Characterization of microstructure and local deformation in 316NG weld heat-affected zone and stress corrosion cracking in high temperature water

Corrosion Science

Volumn 53, Issue 5, 2011, Pages 1916-1932

  Lu, Zhanpeng ^a   Shoji, Tetsuo ^a   Meng, Fanjiang ^a   Xue, He ^a   Qiu, Yubing ^a   Takeda, Yoichi ^a   Negishi, Koji ^a  

^a TOHOKU UNIVERSITY   (Japan)

Author keywords

A. Stainless steel; B. SEM; C. Reactor condition; C. Welding; Stress corrosion

Indexed keywords

A. STAINLESS STEEL; B. SEM; C. WELDING; REACTOR CONDITIONS; STRESS CORROSION;

DEFORMATION; HARDNESS; HEAT AFFECTED ZONE; RESIDUAL STRESSES; STAINLESS STEEL; TEXTURES; WELDING;

STRESS CORROSION CRACKING;

EID: 79952902659     PISSN: 0010938X     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.corsci.2011.02.009     Document Type: Article

References (44)

1. T. Shoji, Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants, in: Proceedings of the 11th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, Skamania, Stevenson, Washington, ANS, 2003, pp. 588-598.
2. Suzuki S., Kumagayi K., Shitara C., Mizutani J., Sakashita A., Tohkuma H., Yamashita H. Maintenology 2004, 3:65-70.
3. Suzuki S., Takamori K., Kumagayi K., Sakashita A., Yamashita N., Shitara C., Okamura Y. E-J. Adv. Maint. 2009, 1:1-29.
4. NISA, Documents Presented at Fifth Structural Integrity Evaluation Committee, February 18, 2003.
5. T.M. Angeliu, P.L. Andresen, E. Hall, J.A. Sutliff, S. Sitzman, R.M. Horn, Intergranular stress corrosion cracking of unsensitized stainless steels in BWR environments, in: Proceedings of the Ninth International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, TMS, 1999, pp. 311-317.
6. Andresen P.L., Morra M.M. J. Nucl. Mater. 2008, 383:97-111.
7. M. Itow, S. Suzuki, SCC growth and retardation behavior of low carbon stainless steel piping in the region near the weld fusion boundary, in: 55th Material and Corrosion Symposium, Paper F08104, JSCE, 2008, pp. 31-34.
8. T. Arai, K. Watanabe, K. Kako, Y. Miyahara, SCC growth behavior of stainless steel in the region near the weld fusion boundary, in: 55th Material and Corrosion Symposium, Paper F08107, JSCE, 2008, pp. 35-38.
9. P.L. Andresen, T.M. Angeliu, L.M. Young, Effect of Martensite and hydrogen on SCC of stainless steels and alloy 600, in: Proceeding of the Corrosion/2001, NACE, Paper No. 228, 2001.
10. Lu Z.P., Shoji T., Takeda Y., Kai A., Ito Y. Corrosion 2007, 63:1021-1032.
11. Lu Z.P., Shoji T., Takeda Y., Ito Y., Yamazaki S. Corros. Sci. 2008, 50:698-712.
12. Lu Z.P., Shoji T., Takeda Y., Ito Y., Kai A., Tsuchiya N. Corros. Sci. 2008, 50:625-638.
13. Lu Z.P., Shoji T., Takeda Y., Ito Y., Kai A., Yamazaki S. Corros. Sci. 2008, 50:561-575.
14. Jiao Z., Was G.S. J. Nucl. Mater. 2008, 382:203-209.
15. Alexandreanu B., Sencer B.H., Thaveeprungsriporn V., Was G.S. Acta Mater. 2003, 51:3831-3848.
16. Alexandreanu B., Was G.S. Corrosion 2003, 59:705-720.
17. Lozano-Perez S., Yamada T., Terachi T., Schroder M., English C.A., Smith G.D.W., Grovenor C.R.M., Eyre B.L. Acta Mater. 2009, 57:5361-5381.
18. T. Shoji, Localized and accelerated oxidation and stress corrosion cracking-role of stress, strain, hydrogen and microstructures, in: Proceedings of the Quantitative Micro-Nano (QMN) Approach to Predicting Stress Corrosion Cracking in Water-Cooled Nuclear Plants, 2010, CDROM.
19. 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, in: Proceedings of the Corrosion/2002, NACE, Paper No. 511, 2002, CDROM.
20. Lu Z.P., Shoji T., Dan T.C., Qiu Y.B., Yonezawa T. Corros. Sci. 2010, 52:2547-2555.
21. Lu Z.P., Shoji T., Meng F.J., Qiu Y.B., Dan T.C., Xue H. Corros. Sci. 2011, 53:247-262.
22. Z.P. Lu, K. Sakaguchi, K. Negishi, Y. Takeda, Y. Ito, T. Shoji, Quantifying the effects of strain-hardening and water chemistry on crack growth rates of 316L SS welds in high temperature water, in: Proceedings of the 14th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, ANS, 2009, pp. 636-645, CDROM.
