Effects of local radiolysis and geometric parameters on intergranular attack caused by crevice corrosion

References

• Was GS, Busby JT. Role of irradiated microstructure and microchemistry in irradiation-assisted stress corrosion cracking. Philos Mag. 2005;85(4–7):443–465.
   Web of Science ®Google Scholar
• Wada Y, Ishida K, Tachibana M. Effectiveness analysis of noble metal treatment to mitigation of intergranular stress corrosion cracking of stainless steel in BWR reactor water environment. Proceedings of 11th International Confererence on Environmental Degradation of Materials in Nuclear Power Systems; 2003 Aug 10−14; Stevenson (WA). ( CD-ROM).
   Google Scholar
• Law RJ, Indig ME, Lin CC, Cowan RL. Suppression of radiolytic oxygen produced in a BWR by feedwater hydrogen addition. Proceedings of 3rd International Conference on Water Chemistry of Nuclear Reactor Systems; 1983 Oct 17–21; Bournemouth, UK.
   Google Scholar
• Hettiarachchi S, Law RJ, Diaz TP, Cowan RL, Keith W, Pathania RS. The first in-plant demonstration of noble metal chemical addition technology for IGSCC mitigation of BWR internals. Proceedings of 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors; 1997 Aug 10–14; Amelia Island (FL).
   Google Scholar
• Ohnaka N, Shoji S, Kikuchi E, Minato A, Ito H. [Effects of environmental factors on the IGSCC susceptibility of sensitized SUS 304 stainless steel in high temperature water]. Boshoku-Gijutsu. 1983;32:214–220. Japanese.
   Google Scholar
• Wada Y, Watanabe A, Ishida K, Tachibana M, Shigenaka N, Kawashima N, Aizawa M. Local radiolysis and electrochemical corrosion potential in crevice environment. Proceedings of the 9th International Radiolysis, Electrochemistry and Material Performance Workshop; 2012 Sep 28; Paris, France. ( [CD-ROM] ISBN978-2-9516195-3-1).
   Google Scholar
• Tachibana M, Ishida K, Wada Y, Shimizu R, Ota N, Hara N. Determining factors for anodic polarization curves of typical structural materials of boiling water reactors in high temperature–high purity water. J Nucl Sci Technol. 2007;44:253–262.
   Google Scholar
• Miller WD, Indig ME, Lawrence Nelson J, Wozadlo GP. Investigation of the protection potential against irradiation assisted stress corrosion cracking. Proceedings of 5th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems –Water Reactors; 1991 Aug 25–29; Monterey (CA).
   Google Scholar
• Wada Y, Ishida K, Tachibana M, Aizawa M, Fuse M. Hydrazine and hydrogen coinjection to mitigate stress corrosion cracking of structural materials in boiling water reactors (VII) – effects of bulk water chemistry on ECP distribution inside a crack. J Nucl Sci Technol. 2007;44(11):1448–1457.
   Web of Science ®Google Scholar
• Chao CY, Lin LF, MacDonald DD. A point defect model for anodic passive films. J Electrochem Soc. 1981;128(6):1187–1194.
   Web of Science ®Google Scholar
• Wada Y, Ishida K, Watanabe A, Tachibana M, Aizawa M, Fuse M. Effects of γ-rays irradiation upon SCC initiation and propagation under BWR conditions. Proceedings of 14th International Confererenec on Environmental Degradation of Materials in Nuclear Power Systems; 2009 Aug 23–27; Virginia Beach (VA). (CD-ROM).
   Google Scholar
• Wada Y, Ishida K, Tachibana M, Aizawa M, Fuse M, Kadoi E, Takiguchi H. Hydrazine and hydrogen co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors (IV). J Nucl Sci Technol. 2007;44(4):607–622.
   Web of Science ®Google Scholar
• Spunks JWT, Woods RJ. An introduction to radiation chemistry. Vol. 262. New York (NY): Wiley; 1990.
   Google Scholar
• Uchida S, Shigenaka N, Tachibana M, Wada Y, Sakai M, Akamine K, Ohsumi K. Effects of hydrogen peroxide on intergranular stress corrosion cracking of stainless steel in high temperature water (I). J Nucl Sci Technol. 1998;35:301–308.
   Web of Science ®Google Scholar