分析了在高温高压水环境下,压水堆(PWR)蒸汽发生器传热管的失效形式及原因,总结了应力腐蚀开裂(SCC)的相关机理,并针对奥氏体不锈钢的应力腐蚀开裂一一种严重的环境促进腐蚀开裂(EAC)形式,分析了相应的解决措施,特别是缓蚀剂解决措施.
参考文献
| [1] | 丁训慎.核电站蒸汽发生器传热管的腐蚀及防护[J].腐蚀与防护,2000,21:1. |
| [2] | 长谷川正义,三岛良绩.核反应堆材料手册[M].北京:原子能出版社,1983.709. |
| [3] | John Douglas. Causes and remedies for the degradation of steam generator tubings in nuclear power plants [ J ]. EPRI Journal, 1995, 5:6. |
| [4] | B R T弗罗斯特主编,周邦新,赵文金译.材料科学与技术丛书[M].北京:科学出版社,1999.10B,93. |
| [5] | [德]H.克舍著,吴荫顺译.金属腐蚀[M].北京:化学工业出版社,1978.423 |
| [6] | 褚武扬.氢损伤与滞后断裂[M].北京:冶金工业出版社,1988.234. |
| [7] | Galvele J R. Stress corrosion cracking of sensitized austenitic stainless steels in high-temperautre water [ J ]. Corros. Sci,1987, 27:1. |
| [8] | Sieradzki K, Newman R C. Stress corrosion cracking in pressureized water reactors-interpretation, modeling, and remedies[J]. Phil. Mag. A, 1985, 51: 95. |
| [9] | Rice J R, Thomson R. Surface mobility mechanism of stresscorrosion cracking[J ]. Phil. Mag. A, 1974, 29:1. |
| [10] | .张跃,褚武扬,王燕斌,等.管线钢氢致附加应力与氢致门槛应力的相关性[J].中国科学,1994,24:551. |
| [11] | 高克玮,褚武扬.高强钢中氢致附加应力的定量研究[J].中国科学,1994,24:551. |
| [12] | 陈奇志,褚武扬,肖纪美.304不锈钢应力腐蚀促进马氏体相变[J].中国科学,1994,24:291. |
| [13] | Jones P A. Stress corrosion cracking of steel in high temperature water[ J ]. Metall. Trans, 1985, 16A: 1133. |
| [14] | Kanfman M J, Fink M I. Stress corrosion crackings of alloy 600 and alloy 690 in caustic solution, electrochemical potential measurements under simulated BWR watr chemicstry conditions[ J ]. Acta Metall, 1988, 36; 2213. |
| [15] | Magnin T, Chieragatti R. Interpretation of corrosion potential data from boiling-water reactors under hydrogen water chemistry conditions [ J ]. Oltra R. Acta Metall. Mater, 1990, 38:1313. |
| [16] | 褚武扬,谷飚,高克玮.应力腐蚀机理研究的新进展[J].腐蚀科学与防护技术,1995,7:2. |
| [17] | 牛林.沈阳:中国科学院金属腐蚀与防护研究所博士学位论文[D],1998.23. |
| [18] | Szklarska-Smialowska Z, Cragnolino G. Influence of surface condition on primary water stress-corrosion cracking initiation of alloy 600[J ]. Corrosion, 1980, 36:12. |
| [19] | Congleton J, Shih H C, Shoji T, et al. Effect of initial surface preparation[J]. Corros, Sci, 1985, 25(8/9) :769. |
| [20] | 杨武,张美杰,赵国珍,等.304不锈钢在高温水中的应力腐蚀破裂[J].金属学报,1991,27(2):B116. |
| [21] | 杨武.316型不锈钢在高温水中的应力腐蚀破裂萌生应变[J].腐蚀科学与防护技术,1995,7:2. |
| [22] | P D stevens-Guille. An analysis of primary water stress corrosion cracking in PWR steam generator [ J ]. Nuclear Safety,1975, 16:3. |
| [23] | Green S J. Role of water purity on stress corrosion cracking[J].J.Pres. Ves & Piping, 1986,25:1. |
| [24] | 丁训慎.核电站蒸汽发生器的化学清洗及现场经验[J].化学清洗,1999,15:2. |
| [25] | D H Hur, H S Chung, U C Kim. Effect of water flow velocity on electrochemical corrosion potential of stainless steel in 288℃ water[J].J.Nuclear Materials, 1995,224:179. |
| [26] | H Kawamura, H Hirano. Electrochemical polarization measurements on type 304ss in high-temperature, high-purity water[J]. Corrosion, 1999, 55: 6. |
| [27] | Y J Kim. Effect of noble metal addition on electrochemical polarization behavior of hydrogen oxidation and oxygen reduction on type 304 stainless steel in high-temperature water[J ]. Corrosion, 1999, 55:6. |
| [28] | J Daret, J P N Paine, M J Partridge. Mitigation of stress corrosion cracking through suppression of radiolytic oxygen [ A ].Proc. 7th Int. symp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. Houston,TX, NACE, 1995.100. |
| [29] | P L Andresen, F P Ford, S M Murphy, et al. Proc. 4th Int.symp. on Environmental Degradation of Materials in Power Systems-Water Reactors[ C]. Houston, TX, NACE, 1995.83. |
| [30] | P L Andresen. Proc. 5th. synp. on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[ C]. La Grange Park, IL:American Nuclear Scoiety, 1992. 209. |
| [31] | S Hettiarachchi, R J Law, T P Diaz, et al. Proc. 7thInt. symp.on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C]. La Grange Park, IL: American Nuclear Society, 1997. 535. |
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