Simulation of thermal fatigue damage in a 316L model pipe component

International Journal of Pressure Vessels and Piping

Volumn 85, Issue 11, 2008, Pages 798-813

  Paffumi, E ^a   Nilsson, K F ^a   Taylor, N G ^a  

^a TNO   (Netherlands)

Author keywords

316L steel; Crack initiation; Crack tip opening displacement; Fatigue crack growth; Thermal fatigue

Indexed keywords

ABS RESINS; CRACK PROPAGATION; CRACKING (CHEMICAL); CRACKS; FATIGUE CRACK PROPAGATION; FATIGUE OF MATERIALS; FINITE ELEMENT METHOD; PIPE; STAINLESS STEEL; THERMAL FATIGUE; THERMAL LOAD; THREE DIMENSIONAL;

316L STEEL; CRACK INITIATION; CRACK TIP OPENING DISPLACEMENT; FATIGUE CRACK GROWTH;

FATIGUE DAMAGE;

EID: 53649108145     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.ijpvp.2008.06.002     Document Type: Article

References (38)

1. IAEA. Assessment and management of ageing of major nuclear power plant components important to safety. Primary piping in PWRs. TECDOC-1361; July 2003.
2. Faidy C, Chapuliot S, Mathet E. Thermal fatigue of reactor components in OECD-NEA countries: a three-fold program to enhance cooperation. In: Proceedings of the SMiRT-18, Beijing, China; August 2005.
3. Kasahara N, Kimura N, Kamide H. Thermal fatigue evaluation method based on power spectrum density functions against fluid temperature fluctuation. In: Proceedings of the ASME PVP2005, Denver, Colorado, USA; July 2005.
4. Higuchi M. Development and evaluation method of fatigue damage on operating plant components considering environmental effects. NEA/CSNI/R(2004)21. In: Proceedings of the third international conference on fatigue of reactor components, Seville, Spain; October 2004.
5. JSME. Guideline for evaluation of high-cycle thermal fatigue of a pipe. S017-2003; 2003.
6. Keller JD, Bilanin AJ, Kaufman AE, Carey J. Thermal cycling screening criteria and evaluation methodology and application to pressurized water reactor branch line piping. NEA/CSNI/R(2004)21. In: Proceedings of the third international conference on fatigue of reactor components, Seville, Spain; October 2004.
7. Davis JM, Deardorff AF, Keller JD, Carey J. Thermal fatigue management guideline for normally stagnant non-isolable RCS branch lines. NEA/CSNI/R(2004)21. In: Proceedings of the third international conference on fatigue of reactor components, Seville, Spain; October 2004.
8. Price JWH. Thermal shock cracking: design and assessment guidelines. Journal of Pressure Vessel Technology 129(1):125-32; February 2007.
9. Kerezsi B.B., and Price J.W.H. Using the ASME and BSI codes to predict crack growth due to repeated thermal shock. International Journal of Pressure Vessels and Piping 79 (2002) 361-371
10. Chapuliot S., Gourdin C., Payen T., Magnaud J.P., and Monavon A. Hydro-thermal-mechanical analysis of thermal fatigue in a mixing tee. Nuclear Engineering and Design 235 (2005) 575-596
11. Metzner K.-J., and Wilke U. European THERFAT project - thermal fatigue evaluation of piping system "Tee"-connections. Nuclear Engineering and Design 235 2-4 (2005) 473-484
12. Taylor N., Nilsson K.F., Dahlberg M., and Faidy C. A procedure for thermal fatigue damage assessment due to turbulent mixing in nuclear piping systems. Proceedings of the international conference on "fatigue design" (2007), CETIM ISBN 2-85400-711-9
13. FAT3D - an OECD/NEA benchmark on thermal fatigue in fluid mixing areas. Report No. NEA/CSNI/R(2005)2; 2005.
14. Curtit F. INTHERPOL thermal fatigue test, NEA/CSNI/R(2004)21. In: Proceedings of the third international conference on fatigue of reactor components, Seville, Spain; October 2004.
15. Maillot V. CEA report R-6041. Ph.D. thesis in French, Ecole Centrale de Lille, Univ. des Sc. de Tech. de Lille; 2003.
16. Calonius K, Solin J. Case study on thermal fatigue potential in a T-joint. In: Proceedings of the third international conference on fatigue of reactor components, Seville, Spain; October 2004.
