Intergranular stress corrosion cracking behavior of austenitic stainless steels in hydrogenated high-temperature water

Corrosion

Volumn 62, Issue 1, 2006, Pages 74-83

  Arioka, K ^a   Yamada, T ^a   Terachi, T ^a   Staehle, R W ^b  

^a INSTITUTE OF NUCLEAR SAFETY SYSTEM   (Japan)

^b UNIVERSITY OF MINNESOTA   (United States)

Author keywords

Austenitic stainless steel; Grain boundary carbide; Grain boundary sliding; Hydrogenated high temperature water; Intergranular stress corrosion cracking

Indexed keywords

FRACTURE; GRAIN BOUNDARIES; HIGH TEMPERATURE APPLICATIONS; HYDROGENATION; PRECIPITATION (CHEMICAL); STAINLESS STEEL;

AUSTENITIC STAINLESS STEEL; GRAIN BOUNDARY CARBIDE; GRAIN BOUNDARY SLIDING; HYDROGENATED HIGH-TEMPERATURE WATER; INTERGRANULAR STRESS CORROSION CRACKING;

STRESS CORROSION CRACKING;

FRACTURE; GRAIN BOUNDARIES; HIGH TEMPERATURE APPLICATIONS; HYDROGENATION; PRECIPITATION (CHEMICAL); STAINLESS STEEL; STRESS CORROSION CRACKING;

EID: 33750858975     PISSN: 00109312     EISSN: None     Source Type: Journal    
DOI: 10.5006/1.3278254     Document Type: Article

References (36)

