Effects of loading mode and water chemistry on stress corrosion crack growth behavior of 316L HAZ and weld metal materials in high temperature pure water

Corrosion Science

Volumn 50, Issue 3, 2008, Pages 625-638

  Lu, Zhanpeng ^a   Shoji, Tetsuo ^a   Takeda, Yoichi ^a   Ito, Yuzuru ^a   Kai, Akira ^a   Tsuchiya, Nobuhisa ^a  

^a TOHOKU UNIVERSITY   (Japan)

Author keywords

A. 316L weld heat affected zone; A. 316L weld metal; A. Simulated boiling water reactor environment; C. Crack growth rate; C. Stress corrosion cracking

Indexed keywords

BOILING WATER REACTORS; CANTILEVER BEAMS; CRACK PROPAGATION; DISSOLVED OXYGEN; GROWTH RATE; HEAT AFFECTED ZONE; MASS TRANSFER; WELDING;

ELECTRIC-CHARGE TRANSFER; SIMULATED BOILING WATER REACTOR ENVIRONMENT; WELD METAL;

STRESS CORROSION CRACKING;

BOILING WATER REACTORS; CANTILEVER BEAMS; CRACK PROPAGATION; DISSOLVED OXYGEN; GROWTH RATE; HEAT AFFECTED ZONE; MASS TRANSFER; STRESS CORROSION CRACKING; WELDING;

EID: 39749151162     PISSN: 0010938X     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.corsci.2007.08.021     Document Type: Article

References (42)

