacent Semi-Elliptical Crack,' Thesis for M.S., Sungkyunkwan University (1990) 

  18. Framatome,' Steam Generator Tube Integrity,' EPRI Report NP-6865-L, Vol. 1 (1991) 

  19. Argonne National Laboratory,' Steam Generator Tube Integrity Program,' Monthly Pregress Report of ANL, April 3 & 28 (2000) 

  20. Moon, S.I, Kim, Y.J., and Lee, J.H,' Estimation of Plastic Collapse Load of Steam Generator with Two Parallel Axial Through-Wall Cracks,' ASME PVP, Vol. 464, pp.223-230 (2003) 

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