A probabilistic simulation of fluid leakage in multiple cracks situation

Fatigue and Fracture of Engineering Materials and Structures

Volumn 25, Issue 11, 2002, Pages 1087-1094

  Xie, L ^a   Yu, Z ^a  

^a NORTHEASTERN UNIVERSITY   (China)

Author keywords

Leak rate; Leak before break; Monte Carlo method; Multiple cracks

Indexed keywords

COMPUTER SIMULATION; CRACK PROPAGATION; FLUIDS; MONTE CARLO METHODS; PRESSURE VESSELS; PROBABILITY; STATISTICAL METHODS;

MULTIPLE CRACKS;

CRACKS;

EID: 0036853563     PISSN: 8756758X     EISSN: None     Source Type: Journal    
DOI: 10.1046/j.1460-2695.2002.00539.x     Document Type: Article

References (49)

1. Nathwani, J.S. and Stebbing, J.D. (1990) Ontario Hydro'S leakbefore-break approach to Darlington NGS heat transport system piping, Int. J. Pres. Ves. Piping 43, 113-127.
2. Bartholome, G., Bieselt, R.W. and Erve, M. (1988) LBB for KWU-plants. Nucl. Eng. Des. 31, 3-10.
3. Bartholome, G. and Wellein, R. (1995) Leak-before-break behaviour of nuclear piping systems. Theor. Appl. Fracture Mech. 23, 145-149.
4. Bartholome, G. (1997) 'German leak-before-break concept' (description of German LBB procedures, practices and applications). Int. J. Pres. Ves. & Pining 71, 139-146.
5. Serpan, Jr (1997) C.Z., Mayfield, M.E., Muscara, J., US Nuclear Regulatory Commission research for primary system integrity regulations. Nuel. Eng. Des. 171, 1-14.
6. Paul, D., Ahmad, J., Scott, P. et al. (1994) Evaluation and Refinement of Leak-Rate Estimation Models, NUREG/CR- 5128, Revision 1. U.S. Nuclear Regulatory Commission, Washington, DC.
7. Norris, D. (1984) PICEP: Pipe crack evaluation program, Epri NP-3596-SR. Electric Power Research Institute, Palo Alto, CA.
8. Rahman, S., Ghadiali, N., Wilkowski, G.M. et al. (1997) A computer model for probabilisfic leak-rate analysis of nuclear piping an piping welds. Int. J. Pres. Ves. & Piping 70, 209-221.
9. Moussa, W.A., Belt, R. and Tan, C.L. (1999) The interaction of two parallel non-coplanar identical surface cracks under tension and bending. Int. J. Pres. Ves. Piping 76, 135-145.
10. NRC (1997) Draft Regulatory Guide DG-1063: An approach for plant-specific, risk-informed decision making inservice inspection of piping. U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory. Research, Washington, DC.
11. ASME (1995) Boiler and pressure vessel code, Sce. III. American Society of Mechanical Engineers, Article IWB-3600, July.
12. Flesch, B. and Cochet, B. (1990) Leak-before-break in steam generator tubes. International J. Pres. Vs. Piping 43, 165-179.
13. Wilkowski, G. (2000) Leak-before-break: what does it really mean? ASME J. Pres. Ves. Technology 122, 267-272.
14. Ohtani, R., Kitamura, T., Tada, N. and Zhou, W. (1995) Characterization of creep fatigue cracking in Type 304 stainless steel. In: Fatigue Under Thermal and Mechanical Loading (Edited by J. Bressers and L. Remy). Kluwer Academic Publishers, Dordrecht, MA, pp. 199-208.
15. Suh, C.M., Hwang, N.S., Nahm, S.H. and Lee, H.M. (1995) Growth and coalescence behavior of surface multi-cracks in type 304 stainless steel at elevated temperature. In: Fatigue Under Thermal and Mechanical Loading: Mechanisms; Mechanics and Modeling (Edited by J. Bressers and L. Remy). Kluwer Academic Publishers, Dordrecht, MA, pp. 89-95.
16. Xie, L.Y. (1999a) Multi-crack growth/coalescence simulation and its role in passive component leak-before-break concept. Nucl. Eng. Des. 194, 113-122.
17. Xie, L.Y. (1999b) The effect of characteristic crack sizes on the leak-before-break case of pressure vessels and piping with multiple cracks. Int. J. Pres. Ves. & Piping 76, 435-439.
18. Bagshaw, N.M., Beck, S.B.M. and Yates, J.R. (2000) Identification of fluid flow regimes in narrow cracks. Proceedings of the Institution of Mechanical Engineering, Vol. 214, Part. C, pp. 1099-1106.
19. Chen, J., Wang, Y.C. and Ju, D.Y. (1994) Anew limit-load formula for the ligament of a surface crack in leak-before-break assessment. Int. J. Pres. Ves. & Pining 60, 223-230.
20. Bonora, N. (1996) COD of off-centred cracks in pipes under bending load: a geometric solution. Int. J. Fracture 75, 1-18.
21. Smith, E. (1997a) The crack opening area when there is limited plasticity. Int. J. Pres. Ves. & Piping 74, 173-176.
22. Smith, E. (1997b) The effect of crack-system compliance on the leakage area for a circumferentially cracked pipe subjected to combined axial and bending loadings. Int. J. Pres. Ves. & Piping 74, 57-61.
23. Smith, E. (1999) The crack opening area for a multiple loading situation. Int. J. Pres. Ves. & Piping 76, 801-802.
