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

The Korean Society of Mechanical Engineers (대한기계학회)
권호 표지
DOI QR코드

DOI QR Code

The Probability Distribution of Fatigue Crack Propagation Life Considering Effect of Crack Coalescence

균열의 합체를 고려한 피로균열 진전수명의 확률분포

  • Published : 2000.05.01
Download PDF
⟨ Previous Next ⟩

Abstract

The studies of probability distribution of the fatigue crack growth life have been somewhat reported. But the study on the probability distribution of the fatigue crack growth life considering the crack coalescence for three dimensional surface fatigue crack has apparently not been reported to date. In this study, the computer program has been developed to predict the probability distribution of the fatigue crack growth life considering the crack coalescence. The effects of parameters for the distribution of the fatigue crack propagation life were evaluated by using the program.

Keywords

References

  1. Okamura, H.., Watanabe, K. and Naito, Y., 1975, 'Reliability Approach in Structural Engineering,' Maruzen, pp. 244-257
  2. Besuner, P. M. and Tetelman, A. S., 1977, 'Probabilistic Fracture Mechanics,' Nuclear Engineering and Designe, Vol. 43, pp. 99-107 https://doi.org/10.1016/0029-5493(77)90134-0
  3. 北川英夫, 中曾根祐司, 1984, '微小分布き裂の發生·成長·合體を伴う魔食據勞破壞過程のモンテカルロ解析モデル,'材科, 第33卷, 第364號, pp. 14-20
  4. Paris, P. C. and Erdogan, F. J., 1963, 'A Critical Analysis off Various Yield Strengths,' Basic Eng., Trans. ASME 85, p. 828
  5. Jr. Newman, J. C. and Raju, I. S., 1979, 'Analysis of Surface Cracks in Finite Plates Under Tension and Bending Loads,' NASA Technical Paper 1578
  6. ASME, 1980, 'Boiler and Pressure Vessel Code, Sec. XI Rules for Inservice Inspection of Nuclear Power Plant Components, Appendix A
  7. British Standard Institute, 1980, 'PD 6493 Guidance on Some Methods for the Deviation of Acceptance Levels for Defects in Fusion Welded Joints
  8. 高溫構造安全技術硏究組合, 'ISES 8218 BER 1次 冷却系配管の健全性評價に關する昭究.
  9. Jouris, G. M. and Shaffer, D. H., 1980, 'Methodology for Inferring Intial Flaw Distribution,' Nucl. Eng. Des., 60. p. 437
  10. Nilsson, F. A.,'Model for Fracture Mechanical Estimation of the Failure Probability of Reactor Pressure Vessels,' Pressure Vessel Technology, Part II, Third National Conference, Tokyo, pp. 593-601
  11. Bruckner, A. and Munz, D., 1983, 'The Effect of Curve Fitting on the Prediction of Failure Probability from the Scatter in Crack Geometry and Fracture Thoughness,' Reliability Engineering 5, pp. 139-146 https://doi.org/10.1016/0143-8174(83)90010-0
  12. Harris, D. O., Lim, E. Y. and Dedhia, D. D., 1981, 'Probability of Pipe Fracture in the Primary Coolant Loop of a PWR Plant,' NURER/CR-2189, Vol. 5
  13. Tang, W. H.., 1973, 'Probabilistic Updating of Flaw Information,' Journal of Testing and Evaluation, Vol. 1, No. 8, pp.459-467 https://doi.org/10.1520/JTE10051J