Dependence of stress corrosion cracking for cold-worked stainless steel on temperature and potential, and role of diffusion of vacancies at crack tips

Corrosion

Volumn 64, Issue 9, 2008, Pages 691-706

  Arioka, K ^a   Yamada, T ^a   Terachi, T ^a   Miyamoto, T ^b  

^a INSTITUTE OF NUCLEAR SAFETY SYSTEM   (Japan)

^b Kobe Material Testing Laboratory Co   (Japan)

Author keywords

Cold work; Grain boundary creep; Intergranular stress corrosion cracking; Potential; Pressurized water reactor; Stainless steel; Temperature; Vacancy diffusion

Indexed keywords

COLD WORKS; GRAIN BOUNDARY CREEP; INTERGRANULAR STRESS CORROSION CRACKING; POTENTIAL; PRESSURIZED WATER; VACANCY DIFFUSION;

AUGER ELECTRON SPECTROSCOPY; BORON; BORON COMPOUNDS; CHROMIUM; CORROSION RESISTANT ALLOYS; CRACK TIPS; CREEP; DIFFUSION; GRAIN BOUNDARIES; GRAIN SIZE AND SHAPE; HYDROGENATION; IRON; LITHIUM; PRESSURIZED WATER REACTORS; RESIDUAL STRESSES; SMALL NUCLEAR REACTORS; STAINLESS STEEL; TEXTURES; VACANCIES;

STRESS CORROSION CRACKING;

EID: 77954815333     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3278507     Document Type: Article

References (72)