1. M.E. Indig, A.R. Mcllree, Corrosion 35 (1979): p. 288.
2. F.P. Ford, M.J. Povich, Corrosion 35 (1979): p. 569.
3. M.E. Indig, J.L. Nelson, Corrosion 47 (1991): p. 202.
4. G. Cragnolino, L. Lin, Z. Szklarska-Smialowska, Corrosion 37 (1981): p. 312.
5. C.M. Pezze, I.L.W. Wilson. Transgranular Stress Corrosion Cracking of 304 Stainless Steel Canopy Seal Welds in PWR Systems," Proc. 4th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems, ed. D. Cubicciotti (Houston, TX: NACE International. 1989). p. 164.
6. G.V. Rao, D.E. Boyle, R. Phillips, "Metallurgical Investigation of Safety Injection System Pipe Cracking at Sequoyar Unit 2 Pressurized Water Reactor Station," Proc. Int. Symp. on Fontevraud 4 (Paris, France: French Nuclear Energy Society, 1998).
7. R. Cauvin, O. Goltrant, Y. Rouillon, E. Cazus, P. Dubuisson, P. Poitrenaud, S. Bellet, "Endommagement des Structures Internes Inferieures Soumises a Forte Fluense: Apports del'Expertise," Proc. Int. Symp. on Fontevraud 3 (Paris, France: French Nuclear -Energy Society, 1994), p. 54.
8. G. Pironet, A. Heuze, O. Goltrant, R. Cauvin, "Expertise Des Vis De Liaison Cloison-Renfort De La Centrale De Tihange 1," Proc. Int. Symp. on Fontevraud 4 (Paris. Fraace: French Nuclear Energy Society, 1998), p. 195.
9. M. Nakano, K. Fukuya, K. Fujii, M. Kodama, T. Torimaru, Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactor (La Grange Park, IL: American Nuclear Society, 2003).
10. T. Yonezawa, K. Arioka, H. Kanasaki, K. Fujimoto, S. Urata, H. Mizuta, "The Cause of Intergranular Cracking in Baffle Former Bolt Materials for PWR Core Internals," Proc. Int. Symp. on Fontevraud 4 (Paris, France: French Nuclear Energy Society, 1998), p. 237.
11. T. Yonezawa, K. Arioka, H. Kanasaki, K. Fujimoto, K. Ajiki, T. Matsuoka, S. Urata, H. Mizuta, J. At. Energy Soc. Jpn. 42 (2000): p. 212.
12. K. Arioka, T. Nojima, T. Kanechiku, C.G. Schmidt, D.D. MacDonald, T. Mager, "Critical Potential of IGSCC for Sensitized Stainless Steels under PWR Environment." The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (Kyoto, Japan: The Japan Society of Mechanical Engineers; New York, NY: ASME International, 1995). p. S112-1.
13. K. Arioka, M. Hourai, S. Okamoto, K. Onimura, "The Effect of Boric Acid, Solution Temperature, and Sensitization on SCC Behavior under Elevated Temperature Water," CORROSION/83, paper no. 135 (Houston, TX: NACE, 1983).
14. 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," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor, eds. S. Bruemmer, P. Ford (Warrendale, PA: The Minerals. Metals, and Materials Society [TMS], 1999). p. 311.
15. P.L. Andresen, M.T. 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).
16. P.L. Andresen, M.T. Angeliu, L.M. Young, "Immunity, Thresholds, and Other SCC Fiction," Proc. Staehle Symp. on Chemistry and Electrochemistry on Corrosion and Stress Corrosion Cracking, ed. R.H. Jones (Warrendale, PA: TMS, 2001). p. 65.
17. K. Arioka, "Effect of Temperature, Hydrogen, and Boric Acid Concentration on IGSCC Susceptibility of Annealed 316 Stainless Steel," Proc. Int. Symp. on Fontevraud 5 (Paris, France: French Nuclear Energy Society, 2002), p. 149.
18. K. Arioka, 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 Reactor (La Grange Park, IL: American Nuclear Society, 2003).
19. N. Totsuka, Z. Szklarska-Smialowska, Corrosion 44 (1988): p. 124.
20. Z. Szklarska-Smialowska, Z. Xia, S.W. Sharkawy, Corrosion 48 (1992): p. 455.
21. K. Arioka, T. Yamada, "Effect of Grain Boundary Chemistry on IGSCC Susceptibility of Stainless Steels in High-Temperature Water," 2001 Fall Meeting of the Atomic Energy Society of Japan (Sapporo, Japan, 2001).
22. P.L. Andresen, P.W. Emigh, M.M. Morra, R.M. Horn, "Alloy X750 Stress Corrosion Crack Growth Rate Behavior in High-Temperature Water," Proc. 11th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactor (La Grange Park, IL: American Nuclear Society, 2003).
23. K. Norring, J. Engstrom, P. Norberg, "Intergranular Stress Corrosion Cracking in Steam Generator Tubing Testing of Alloy 690 and Alloy 600 Tubes," Proc. 3rd Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactor, eds. G.J. Theus, J.R. Weeks (Warrendale, PA: The Metallurgical Society, 1988), p. 587.
24. S. Le Hong, C. Amzallag, A. Gelpi, "Modeling of Stress Corrosion Crack Initiation on Alloy 600 in Primary Water of PWRs," Proc. 9th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactor, eds. S. Bruemmer, P. Ford, G. Was (Warrendale, PA: TMS, 1999), p. 115-123.
25. A.S. O'Neill, J.F. Hall, EPRI Report NP-7094, Electric Power Research Institute, 1990.
26. M.E. Indig, D.A. Vermilyea, Corrosion 31 (1975): p. 51.
27. J.B. Lee, Corrosion 37 (1981): p. 467.
28. J.K. Sung, G.S. Was, Corrosion 47 (1991): p. 824-834.
29. G.S. Was, J.K. Sung, T.M. Angeliu, Metall. Trans. A. 23A (1992): p. 1,033-1,037.
30. T.M. Angeliu, J.K. Sung, G.S. Was, "The Role of Carbon and Chromium on the Mechanical and Oxidation Behavior of Nickel-Base Alloys in High-Temperature Water," Proc. 5th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactor (La Grange Park, IL: American Nuclear Society, 1992).
31. T.M. Angeliu, G.S. Was, Metall. Trans. A. 25A (1994): p. 1, 169-1, 183.
32. T.M. Angeliu, D.J. Paraventi, G.S. Was, Corrosion 51 (1995): p. 837-848.
33. 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. Was (Warrendale, PA: TMS. 1999), p. 269-276.
34. B. Capell, L. Fournier, G.S. Was, "Intergranular Cracking Behavior of Ni-xCr-9Fe-C Alloys in Hydrogenated Steam," Proc. 10th Int. Symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor (Houston, TX: NACE, 2001).
35. F. Vaillant, J.-D. Mithieux, O. deBouvier, D. Vancon, 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. Bruemmer, P. Ford, G. Was Warrendale, PA: TMS. 1999), p. 251-259.
36. T. Kishimoto, N. Shinya, H. Tanaka, Zairyou 37 (1988): p. 289-294.