Fracture toughness, tensile and stress corrosion cracking properties of alloy 600, alloy 690 and their welds in water

NACE - International Corrosion Conference Series

Volumn 1996-March, Issue , 1996, Pages

  Brown, C M ^a   Mills, W J ^a  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

Author keywords

Alloy 600; Alloy 690; EN52; EN82H; Fracture toughness; Hydrogen; Stress corrosion cracking; Tensile properties; Water; Welds

Indexed keywords

BRITTLENESS; CRACKS; DUCTILE FRACTURE; ELASTOPLASTICITY; FRACTURE MECHANICS; FRACTURE TESTING; HYDROGEN; HYDROGEN EMBRITTLEMENT; LOAD TESTING; RESIDUAL STRESSES; STRAIN RATE; STRESS CORROSION CRACKING; TEMPERATURE; TENSILE PROPERTIES; WATER; WELDING; WELDS;

ALLOY 600; ALLOY 690; EN52; EN82H; ENVIRONMENTAL INTERACTIONS; FRACTURE TOUGHNESS TESTING; HIGH-TEMPERATURE WATER; HYDROGEN INDUCED CRACKING;

FRACTURE TOUGHNESS;

EID: 85039583102     PISSN: 03614409     EISSN: None     Source Type: Book Series    
DOI: None     Document Type: Conference Paper

References (35)

1. Proceedings of the 1985 Workshop on Primary-Side Stress Corrosion Cracking of PWR Steam Generator Tubing, EPRI Report NP-5158, June 1987.
2. Y. S. Garud and T. L. Gerber, Tntergranular Stress Corrosion Cracking of Ni-Cr-Fe Alloy 600 Tubes in PWR Primary Water-Review and Assessment for Model Development, " EPRI Report NP-3057, May 1983.
3. P. Saint Paul and G. Slama, Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (LaGrange Park, IL: American Nuclear Society, 1992), p. 39.
4. A. S. O'Neill and J. F. Hall, "Literature Survey of Cracking of Alloy 600 Penetrations in PWRs, " EPRI Report NP-7094, December 1990.
5. J. F. Hall, D. B. Scott, D. A. Wright and R. S. Pathania, Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (LaGrange Park, IL: American Nuclear Society, 1992), p. 652.
6. D. Alter, Y. Robin, M. Pichon, A. Teissier and B. Thomeret, Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (LaGrange Park, IL: American Nuclear Society, 1992), p. 661.
7. C. A. Campbell and S. Fyfitch, Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Warrendale, PA: The Metals Society, 1993), p. 863.
8. D. Buisine, F. Cattant, J. Champredonde, C. Pichon, C. Benhamou, A. Gelpi and M. Vaindirlis, Proceedings of Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Warrendale, PA: The Metals Society, 1993), p. 845.
9. G. L. Webb and M. G. Burke, Proceedings of the Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Houston, TX: National Association of Corrosion Engineers, 1995), p. 41.
10. R. Bandy and D. van Rooyen, Corrosion, 40(1984), p. 425.
11. T. Yonezawa, N. Sasaguri and K. Onimura, "Effects of Metallurgical Factors on Stress Corrosion Cracking of Ni-Base Alloys in High Temperature Water, " JAIF International Conference on Water Chemistry in Nuclear Power Plants, 2(1988), p. 490.
12. R. Bandy and D. van Rooyen, "Quantitative Examination of Stress Corrosion Cracking of Alloy 600 in High Temperature Water-Work During 1983, " Proceedings of 1983 Workshop on Primary-Side Stress Corrosion Cracking of PWR Steam Generator Tubing, EPRI NP-5498, November 1987.
13. J. A. Gorman, R. A. Ogren and J. P. N. Paine, Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (LaGrange Park, IL: American Nuclear Society, (1992), p. 609.
14. G. L. Webb, Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Warrendale, PA: The Metals Society, 1993), p. 687.
15. G. PAirey, Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Houston, TX: NACE International, 1984), p. 462.
16. R. J. Jacko, G. Economy and F. W. Pement, Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (LaGrange Park, IL: American Nuclear Society, 1992), p. 613.
17. K. Norring, J. Engstrom and P. Norberg, Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Warrendale, PA: The Metals Society, 1988), p. 587.
18. R. G. Aspden, T. F. Grand and D. L. Harrod, "Corrosion Performance of Alloy 690, " Proceeding: 1989 EPRI Alloy 690 Workshop, EPRI Report NP-6750-SD, April 1990.
19. R. A. Page, Corrosion, 39(1983), p. 409.
20. T. Yonezawa, K. Onimura, N. Sasaguri, T. Kusakabe, H. Nagano, K Yamanaka, T. Minami and M. Inoue, Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (LaGrange Park, PA: American Nuclear Society, 1986), p. 593.
21. T. W. Crooker, J. A. Hauser, II, and R. A. Bayles, Proceedings of the Conference on Environmental Degradation of Engineering Materials III, (State College, PA: Pennsylvania State University, 1987), p. 521.
22. R. R. Fessier and T. J. Barlo, Environment-Sensitive Fracture: Evaluation and Comparison of Test Methods, ASTM STP 821 (Philadelphia, PA: American Society for Testing and Materials, 1984), p. 368.
23. W. J. Mills, Journal of Testing and Evaluation, 9(1981), p. 56.
24. P. C. Paris, H. Tada, A. Zahoor and H. Ernst, Elastic-Plastic Fracture, ASTM STP 668 (Philadelphia, PA: American Society for Testing and Materials, 1979), p. 5.
25. A. Saxena and S. J. Hudak, Jr., International Journal of Fracture, 14(1978), p. 453.
26. H. C. Rogers, Ductility, (Metals Park, OH: American Society of Metals, 1968), p. 31.
27. T. B. Cox and J. R. Low, Jr., Metallurgical Transactions, 5(1974), p. 1457.
28. T. B. Cassagne and A. Gelpi, Proceedings of the Fifth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (LaGrange Park, IL: American Nuclear Society, 1992), p. 518.
29. J. P. Foster, W. H. Bamford and R. S. Pathania, Proceedings of the Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Houston, TX: National Association of Corrosion Engineers, 1995), p. 25.
30. R. B. Rebak and Z. Szklarska-Smialowska, Corrosion, 50(1994), p. 378.
31. Y. Shen and P. G. Shewmon, Corrosion, 47(1991), p. 712.
32. M. O. Speidel and R. Magdowski, International Conference on Corrosion-Deformation Interactions CDI'92, Fontainebleau-France, (1992), p. 107.
33. R. A. Page, Corrosion, 41(1985), p. 338.
34. L. G. Ljungberg, A. Orinas, P. Stahle and J. L. Nelson, Proceedings of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, (Warrendale, PA: The Metals Society, 1993), p. 379.
35. L. A. James and W. J. Mills, Service Experience, Structural Integrity, Severe Accidents, and Erosion in Nuclear and Fossil Plants, ASME PVP-Vol. 303 (New York, NY: American Society of Mechanical Engineers, 1995), p. 21.