23. Kim J.H., Ballinger R.G. Corrosion 2008, 64:645-656.
24. OIM Analysis for Windows 5.0, User Manual, TexSEM Laboratories, Inc., Utah, USA, 2005.
25. Z.P. Lu, H. Xue, T. Shoji, Crack branching and its effect on environmentally assisted cracking in high temperature water environments, in: Proceedings of the 2010 ASME Pressure Vessels and Piping Division Conference, ASME, 2010, PVP2010-25818.
26. K. Negishi, Evaluation of stress corrosion cracking characteristic of weldment of 316L stainless steels piping mockups influenced by thermal aging, Master Thesis, Department of Mechanical and Aerospace Engineering, Tohoku University, March 2009.
27. M. Ando, K. Nakata, M. Itow, N. Tanaka, M. Koshiishi, R. Obata, Y. Miwa, Y. Kaji, M. Hayakawa, CGR behavior of low carbon stainless steel of hardened heat affected zone in plr piping weld joints, in: Proceedings of the 13th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, 2007, CNS, CDROM.
28. 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: Proceedings of the 11th International Conference on Environmental Degradation of Materials Nuclear Power Systems - Water Reactors, ANS, 2003, pp. 834-843.
29. M. Itow, M. Kikuchi, N. Tanaka, J. Kuniya, M. Yamamoto, S. Suzuki, S. Namatame, T. Futami, SCC growth rates and reference curves for low-carbon stainless steels in BWR environments, in: Proceedings of the 2004 ASME Pressure Vessels and Piping Division Conference, ASME, 2004, pp. 167-173.
30. Andresen P.L., Morra M.M. J. Pressure Vessel Technol. 2007, 129:488-506.
31. M. Tsubota, Y. Katayama, Y. Saito, T. Kaneko, Stress corrosion cracking growth behavior of cold worked austenitic stainless steel in high temperature water, in: Proceedings of the 12th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, TMS, 2005, pp. 167-181.
32. Yamazaki S., Lu Z.P., Ito Y., Takeda Y., Shoji T. Corros. Sci. 2008, 50:835-846.
33. P.M. Scott, P. Combrade, On the mechanism of stress corrosion crack initiation and growth in alloy 600 exposed to PWR primary water, in: Proceedings of the 11th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, ANS, 2003, pp. 29-38.
34. Shoji T., Lu Z.P., Murakami H. Corros. Sci. 2010, 52:769-779.
35. T. Shoji, S. Suzuki, R.G. Ballinger, Theoretical prediction of SCC growth behavior-threshold and plateau growth rate, in: Proceedings of the Seventh International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, NACE, 1995, pp. 881-891.
36. T. Shoji, Z.P. Lu, S. Yamazaki, The effect of strain-hardening on PWSCC of nickel-base Alloys 600 and 690, in: Proceedings of the 14th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, ANS, 2009, pp. 220-238.
37. Arioka K., Yamada T., Terachi T. Corrosion 2006, 62:568-575.
38. Moshier W.C., Brown C.M. Corrosion 2000, 56:307-320.
39. Lu Z.P., Takeda Y., Shoji T. J. Nucl. Mater. 2008, 383:92-96.
40. Andresen P.L., Ford F.P. Mater. Sci. Eng. A 1988, 103:167-184.
41. M. Toloczko, S.M. Bruemmer, P.L. Andresen, SCC crack growth of cold-worked 316L SS in BWR oxidizing and hydrogen water chemistry conditions, in: Proceedings of the 13th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, CNS, 2007, CDROM.
42. P.L. Andresen, M.M. Morra, Effects of Si on SCC of irradiated and unirradiated stainless steels and nickel alloys, in: Proceedings of the 12th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, TMS, 2005, pp. 87-106.
43. K. Nakade, T. Hirasaki, S. Suzuki, K. Takamori, K. Kumagai, Y. Tanaka, K. Umeoka, SCC crack propagation behavior in 316L weld metal under high temperature water, in: JSCE Conference on Materials and Corrosion 2008, Paper No. A-204.
44. Z.P. Lu, T. Shoji, Y. Takeda, Y. Ito, A. Kai, N. Tsuchiya, Effects of electrochemical potential on crack growth rates of 316L weld HAZ and weld metal materials in 288°C pure water, in: Proceedings of the 13th International Conference on Environmental Degradation Materials Nuclear Power Systems - Water Reactors, CNS, 2007, CDROM.