17. Paffumi E. Simulation and modelling of thermal fatigue damage in austenitic piping components, Ph.D. thesis. UK: University of Swansea; 2004.
18. Paffumi E., Nilsson K.F., Taylor N., Hurst R., and Bache M.R. Cracks initiation, propagation and arrest in 316L model pipe components under thermal fatigue. Journal of ASTM International 2 5 (May 2005)
19. Paffumi E, Nilsson KF, Taylor N, Hurst R, Bache MR. Measurement of shallow crack growth during thermal fatigue of 316L tubular test piece. In: Proceedings of the third international conference on fatigue of reactor components, OECD/EPRI, Seville; 3-6 October 2004.
20. Paffumi E., Nilsson K.F., and Taylor N.G. Analysis of the thermal fatigue cracking of 316L model pipe components under cyclic down-shocks. In: McCabe J. (Ed). Design and analysis of piping components, thermal stresses and CFD in vessel design. Proceedings of the PVP2005, Denver, CO, USA (July 17-21, 2005)
21. Kerr DC, Andritsos F, Hurst RC. Crack growth determination in thermally loaded components. In: Proceedings of the SMIRT, vol. 11; 1991. p. 265-70.
22. Ensemble de caractéristiques 1S, RCC-MR ed.; May 1993.
23. Huthmann H, Picker C. Behaviour of short fatigue cracks in austenitic stainless steels. Literature review. European Commission, Nuclear Science and Technology, EUR 15186; 1995.
24. Setz W, Buckthorge D. Behaviour of short cracks in austenitic stainless steels. Part III. Final report for European Commission Contract RA1-0193-D; December 1993.
25. Gao Z, Sun W, Jin W, Wang J, Zhang F. Fatigue crack growth properties of 16MNR and 316L steels at high temperature. In: Proceedings of the PVP2005, ASME pressure vessel and piping division conference, Denver, USA; July 2005.
26. Sherry A.H., Wardle G., Jacques S., and Hayes J.P. Tearing-fatigue interactions in 316L(N) austenitic stainless steel. International Journal of Pressure Vessels and Piping 82 11 (November 2005) 840-859
27. Drubay B., Marie S., Chapuliot S., Lacire M.H., Michel B., and Deschanels H. A16: guide for defect assessment at elevated temperature. International Journal of Pressure Vessels and Piping 80 7-8 (2003) 499-516
28. Holman J.P. Heat transfer. 8th ed. (1997), McGraw-Hill Inc.
29. Lemaitre J., and Chaboche J.-L. Mechanics of solid materials (1990), Cambridge University Press, Cambridge, UK
30. ASME nuclear boiler and pressure vessel code, code case N-201-4, Appendix Y; 2004.
31. ASME nuclear boiler and pressure vessel code - section XI (2004), ASME
32. Régles de surveillance en exploitation des matérials mécaniques des ilots nucléaires REP, RSE-M ed.; 1997.
33. Raju I.S., and Newman Jr. J.C. Stress-intensity factors for internal and external surface cracks in cylindrical vessels. Journal of Pressure Vessel Technology 104 (1982) 293-298
34. Marie S., Chapuliot S., Kayser Y., Lacire M.H., Drubay B., Barthelet B., et al. French RSE-M and RCC-MR code appendices for flaw analysis: presentation of the fracture parameters calculation - part III: cracked pipes. International Journal of Pressure Vessels and Piping 84 (2007) 614-658
35. I Pour les Tubes Comportant un Defaut de Surface Semi-elliptique Longitudinal ou Circonferentiel, interne ou externe, CEA/SACLAY-R-5900. France: Direction de l'information scientifique et technique; 2000. ISSN 0429-3460.
36. Shih C.F. Relationships between the J-integral and the crack opening displacement for stationary and extending cracks. Journal of the Mechanics and Physics of Solids 29 4 (1981) 305-326
37. Sreenivasan P.R., Ray S.K., Vaidyanathan S., and Rodriguez P. Measurement of stretch zone height and its relationship to crack tip opening displacement and initiation J-value in an AISI 316 stainless steel. Fatigue and Fracture of Engineering Materials and Structures 19 7 (1996) 855-868
38. Obrtlík K., Polák J., Hájek M., and Vašek A. Short fatigue crack behaviour in 316L stainless steel. International Journal of Fatigue 19 (1997) 471-475