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

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  );
  • 초록

    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 criteria, and these studies have shown that steam generator tubes with a certain range of axial through-wall cracks could remain in service without any safety or reliability problems. However, these studies have been limited, thus far, to consideration of single cracked tubes, necessitating a study on multiple cracks, which are commonly found. A crack coalescence model applicable to steam generator tubes with two collinear axial through-wall cracks was proposed in the previous study. In this paper, the investigation is extended to the parallel axial cracks spaced in a circumferential direction, because parallel axial cracks are more frequently detected during in-service inspections than collinear axial cracks. Interaction effects between two parallel cracks are evaluated by performing elastic and elastic-plastic finite element analyses.


  • 주제어

    coalescence criterion .   interaction effect .   steam generator tube .   plastic collapse .   plugging .   rupture.  

  • 참고문헌 (20)

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    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) 
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    10. Erdogan, F.,' Ductile Failure Theories for Pressurized Pipes and Containers,' Int. J. PVP, Vol. 4 (1976) 
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    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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  • 이진호 (16)

  • Song, Myung-Ho (16)

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