1. T.M. Angellu, P.L. Andresen, J.A. Sutliff, R.M. Horn, "Intergranular Stress Corroaion Cracking of Unsensitized Stainless Steels in BWR Environments," Proc. 9th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, eds. S. Bmemmer, P. Ford, G.S. Was (Warrendale, PA: The Minerals, Metals, and Material Society [TMS], 1999), p. 331.
2. P.L. Andresen, T.M. Angeliu, W.R. Catlin, L.M. Young, R.M. Horn, "Effect of Deformation on SCC of Unseiisitized Stainless Steel," CORROSION/2000, paper no. 203 (Houston, TX: NACE International, 2000).
3. P.L. Andresen, T.M. Angeliu, L.M. Young, "Effect of Martensite and Hydrogen on SCC of Stainless Steels and Alloy 600," CORROSION/2001, paper no. 01228 (Houston, TX: NACE, 2001).
4. P.L. Andresen, T.M. Angeliu, L.M. Young, "Immunity, Thresholds, and Other SCC Friction," Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and SCC, ed. R.H. Jones (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS], 2001), p. 65.
5. P.L. Andresen, "Similarity of Cold Work and Radiation Hardening in Enhancing Yield Strength and SCC Growth of Stainless Steel iIn Hot Water," CORROSION/2002, paper no. 02509 (Houston, TX: NACE, 2002).
6. P.L. Andresen, P.W. Emigh, M. Morra, R.M. Horn, "Alloy X-750 Stress Corrosion Crack Growth Rate Behavior in High-Temperature Water," Proc. 11th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ed. G.S. Was (LaGrange Park, IL: American Nuclear Society, 2003).
7. S. Tahtinen, H. Hanninen, M. Trolle, "Stress Corrosion Cracking of Cold-Worked Austenitic Stainless Steel Pipes in BWR Reactor Water," Proc. 6th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Littleton, CO: American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1994), p. 245.
8. S. Ooki, Y. Tanaka, K. Takamori, S. Suzuki, "Study on SCC Growth Behavior of BWR Core Shroud," Proc. 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. L. Nelson, P. King, T. Allen (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS], 2005).
9. K. Kumagai, S. Suzuki, K. Asano, "Detailed Examinations of PLR Weld Joints for the Evaluation of Reasonable SCC Growth Rate," Proc. Int. Symp. Fontevraud 6 (Paris, France: French Nuclear Society, 2006), p. 22.
10. T. Couvant, P. Moulart, L. Legras, P. Bordes, J. Capelle, Y. Rouillon, T. Balon, "PWSCC of Austenite Stainless Steels of Heater of Pressurizers," Proc. Int. Symp. Fontevraud 6 (Paris, France: French Nuclear Society, 2006), p. 67.
11. P.L. Andresen, P.W. Emigh, M.M. Morra, "Effects of PWR Primary Water Chemistry and Deaerated Water on SCC," CORROSION/2005, paper no. 05592 (Houston, TX: NACE, 2005).
12. K. Arioka, "Effect of Temperature, Hydrogen, and Boric Acid Concentration on IGSCC Susceptibility of Annealed 316 Stainless Steel," Proc. Int. Symp. Fontevraud 5 (Paris, France: French Nuclear Society, 2002), p. 149.
13. T. Fukumura, T. Terachi, K. Arioka, "Influence of Water Chemistry on IGSCC Growth Rate of SUS316 Under Simulated PWR Primary Water," Proc. Symp. on Water Chemistry and Corrosion of Nuclear Power Plants in Asia 2005 (Gyeormju, Korea: Korean Atomic Energy Research Institute, 2005), p. 133.
14. K. Arioka, K. Kaneshima, T. Yamada, T. Terachi, "Influence of Hydrogen, Boric Acid, and Grain Boundary Carbide on IGSCC Behaviors of SUS316 Under Hydrogenated PWR Primary Water," Proc. 11th Int. Symp. on Environmental Degradation of Materials In Nuclear Power Systems - Water Reactors, ed. G.S. Was (La-Grange Park, IL: American Nuclear Society, 2003).
15. K. Arioka, G. Chiba, T. Yamada, T. Terachi, "Influence of Orientation of Cold Work and Carbide Precipitation on IGSCC Behaviors of SUS316 in Hydrogenated High-Temperature Water," Proc. 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. L. Nelson, P. King, T. Allen (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS], 2005).
16. K. Arioka, T. Yamada, T. Terachi, R.W. Stachle, Corrosion 62 (2006): p. 74.
17. K. Arioka, T. Yamada, T. Terachi, G. Chiba, Corrosion 62 (2006): p. 568.
18. K. Arioka, T. Yamada, T. Terachi, G. Chiba, "Cold Work and Temperature Dependence on Crack Growth Behaviors of Austenltic Stainless Steels in Hydrogenated and Oxygenated High Temperature," Proc. Int. Symp. Fontevraud 6 (Paris, France: French Nuclear Society, 2006), p. 51.
