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690TT合金在高温含铅碱液中的腐蚀行为 |
胡轶嵩,王俭秋,柯伟,韩恩厚 |
中国科学院金属研究所 金属腐蚀与防护国家重点实验室 沈阳 110016 |
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CORROSION BEHAVIOR OF ALLOY 690TT IN HIGH TEMPERATURE LEAD-CONTAINING CAUSTIC SOLUTION |
HU Yisong, WANG Jianqiu, KE Wei, HAN En-hou |
State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016 |
[1] Was G S. Grain-boundary chemistry and intergranular fracture in austenitic nickel-base alloys-a review [J]. Corrosion, 1990, 46(4):319-330[2] Ding X S. Corrosion and protection of nuclear power plants steam generator tubes [J].Corros. Prot., 2000, 21(1): 15-18 (丁训慎. 核电站蒸汽发生器传热管的腐蚀与防护 [J]. 腐蚀与防护, 2000, 21(1): 15-18)[3] Ding X S. Cleaning technique for steam generators in nuclear power station [J]. Cleaning World, 2004, 20(4): 32-36 (丁训慎. 核电站蒸汽发生器传热管的清洗技术 [J]. 清洗世界, 2004,20(4): 32-36)[4] Ding X S. The operation safety of steam generators in NPP [J]. Nucl. Safety, 2004, (4): 29-34(丁训慎. 核电厂蒸汽发生器运行中的安全问题, 核安全, 2004, (4): 29-34)[5] Staehle R W, Gorman J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part 1 [J]. Corrosion, 2003, 59(11): 931-994[6] Staehle R W, Gorman J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part 2 [J].Corrosion, 2004, 60(1): 5-63[7] Staehle R W, Gorman J A.Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: Part3 [J]. Corrosion, 2004, 60(2): 115-180[8] Miglin B P, Sarver J M. Preliminary studies of lead stress corrosion cracking of alloy 690 [A]. Proceeding of the Fourth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors [C]. Jekyll Island, GA: 1989: 7-18[9] Gomez B D, Castno M L, Garcia M S. Stress corrosion cracking susceptibility of steam generator tube materials inAVT(all volatile treatment) chemistry contaminated with lead [J]. Nucl. Eng. Design,1996, 165(1): 161-169[10] Kim U C, Kim K M, Lee E H. Effects of chemical compounds on the stress corrosion cracking of steam generator tubing materials in a caustic solution [J]. J. Nucl. Mater., 2005, 341: 169-174[11] Cao C N. Corrosion Electrochemistry [M]. Beijing: Chemical Industry Press, 2004(曹楚南. 腐蚀电化学原理 [M]. 北京:化学工业出版社, 2004)[12] Ahn S J, Rao V S, Kwon H S, et al. Effects of PbO on the repassivation kinetics of alloy 690 [J]. Corros. Sci.,2006, 48(5): 1137-1153[13] Hwang S S, Kim H P, Lee D H, et al. The mode of stress corrosion cracking in Ni-base alloys in high temperature water containing lead [J]. J. Nucl. Mater.,1999, 275(1): 28-36[14] Hwang S S, Kim J S. Electrochemical interaction of lead with Alloy 600 and Alloy 690 in high-temperature water [J]. Corrosion, 2002, 58(5): 392-398[15] Montemor M F, Ferreira M G S, Walls M, et al. Influnence of pH on properties of oxide films formed on type 316L stainless steel, alloy 600, and alloy 690 in high-temperature aqueous environments [J]. Corrosion,2003, 59(1): 11-21[16] Peng B, Lu B T, Lu Y C, et al. Investigation of passive films on nickel alloy 690 in lead-containing environments [J]. J. Nucl. Mater., 2008, 378(3): 333-340[17] Ding X S. IGA/IGSCC and protection on secondary side of steam generator tubes in nuclear power plants [J]. Corros. Prot., 2002,23(10): 441-444 (丁训慎. 核电站蒸汽发生器传热管二次侧晶间腐蚀和晶间应力腐蚀及防护 [J]. 腐蚀与防护, 2002, 23(10): 441-444)[18] Thomas L E, Bruemmer S M. High-resolution characterization of intergranular attack and stress corrosion cracking of alloy 600 in high-temperature primary water [J]. Corrosion, 2000,56(6): 572-587[19] Miglin B P, Sarver J M, Psaila-Dombrowksi M J, et al. Lead assisted stress corrosion cracking of nuclear steam generator tubing materials [A]. Proceeding of Improving the Understanding and Control of Corrosion on the Secondary Side of Steam Generator [C]. Airlie, NACE: 1995: 305-320 |
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