Effects of hydrogen water chemistry on corrosion fatigue behavior of cold-worked 304L stainless steel in simulated BWR coolant environments

Journal of Nuclear Materials

Volumn 411, Issue 1-3, 2011, Pages 83-89

  Chiang, M F ^a   Young, M C ^a   Huang, J Y ^a  

^a INSTITUTE OF NUCLEAR ENERGY RESEARCH   (Taiwan)

Author keywords

[No Author keywords available]

Indexed keywords

304L STAINLESS STEEL; COLD WORKS; CORROSIVE ENVIRONMENT; EFFECTIVE MEASURES; FATIGUE CRACK GROWTH RATES; FATIGUE DEGRADATION; FATIGUE RESISTANCE; FRACTURE FEATURE; HYDROGEN INJECTION; HYDROGEN WATER CHEMISTRY; INDUCED CRACK; OXYGEN CONCENTRATIONS; STAINLESS STEEL-304; WATER ENVIRONMENTS;

BOILING WATER REACTORS; COOLANTS; CORROSION; CRACK CLOSURE; DEBRIS; FATIGUE CRACK PROPAGATION; HYDROCHEMISTRY; HYDROGEN; OXYGEN; STAINLESS STEEL;

CORROSION FATIGUE;

EID: 79953213985     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2011.01.035     Document Type: Article

References (32)

1. J.R. Buckley, and D. Hardie Corr. Sci. 40 1993 93 107
2. C. Garcia, F. Martin, P.D. Tiedra, J.A. Heredero, and M.L. Aparidio Corr. Sci. 43 2001 1519 1539
3. C. Garcia, F. Martin, and P. De Tiedra Corr. Sci. 58 2002 849 857
4. S.G. Hong, S. Yoon, and S.B. Lee Int. J. Fat. 25 2003 1293 1300
5. S. Ukai, and T. Uwaba J. Nucl. Mater. 317 2003 93 101
6. R. Sandhya, K. Bhanu, S. Rao, L. Mannan, and R. Devanathan Int. J. Fat. 23 2001 789 797
7. M. Gao, S. Chen, and R.P. Wei Metallur. Trans. A 23A 1992 355 370
8. T.M. Angeliu, Microstructural characterization of L-grade stainless steels relative to the IGSCC behavior in BWR environments, in: F.P. Ford, G.S. Was, J.L. Nelson (Eds.), Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2001.
9. R.P. Shogan, T.R. Mager, Susceptibility of type 316 stainless steel to irradiation assisted stress corrosion cracking in a PWR environment, in: F.P. Ford, G.S. Was, J.L. Nelson (Eds.), Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2001.
10. R.M. Horn, G.M. Gordon, F.P. Ford, and R.L. Cowan Nucl. Eng. Des. 17 1997 313 325
11. H.D. Solomon, C. Amzallag, A.J. Vallee, R.E. Delair, Cycle fatigue limit of type 304L SS in air and PWR water at 150 °C and 300 °C, in: T.R. Allen, P.J. King, L. Nelson (Eds.), Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2005, pp. 1083-1089. (Pubitemid 43907581)
12. B.K. Kim, H. Cho, I.S. Kim, C.H. Jang, B.S. Kim, S.C. Byeon, Study on low cycle fatigue behavior of type 316 stainless steel in a 310 °C water environment, in: Proceedings of the International Conference in Water Chemistry of Nuclear Reactor Systems, 2006.
13. J. Kuniya, I. Masaoka, and R. Sasaki Corrosion 44 1988 21 28
14. Y.H. Lu, Q.J. Peng, T. Sato, and T. Shoji J. Nucl. Mater. 347 2005 52 68
15. T. Onchi, K. Hide, M.L. Catano, M. Navas, A role of localized plastic deformation on intergranular crack initiation of irradiated thermally sensitized type 304 stainless steels in inert gas and in water, in: F.P. Ford, G.S. Was. J.L. Nelson (Eds.), Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2001.
16. Y. Kaneshima, N. Totsuka, T. Yamada, N. Nakajima, K. Negishi, Influence of deformation and ferrite content on susceptibility to SCC of austenitic stainless steel in simulated PWR primary wate, in: F.P. Ford, G.S. Was, J.L. Nelson (Eds.), Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2001.
17. R.P. Shogan, T.R. Mager, Susceptibility of type 316 stainless to irradiation assisted stress corrosion cracking in a PWR environment, in: F.P. Ford, G.S. Was, J.L. Nelson (Eds.), Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2001.
18. W. Bilanin, D. Cubicciotti, R.L. Jones, A.J. MacHiels, L. Nelson, and C.J. Wood Prog. Nucl. Energy 20 1 1987 43 70
19. J.D. Gilman Int. J. Pres. Ves. Pip. 31 1988 55 68
20. D.R. Tice, J.W. Stairmand, H.J. Fairbrother, A. Stock, in: 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Whistler, Aug., 2007, pp. 19-23.
21. M.C. Young, J.Y. Huang, and R.C. Kuo Mater. Trans. 50 3 2009 657 663
22. L.W. Tsay, Y.C. Liu, M.C. Young, and D.Y. Lin Mater. Sci. Eng. 74A 1-2 2004 204 210
23. G. Schuster, and C. Altstetter Metall. Trans. A 14A 1983 2077 2084
24. J.R. Buckley, and D. Hardie Corros. Sci. 34 1993 93 107
25. N. Narita, and H.K. Birnbaum Scripta Metall. 14 1980 1355 1358
26. L. Peguet, B. Malki, and B. Baroux Corros. Sci. 49 2007 199 1948
27. D. Eliezer, D.G. Chakrapani, C.J. Altstetter, and E.N. Pugh Metall. Trans. 10A 1979 935 941
28. N. Narita, C.J. Altstetter, and H.K. Birnbaum Metall. Trans. 13A 1982 1355 1364
29. S. Suresh, G.F. Zaminski, and R.O. Ritchie Metall. Trans. 12A 1981 1435 1443
30. M. Gao, and R.P. Wei Scripta Metall. Mater. 26 1992 1175 1180
31. L.W. Tsay, M.C. Young, and C. Chen Corr. Sci. 45 2003 1985 1997
32. L.W. Tsay, M.C. Young, F.Y. Chou, and R.K. Shiue Mat. Chem. Phys. 88 2004 348 352