Transactions of the Korean Society of Mechanical Engineers A (대한기계학회논문집A)

The Korean Society of Mechanical Engineers (대한기계학회)
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Stress Intensity factor Calculation for the Axial Semi-Elliptical Surface Flaws on the Thin-Wall Cylinder Using Influence Coefficients

영향계수를 이용한 원통용기 축방향 표면결함의 응력확대계수의 계산

  • 장창희 (전력연구원 원자력연구원) ;
  • 문호림 (전력연구원 원자력연구원) ;
  • 정일석 (전력연구원 원자력연구원) ;
  • 김태룡 (전력연구원 원자력연구원)
  • Published : 2002.11.01
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Abstract

For integrity analysis of nuclear reactor pressure vessel, including the Pressurized thermal shock analysis, the fast and accurate calculation of the stress intensity factor at the crack tip is needed. For this, a simple approximation scheme is developed and the resulting stress intensity factors for axial semi-elliptical cracks in cylindrical vessel under various loading conditions are compared with those of the finite element method and other approximation methods, such as Raju-Newman's equation and ASME Sec. Xl approach. For these, three-dimensional finite-element analyses are performed to obtain the stress intensity factors for various surface cracks with t/R = 0.1. The approximation methods, incorporated in VINTIN (Vessel INTegrity analysis-INner flaws), utilizes the influence coefficients to calculate the stress intensity factor at the crack tip. This method has been compared with other solution methods including 3-D finite clement analysis for internal pressure, cooldown, and pressurized thermal shock loading conditions. The approximation solutions are within $\pm$2.5% of the those of FEA using symmetric model of one-forth of a vessel under pressure loading, and 1-3% higher under pressurized thermal shock condition. The analysis results confirm that the VINTIN method provides sufficiently accurate stress intensity factor values for axial semi-elliptical flaws on the surface of the reactor pressure vessel.

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References

  1. USNRC, 1982, 'NRC Staff Evaluation of Pressurized Thermal Shock,' SECY82-465
  2. Simonen, F. A. et al., 1986, 'VISA-II-A Computer Code for Predicting the Probability of Reactor Vessel Failure,' Pacific Northwest Laboratory, NUREG/CR-4486
  3. Raju, I. S. and Newman, J. C., 1982, 'Stress Intensity for Internal Surface Cracks in Cylindrical Vessels,' ASME Journal of Pressure Vessel Technology, Vol. 104, pp. 293-298 https://doi.org/10.1115/1.3264220
  4. ASME, 1995, 'Analysis of Flaws,' ASME B&PV Code Sec. Xl, App. A
  5. Atluri, S. N. and Kathiresan, K., 1979, '3-D Analysis of Surface Flaws in Thick-Walled Reactor Pressure Vessels Using Displacement-Hybrid Finite Element Method,' Nuclear Engineering and Design, Vol. 51, pp. 163-176 https://doi.org/10.1016/0029-5493(79)90088-8
  6. Heliot, J., Labbens, R. C. and Pellissier-Tanon, A., 1979, 'Semi-Elliptical Cracks on the Meridional Plane of a Cylinder Subjected to Stress Gradients,' Fracture Mechanics. ASTM STP 677, American Society for Testing and Materials, pp. 341-364
  7. Kobayashi, A. S., 1974, 'A simple Procedure for Estimating Stress Intensity in Regions of High Stress Gradients,' In Significance of Defects in Welded Structure (Edited by Kanazawa, T. and Kobayashi, A. S.), University of Tokyo Press, Tokyo, Japan, pp. 127-143
  8. Kobayashi, A. S., Emery, A. F., Polvanich, N. and Love, W. J., 1977, 'Inner and Outer Surface Cracks in Internally Pressurized Cylinders,' ASME Journal of Pressure Vessel Technology, Vol. 99, pp. 83-89 https://doi.org/10.1115/1.3454523
  9. McGowan, J. J., and Raymund, M. 1979, 'Stress Intensity Factor Solution for Internal Longitudinal Semi-Elliptical Surface Flaws in a Cylinder under Arbitrary Loading,' Fracture Mechanics. ASTM STP 677, American Society for Testing and Materials, pp. 365-380
  10. Underwood, J. H., 1972, 'Stress Intensity Factors for Internally Pressurized Thick-Wall Cylinders,' Stress Analysis and Crack Growth. ASTM STP 513, American Society for Testing and Materials, pp. 59-72
  11. Jang, C. H., Moonn, H. R., Jeong, I. S., and Hong, S. Y., 2001, 'Development of the Improved Probabilistic Fracture Mechanics Analysis Code: VINTIN,' Proc. 2001 Spring Meeting of KNS, Cheju, Korea, 2001. 5.25-26
  12. Dickson, T. L., 1994, 'FAVOR: A Fracture Analysis Code for Nuclear Reactor Pressure Vessels, Release 9401,' Oak Ridge National Laboratory, ORNL/NRC/L TRJ94/1
  13. Jang, C. H., et al., 2000, 'VINTIN: Vessel Integrity Analysis Inner Flaws,' KEPRI TM.00NP10.P2000.350
  14. Moonn, H. R. and Jang, C. H., 'Comparison of Stress Intensity Factors for Longitudinal Semi-elliptical Surface Cracks in Cylindrical Pressure Vessels,' Proc. 2001 Spring Meeting of KSME, Cheju, Korea, 2001. 6.28-29
  15. Jang, C. H., Moonn, H. R., and Jeong, I. S., 2001, 'Stress Intensity Factor Calculation for the Semi-elliptical Surface Flaws on the Thin-Wall Cylinder using Influence Coefficients,' Proc. 2001 Spring Meeting of KSME, Cheju, Korea, 2001. 6. 28-29
  16. Hibbitt, Karlsson & Sorensen, lnc., 1999, ABAQUS User's manual
  17. Rice, J. R., 1968, 'A Path Independent Integral and Approximate Analysis of Strain Concentration by Notches and Cracks,' Journal of Applied Mechanics, pp.379-386
  18. Wu, X. and Carlsson, A. J., 1991, Weight Functions and Stress Intensity Factor Solutions, Pergamon Press, Oxford
  19. Timoshenko, S., 1940, Theory of Plate and Shells, McGraw-Hill, New-York
  20. Wang, X. and Lambert, S. B., 1996, 'Stress Intensity Factors and Weight Functions for Longitudinal Semi-Elliptical Surface Cracks in Thin Pipes,' International Journal of Pressure Vessel & Piping, Vol. 65, pp. 75-87 https://doi.org/10.1016/0308-0161(94)00160-K
  21. Keeney, J. A. and Bryson J. W., 1995, 'Stress Intensity Factor Influence Coefficients for Semielliptical Inner Surface Flaws in Clad Pressure Vessels,' Fracture Mechanics, Vol. 26, pp. 430-443