Crack propagation rate modelling for 316SS exposed to PWR-relevant conditions

Journal of Nuclear Materials

Volumn 384, Issue 3, 2009, Pages 274-285

  Vankeerberghen, M ^a   Weyns, G ^b   Gavrilov, S ^a   Martens, B ^c   Deconinck, J ^b  

^a BELGIAN NUCLEAR RESEARCH CENTRE   (Belgium)

^b VRIJE UNIVERSITEIT BRUSSEL   (Belgium)

^c GHENT UNIVERSITY   (Belgium)

Author keywords

[No Author keywords available]

Indexed keywords

ACIDS; BORIDE COATINGS; CHEMICAL ELEMENTS; CRACK PROPAGATION; CRACKS; DISSOLUTION; GROWTH (MATERIALS); HYDROGEN; INORGANIC ACIDS; LITHIUM; LITHIUM ALLOYS; METAL RECOVERY; PRESSURIZED WATER REACTORS; SMALL NUCLEAR REACTORS; STAINLESS STEEL; STRAIN RATE; YIELD STRESS;

ANALYTICAL EXPRESSIONS; BORIC ACIDS; COLD WORKED; CRACK GROWTH RATES; CRACK LENGTHS; CRACK PROPAGATION RATES; CRACK-TIP; CRACK-TIP STRESS; DATA SETS; DISSOLVED HYDROGENS; ELECTROCHEMICAL CONDITIONS; FINITE ELEMENT CALCULATIONS; LITHIUM HYDROXIDES; METAL DISSOLUTIONS; PLANE STRAINS; STRESS DEPENDENTS; STRESS INTENSITIES; TYPE 316 STAINLESS STEELS;

CRACKING (CHEMICAL);

EID: 59149083358     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2008.11.034     Document Type: Article

References (31)

1. Scott P.M. Corrosion 56 8 (2000) 771
2. Ford F.P., and Andresen P.L. Corrosion in nuclear systems: environmentally assisted cracking in light water reactors. In: Marcus P. (Ed). Corrosion Mechanisms in Theory and Practice (2002), CRC Press
3. Ford F.P. Slip dissolution model. In: Desjardins D., and Oltra R. (Eds). Corrosion Sous Contrainte - Phénoménologie et Méchanismes (1990), Bombannes
4. Gavrilov S., Vankeerberghen M., Nelissen G., and Deconinck J. Corros. Sci. 49 (2007) 980
5. T. Shoji, K.S. Raja, G.F. Li, Y.J. Lee, A. Brozova, Critical parameters of environmentally assisted cracking in nuclear systems, Corrosion/2000, NACE, Paper 00190, 2000.
6. Hall Jr. M.M. Corros. Sci. 50 (2008) 2902
7. Turnbull A. Corros. Sci. 39 (1997) 789
8. Newman J.S. Electrochemical Systems (1991), second Ed., Prentice-Hall
9. Nelissen G., Van Theemsche A., Dan C., Van den Bossche B., and Deconinck J. J. Electroanal. Chem. 563 2 (2004) 213
10. Arioka K., Yamada T., Terachi T., and Chiba G. Corrosion 63 12 (2007) 1114
11. M. Vankeerberghen, A mechano-electrochemical diagram for crack growth under EAC conditions, Corrosion/2004, Paper No. 04573, NACE, 2004.
12. Materials Reliability Program (Disposition curves), EPRI, Palo Alto, CA: e.g. MRP-115 2004 1006696.
13. M. Jürgensen, H. Neder, D. Wolter, U. Staudt, S. Odar, V. Schneider, VGB guideline for the water in nuclear power plants with light water reactors (PWR) VGB-R 401 J, 2006.
14. Turnbull A. Corros. Sci. 39 4 (1997) 789
15. Macdonald D.D., and Urquidi-Macdonald M. Corros. Sci. 32 1 (1991) 51
16. Vankeerberghen M., and Macdonald D.D. Corros. Sci. 44 (2002) 1425
17. E.M. Gutman, Mechanochemistry of Solid Surfaces, World Scientific Publishing, 1994, ISBN: 9810217811.
18. T.L. Anderson, Fracture Mechanics - Fundamentals and Applications, Taylor and Francis, 2005, pp. 75 and 114, ISBN: 0-8493-1656-1.
19. R.M. McMeeking, D.M. Parks, On criteria for J-dominance of crack tip fields in large-scale yielding, in: Elastic Plastic Fracture, ASTM STP 668, 1979, p. 175.
20. T. Shoji, S. Suzuki, R.G. Ballinger, Theoretical prediction of SCC growth behavior, in: Proceedings of the Seventh International Symposium Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, vol. 1, 1995, pp. 881-889.
21. Shoji T., Lu Z., Peng Q., Wang S., Takeda Y., and Kai A. Pres. Ves. Pip. 479 (2004) 175
22. Andresen P.L., and Ford F.P. Mater. Sci. Eng. A 103 (1988) 167
23. Andresen P.L., and Ford F.P. Int. J. Pres. Ves. Pip. 59 (1994) 61
24. Andresen P.L., and Morra M.M. Corrosion 64 1 (2008) 15
25. P.L. Andresen, SCC mitigation strategies in hot water, Corrosion/1997, Paper No. 102, NACE, 1997.
26. L. Duisabeau, L. Fournier, A. Toivonen, P. Aaltonen, SCC growth rate quantification in CW 316L stainless steel in PWR primary water using reduced size compact tension specimens, in: Proceedings of the Fontevraux 6, Sixth International Symposium Contributions of Materials Investigations to Improve the Safety and Performance of LWRs, 2006.
27. C. Guerre, O. Raquet, E. Herms, M. Le Calvar, G. Turluer, SCC growth behavior of austenitic stainless steels in PWR primary water conditions, in: Proceedings of the 12th International Symposium Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2005, pp. 1029-1036.
28. Various private communications.
29. Delafosse D., and Magnin T. Eng. Fract. Mech. 68 (2001) 693
30. R.W. Staehle, Critical analysis of 'tight cracks', in: Proceedings of the 13th International Symposium Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2007.
31. Macdonald D.D. Corros. Sci. 38 6 (1996) 1003