[1]Bamford W,Hall J. A review of alloy 600 cracking in operating nuclear plants including alloy 82 and 182 weld behavior[C]∥12th International Conference on Nuclear Engineering. Arlington:American Society of Mechanical Engineers, 2004: 131139.[2]Was G S, Andresen P L. Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments [J]. Corrosion, 2007, 63(1): 1945.[3]Boursier J M, Gallet S, Rouillon Y, et al. Stress corrosion cracking of austenitic stainless steels in PWR primary water: an update of Metallurgical Investigations Performed on French Withdrawn Components[C]∥Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors. France: Fontevraud 5 International Symposium, 2002:129136.[4]Higgins J P. The general electric report[J]. Nuclear News, 1968, 11: 3743. [5]Andresen P L, Angeliu T M, Horn R M, et al. Effect of deformation on SCC of unsensitized stainless steel [J]. Corrosion, 2000:203. [6]Andresen P L, Morra M M. Stress corrosion cracking of stainless steels and nickel alloys in hightemperature water [J]. Corrosion, 2008, 64(1): 1529. [7]Arioka K. Effect of temperature, hydrogen and boric acid concentration on IGSCC susceptibility of annealed 316 stainless steel[C]∥Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors. France: Fontevraud 5 International Symposium, 2002: 149158. [8]Arioka K, Yamada T, Terachi T, et al. Cold work and temperature dependence of stress corrosion crack growth of austenitic stainless steels in hydrogenated and oxygenated hightemperature water [J]. Corrosion, 2007, 63(12): 11141123.[9]Ilevbare G O, Cattant F, Peat N K. SCC of stainless steels under PWR service conditions[C]∥Proceedings of the 7th International Conference on Contribution of Materials Investigations to Improve the Safety and Performance of LWRs. France: Fontevraud 7 International Symposium, 2010:2630[10]Suzuki S, Takamori K, Kumagai K, et al. Stress corrosion cracking in low carbon stainless steel components in BWRs [J]. EJournal of Advanced Maintenance, 2009(1): 129.[11]Kain V, Chandra K, Adhe K N, et al. Effect of cold work on lowtemperature sensitization behaviour of austenitic stainless steels [J]. Journal of Nuclear Materials, 2004, 334(2): 115132.[12]Andresen P L, Morra M M. IGSCC of nonsensitized stainless steels in high temperature water [J]. Journal of Nuclear Materials, 2008, 383(1): 97111.[13]杜东海,余论,陈凯,等. 直流电压降法应力腐蚀裂纹扩展速率在线测定试验系统[J]. 理化检验:物理分册,2014, 50(1): 2530.DU Donghai, YU Lun, CHEN Kai, et al. Measurement system for stress corrosion cracking growth rate based on driect current potential drop method[J]. Physical Testing and Chemical Analysis Pat A: Physical Testing, 2014, 50(1): 2530.[14]Andresen P L. Emerging issues and fundamental processes in environmental cracking in hot water [J]. Corrosion, 2008, 64(5): 439464. |