19. K. Arioka, T. Yamada, T. Terachi, G. Chiba, Corrosion 63 (2007): p. 1, 114.
20. W.E. Berry, E.L. White, W.K. Boyd, Corrosion 29 (1973): p. 451.
21. R.L. Cowan, B.M. Gordon, "Intergranular Stress Corrosion Cracking and Grain Boundary Composition of Fe-Cr-Nl Alloy," Proc. Stress Corrosion Cracking and Hydrogen Embrittlement of Iron-Based Alloys, eds. R.W. Staehle, J. Hochmann, R.D. McCright (Houston, TX: NACE, 1978), p. 1,023.
22. K. Arioka, M. Hourai, S. Okamoto, K. Onlmura, "The Effect, of Boric Acid, Solution Temperature, and Sensitization on SCC Behavior Under Elevated Temperature Water," CORROSION/1983, paper no. 135 (Houston, TX: NACE, 1983).
23. F.P. Ford, D.F. Taylor, P.L. Andresen, R.G. Bellinger, "Environmentally Controlled Cracking of Stainless Steels in Light Water Reactor Environments," in Environmentally Controlled Cracking of Stainless Steels in Light Water Reactor Environments, NP-5064M (Palo Alto, CA: Electric Power Research Institute, 1987).
24. S.M. Bruemmer, B.W. Arey, L.A. Chariot, Corrosion 48 (1992): p. 42.
25. P.L. Andresen, "Effect of Noble Metal Coating and Alloying on Stress Corrosion Crack Growth Rate of Stainless Steel in 288°C Water," Proc. 6th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. R.E. Gold, E.P. Simonen (Littleton, CO: American Institute of Mining, Metallurgical, and Petroleum Engineers [AIME], 1994), p. 245.
26. P.L. Andresen, "Effect of Specific Anionic Impurities on Environmental Cracking of Austenltic Materials in 288°C Water," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. D. Cublcclottl (LaGrange Park, IL: American Nuclear Society, 1991), p. 209.
27. L.E. Thomas, S.M. Bruemmer, "Analytical Transmission Electron Microscopy Characterization of Stress Corrosion Cracks in a Irradiated Type 316 Stainless Steel," Proc. Int. Symp. Fontevraud 5 (Paris, France: French Nuclear Society, 2002), p. 347.
28. S.M. Bruemmer, L.E. Tilomas, "Insight into Environmental Degradation Mechanisms from High-Resolution Characterization on Crack Tips," Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and Stress Corrosion Cracking, ed. R.H. Jones (Warrendale, PA: The Minerals, Metal, and Materials Society [TMS], 2001), p. 123.
29. L.E. Thomas, S.M. Bruemmer, "High Resolution Analytical Electron Microscopy Characterization of Environmentally Assisted Cracks in Alloy 182 Weldments," Proc. 1 lth Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, ed. G.S. Was (LaGrange Park, IL: American Nuclear Society, 2003).
30. L.E. Thomas, P.L. Andresen, S.M. Bruemmer, "High Resolution Characterization of Stress Corrosion Cracks in Austenltic Stainless Steel from Crack Growth Tests in LWR Simulated Environments," Proc. 12th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. L. Nelson, P. King, T. Allen (Warrendale, PA: The Minerals, Metal, and Materials Society [TMS], 2005).
31. L.E. Thomas, S.M. Bruemmer, Corrosion.56 (2000): p. 572.
32. L.E. Thomas, S.M. Bruemmer, "High Resolution Characterization of Stress Corrosion Crack Tips in Stainless Steel Core Internals," Proc. Int. Symp. Fontevraud 6 (Paris, France: French Nuclear Society, 2006), p. 553.
33. L.E. Thomas, S.M. Bruemmer, "Crack-Tip Characteristics in BWR Service Components," Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, eds. P. King, T. Allen (Toronto, Canada: Canadian Nuclear Society, 2007).
34. L.E. Thomas, S.M. Bruemmer, "Comparison of IGSCC Crack-Tip Characteristics Produced in BWR Oxidizing Water and BWR Hydrogen Water Chemistry Conditions," Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. P. King, T. Allen (Toronto, Canada: Canadian Nuclear Society, 2007).
35. J.K. Sung, G.S. Was, Corrosions (1991): p. 824.
36. G.S. Was, J.K. Sung, T.M. Angellu, Metall. Trans. A., Phys. Metall. Mater. Sci. 23A (1992): p. 1,033.
37. T.M. Angeliu, J.K. Sung, G.S. Was, "The Role of Carbon and Chromium on the Mechanical and Oxidation Behavior of Nickel Based Alloys in High-Temperature Water," Proc. 5th Int.Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, ed. D. Cubicclotti (LaGrange Park, IL: American Nuclear Society, 1991), p. 475.