1. T. Shoji, Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants, in: Proc. 11th Int. Symposium. Environ. Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 2003, p. 588.
2. Kumagai K., Suzuki S., Mizutani J., Shitara C., Yonekura K., Masuda M., and Futami T. Evaluation of IGSCC growth behavior of 316NG PLR piping in BWR. In: Wang Y.Y. (Ed). Residual Stress, Fracture, and Stress Corrosion Cracking PVP-vol. 479 (2004), ASME 217
3. Suzuki S., Kumagai K., Shitara C., Mizutani J., Sakashita A., Tokuma H., and Yamashita H. Maintenology 3 (2004) 65
4. Horn R.M., Gordon G.M., Ford F.P., and Cowan R.L. Nuclear Engineering and Design 174 (1997) 313
5. Angeliu T.M., Andresen P.L., Hall E., Sutliff J.A., Sitzman S., and Horn R.M. Intergranular stress corrosion cracking of unsensitized stainless steels in BWR environments. In: Ford F.P., Bruemmer S.M., and Was G.S. (Eds). Proc. 9th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors (1999), TMS 311
6. P.L. Andresen, L.M. Young, W.R. Catlin, R.M. Horn, Stress corrosion crack growth rate behavior of various grades of cold worked stainless steel in high temperature water, Corrosion/2002, NACE, 2002, paper no. 511.
7. T. Shoji, G.F. Li, J.H. Kwon, S. Matsushima, Z.P. Lu, Quantification of yield strength effects on IGSCC of austenitic stainless steels in high temperature waters, in: Proc. 11th Int. Symp. Environ. Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 2003, pp. 834.
8. Mostovoy S., Crosley P.B., and Ripling E.J. Journal of Materials 2 (1967) 661
9. Beres W., Koul A.K., and Thamburaj R. Journal of Testing and Evaluation 25 (1997) 536
10. Nakajima H., Shoji T., Kikuchi M., Nitsuma H., and Shindo M. Detecting acoustic emission during cyclic crack growth in simulated BWR environments. In: Hudak Jr. S.J., and Bucci R.J. (Eds). Fatigue crack growth measurement and data analysis. ASTM STP vol. 738 (1981), ASTM 139
11. S. Hettiarachchi, BWR SCC mitigation strategies and their effectiveness, in: Proc. 11th Int. Symp. Environ. Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, 2003, pp. 477.
12. Voort G.F.V., Lucas G.M., and Manilova E.P. Metallography and microstructures of stainless steels and maraging steels. In: Voort G.F.V. (Ed). ASM handbook. Metallography and Microstructures vol. 9 (2004), ASM International 670
13. Itow M., Kikuchi M., Tanaka N., Kuniya J., Yamamoto M., Suzuki S., Namatame S., and Futami T. SCC growth rates and reference curves for low carbon stainless steels in BWR environments. In: Wang Y.Y. (Ed). Residual Stress, Fracture, and Stress Corrosion Cracking PVP-vol. 479 (2004), ASME 167
14. Jones R.H. Stress corrosion cracking. In: Cramer S.D., and Covino B.S. (Eds). ASM handbook. Corrosion: Fundamentals Testing and Protection vol. 13A (2003), ASM 356
15. Takamori K., Suzuki S., and Kumagai K. Maintenology 3 (2004) 52
16. Taylor G.I. Proceedings Of The Royal Society Of London Series A-Mathematical And Physical Sciences 145 (1934) 362
17. Ashby M.F. Philosophical Magazine 21 (1970) 399
18. Fleck N.A., Muller G.M., Ashby M.F., and Hutchinson J.W. Acta Metallurgica Et Materialia 42 (1994) 475
19. Hall E.O. Proceedings of the Royal Society of London Series B-Mathematical and Physical Sciences 64 (1951) 742
20. Petch N.J. Journal of Iron Steel Instrument 174 (1963) 25
21. T. Shoji, S. Suzuki, R.G. Ballinger, Theoretical prediction of SCC growth behavior-threshold and plateau growth rate, in: Proc. 7th Int. Symp. Environ. Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, 1995, pp. 881.
22. Ford F.P. Corrosion 52 (1996) 375
23. Nishimoto K., Natsume S., Ogawa K., and Matsumoto O. Welding of Stainless Steels (2001), Saipo Publications Inc., Tokyo p. 33
24. Lu Z.P., Shoji T., Takeda Y., Ito Y., Kai A., and Yamazaki S. Transient and steady state crack growth kinetics for stress corrosion cracking of a cold worked 316L stainless steel in oxygenated pure water at different temperatures. Corrosion Science (2007) 10.1016/j.corsci.2007.08.005
25. Andresen P.L. SCC testing and data quality consideration. In: Ford F.P., Bruemmer S.M., and Was G.S. (Eds). Proc. 9th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors (1999), TMS 411
26. Jenssen A., Jansson C., and Sunderberg J. The effect of holding time on the crack growth rate of sensitized stainless steel in high temperature water. In: Allen T.R., King P.J., and Nelson L. (Eds). Proc. 12th Int. Symp. Environ. Degradation of Materials in Nuclear Power Systems-Water Reactors (2005), TMS 157
27. Lin C.C., Kim Y.J., Niedrach L.W., and Ramp K.S. Corrosion 52 (1996) 618
28. Indig M.E., and Nelson J.L. Corrosion 47 (1991) 202
29. Macdonald D.D. Corrosion 48 (1992) 194
30. P.L. Andresen, Perspective and direction of stress corrosion cracking in hot water, in: Proc. 10th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors, NACE, 2001, CDROM.
31. Arioka K., Yamada T., and Terachi T. Corrosion 62 (2006) 568
32. G.B. Naumov, et al., Handbook of thermodynamic data, U.S. Geological Survey, Menlo Park, CA, 1974.
33. Vankeerberghen M., and Macdonald D.D. Corros. Sci. 44 (2002) 1425
34. Andresen P.L., Gott K., and Nelson J.L. Stress corrosion cracking of sensitized type 304 stainless steel in 288C water: a five laboratory round robin. In: Ford F.P., Bruemmer S.M., and Was G.S. (Eds). Proc. 9th Int. Symp. Environ. Degradation of Materials Nuclear Power Systems-Water Reactors (1999), TMS 423
35. Macdonald D.D., Lu P.C., UrquidiMacdonald M., and Yeh T.K. Corrosion 52 (1996) 768
36. Andresen P.L., and Ford F.P. Materials Science and Engineering A-Structural Materials Properties Microstructure and Processing 103 (1988) 167
37. Turnbull A. Corrosion Science 39 (1997) 789
38. Kim Y.J. Corrosion 55 (1999) 81
39. Kim Y.J. Corrosion 58 (2002) 208
40. Kim Y.J. Corrosion 61 (2005) 889
41. Bruemmer S.M., and Thomas L.E. High-resolution characterizations of stress-corrosion cracks in austenitic stainless steel from crack growth tests in BWR-simulated environments. In: Allen T.R., King P.J., and Nelson L. (Eds). Proc. 12th Int. Symp. Environ. Degradation of Materials in Nuclear Power Systems-Water Reactors (2005), TMS 189
42. Bard A.J. Electrochemical Methods-Fundamentals and Applications. second ed. (2001), Wiley p. 138