24. Chattopadhyay, J., Dutta, B.K. and Kushwaha, H.S. (1999) Leak-before-break qualification of primary heat transport piping of 500 Mwe Tarapur atomic power plant. Int. J. Pres. Ves. & Pining 76, 221-243.
25. Hasegawa, K., Okamoto, H., Yokota, Y. et al. (1991) Crack opening area of pressurized pipe for leak-before-break evaluation. JSME Int. J. 34, 332-338.
26. Linkens, D., Sherry, N.K. and Bilo, M. (1998) A probabilistic approach to fracture assessment of onshore gas-transmission pipelines. Pipes & Pipelines Int. July-August, 5-16.
27. Electric Power Research Institute (1993) Outside diameter stress corrosion cracking of steam generator tubing at tube support plates - a database for alternate repair limits, Vol. 2: 3/4 Inch Diameter Tubing, EPRI TR-100407, Rev. 1. Electric Power Research Institute, Palo Alto, CA.
28. Nuclear Regulatory Commission (1993) Voltage-based interim plugging criteria for steam generator tubes, NUREG-1477. US Nuclear Regulatory Commission, Rockville, MD.
29. Chatropadhyay, J., Dutta, B.K. and Kushwaha, H.S. (1992) Application of leak-before-break concept in the design of high temperature and high pressure primary heat transport piping system. Bhabha Atomic Research Centre External Report, BARC/ 1992E/033, India.
30. Clarke, L.V., Bainbridge, H., Beck, S.B.M. et al. (1997) Measurement of fluid flow rates through cracks. Int. J. Pres. Ves. & Pining 71, 71-75.
31. Matsumoto, K., Nakamura, S., Gotoh, N. et al. (1991) Study on crack opening areas and coolant leak rates on pipe cracks. J. Pres. Ves. & Piping 46, 35-50.
32. Nam, K.W., Ando, K., Yuzuru, S. et al. (1992) Leak-before-break conditions of plates and pipes under high fatigue stresses. Fatigue Fract. Engng. Mater. Struct. 15, 809-24.
33. Chexal, V.K., Oninones, D.F. and Horowitz, J. (1992) Validation of leak rate model for leak-before-break applications, Service Experience and Life Management in Operating Plants. ASME Pres. Ves. & Piping Division PVP 240, pp. 67-74.
34. Isozaki, T., Shibata, K., Shinokawa, H. et al. (1990) Measurement of leak rate through fatigue cracks in pipes under four-point bending and BWR conditions. Int. J. Pres. Ves. & Piping 43, 399-411.
35. Grebner, H. (1994) Results of a bench mark test on the crack opening and leak rate calculation. Int. J. Pres. Ves. & Piping 61, 35-39.
36. Cizelj, L., Hauer, I., Roussel, G. et al. (1998) Probabilistic assessment of excessive leakage through steam generator tubes degraded by secondary side corrosion. Nucl. Eng. Des. 185, 347-359.
37. Puls, M.P., Wilkins, B.J.S., Rigby, G.L. et al. (1998) A probabilistic method for leak-before-break analysis of CANDU reactor pressure tubes. Nucl. Eng. Des. 185, 241-248.
38. USNRC (1984) Report of the United States Nuclear Regulatory Commission Piping Reviews Committee, Evaluation of potential for pipe breaks, NUREG/CR-1061, 3.
39. Park, Y.-W. and Chung, Y-K. (1999) Leak-before-break assessment of CANDU pressure tube considering leak detection capability. Nucl. Eng. Des. 191, 205-216.
40. Meyer, S., Diegele, E., Bruckner-Foit, A. et al. (2000) Crack interaction modelling. Fatigue Frac. Engng. Mater. Struct. 23, 315-323.
41. Leek, T.H. and Howard, I.C. (1996) An examination of methods of assessing interacting surface cracks by comparison with experimental data. Int. J. Pres. Ves. & Piping 68, 181-201.
42. Khaleel, M.A. and Simonen, F.A. (2000) A model for predicting vessel failure probabilities including the effects of service inspection and flaw sizing errors. Nucl. Eng. Des. 200, 353-369.
43. Richinson, P.J. and Singh, N.P. (1996) Fitness for service guidelines for Zr alloy pressure tubes. COG-91-66 1996 Issue. AECL.
44. Moan, G.D., Coleman, C.E., Price, E.G. et al. (1990) Leakbefore-break in the pressure tubes of CANDU reactors, Int. J. Pres. Ves. & Piping 43, 1-21.
45. Koike, M.H., Takahashi, T. and Baba, H. (1990) Leak-Before-Break experiments on heat treated zr-2.5wt% Nb pressure tubes. Int. J. Pres. Ves. & Piping 43, 39-56.
46. Harris, D.O. and Lim, E.Y. (1983) Application of a probabilistic fracture mechanics model to the influence of in-service inspection of structural reliability. Probabilistic Fracture Mechanics and Fatigue Methods: Applications for Structural Reliability and Maintenance. ASTM STP 789, 19-41.
47. Kurisaka, K. and Nakai, R. (1996) LMFR Piping Reliability Analysis Using Probabilistic Fracture Mechanics. In: PSAM-III (Edited by C. Cacciabue and I.A. Papazoglou). Springer, Crete, Greece, pp. 1714-1719.
48. Nilsson, F., Brickstad, B. and Skanberg, L. (1990) Failure probability of nuclear piping due to IGSCC. Int. J. Pres. Ves. & Piping 43, 205-217.
49. Lees, F.P. (1996) Loss Prevention in the Process Industries, Vol. 1. Butterworth-Heinemann, Oxford.