38. T.M. Angellu, G.S. Was, Metall Trans. A., Phys. Metall. Mater. Sci. 25A(1994): p. 1,169.
39. T.M. Angeliu, D.J. Paraventl, G.S. Was, Corrosion 51 (1995): p. 837.
40. Y. Yi, G.S. Was, J. Cookson, "Creep of Nickel-Based Alloys in High-Temperature Water," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, eds. S. Bruemmer, P. Ford, G.S. Was (Warrendale, PA: The Minerals, Metals, and Materials Society [TMS], 1999), p. 269.
41. B. Capell, L. Fournier, G.S. Was, "Intergranular Cracking Behavior of Ni-xCr-9Ni-C Alloys in Hydrogenated Steam," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactor, eds. P. Ford, G.S. Was (Houston, TX: NACE, 2001).
42. F. Vaillant, J.-D. Mithleux, O. de Bouvier, D. Vacon, G. Zacharie, Y. Brechet, F. Louchet, "Influence of Chromium Content and Microstructure on Creep and PWSCC Resistance of Nickel-Based Alloys," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactor, eds. S.M. Bruemmer, P. Ford, G.S. Was (Warrendale, PA: The Minerals, Metals, and Material Society [TMS], 1999), p. 251.
43. M.M. Hall, Jr., "Thermally Activated Dislocation Creep Model for Primary Water Stress Corrosion Cracking of Ni-Cr-Fe Alloys," Proc. Int. Symp. on Plant Aging and Life Prediction of Corrodible Structures," eds. T. Shoji, T. Shibata (Houston, TX: NACE, 1997), p. 107.
44. M.M. Hall, Jr., D.M. Symons, "Hydrogen-Assisted Creep Fracture Model for Low Potential Stress Corrosion Cracking of Ni-Cr-Fe Alloys," Proc. Staehle Symp. on Chemistry and Electrochemistry of Corrosion and SCC, ed. R.H. Jones (Warrendale, PA: The Minerals, Metals and Materials Society [TMS], 2001), p. 447.
45. D.D. Macdonald, A.C. Scott, P. Wentrcek, J. Electrochem. Soc. 128 (1981): p. 250.
46. D.D. Macdonald, Corrosion 48 (1992): p. 194.
47. I. Kaur, W. Gust, eds., Handbook of Grain and Interphase Boundary Diffusion Data. (Suttgart, Germany: Ziegler Press, 1989), p.638-791.
48. R.A. Perkins, R.A. Padgett, Jr., N.K. Tunali, Met Trans. 4 (1973): p. 2,535.
49. A.F. Smith, Met Sci 9 (1975): p. 375.
50. S.J. Rothman, L.J. Nowichi, G.M. Murch, J. Phys. F, Met Phys. 10 (1980): p. 383.
51. J.H. Wang, J. Am. Chem. Soc. 73 (1951): p. 510.
52. D.M. Himmelblau, Chem. Rev. 64 (1964): p. 527.
53. P.A. Johnson, A.L. Babb, Chem. Rev. 56 (1956): p. 387.
54. A. Akgerman, J.L. Gainer, J. Chem. Eng. Data 17 (1972): p. 372.
55. T. Tanabe, Y. Yamanishi, K. Sawada, S. Imoto, J. Nucl Mater. 122, 123(1984): p. 1,568.
56. G.A. Esteban, A. Perujo, L.A. Sedano, F. Legarda, B. Mancinelli, K. Douglas, J. Nucl. Mater. 300 (2002): p. 1.
57. P.L. Andresen, Corrosions (1993): p. 714.
58. J.B. Lee, Corrosion 37 (1981): p. 467.
59. A.K. Agrawal, G.A. Welch, J.A. Begley, R.W. Staehle, "SCC of Sensitized and Quench-Annealed Type 304 Stainless Steel in High -Purity Water," CORROSION/1978, paper no. 187 (Houston, TX: NACE, 1978).
60. W.E. Ruther, W.K. Soppet, T.F. Kassner, Corrosion 44 (1988): p. 791.
61. T. Chuang, J.R. Rice, Acta Metall. 21 (1973): p. 1,625.
62. M.P. Puls, R. Dutton, R.N. Stevens, Acta Metall 22 (1974): p. 639.
63. R. Raj, M.F. Ashby, Acta Metall. 23 (1975): p. 653.
64. K. Sadananda, Met. Trans. A 9A (1978): p. 635.
65. V. Vitek, Acta Metall. 26 (1978): p. 1, 345.
66. K. Sadananda, P. Shahinian, Met Trans. A 11A (1980): p. 267.
67. K. Sadananda, P. Shahinian, Met. Trans. A 14A (1983): p. 1,467.
68. J.P. Hirth, W.D. Nix, Acta Metall. 33 (1985): p. 359.
69. T. Shoji, T. Yamamoto, K. Watanabe, Z. Lu, "Progress in the Mechanistic Understanding of BWR SCC and Its Implication to the Prediction of SCC Growth Behavior in Plants," Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, ed. G.S. Was (LaGrange Park, IL: American Nuclear Society, 2003).
70. R.W. Balluffi, Met. Trans. A 13A (1982): p. 2,069.
71. K. Arioka, T. Yamada, T. Terachi, T. Miyamoto, "Role of Vacancy Diffusion at Crack Tip on IGSCC of CW316 in High Temperature Water," Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, eds. P. King, T. Allen (Toronto, Canada: Canadian Nuclear Society, 2007).
72. R.W. Staehle, "Critical Analysis of Tight Cracks," Proc. 13th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, eds. P. King, T. Allen (Toronto, Canada: Canadian Nuclear Society, 2007).