表面状态对核电关键材料腐蚀和应力腐蚀的影响
收稿日期: 2023-03-24
网络出版日期: 2023-04-03
基金资助
国家重点基础研究发展计划项目(2011CB610500);国家重点基础研究发展计划项目(2006CB610500);国家重大科技专项项目(2011ZX06004-009);国家重点研发计划项目(2016YFE0105200);中国科学院重点部署项目(ZDRW-CN-2017-1);中国科学院前沿科学重点研究计划项目(QYZDY-SSW-JSC012)
Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials
Received date: 2023-03-24
Online published: 2023-04-03
Supported by
National Basic Research Program of China(2011CB610500);National Basic Research Program of China(2006CB610500);National Science and Technology Major Project of China(2011ZX06004-009);National Key Research and Development Program of China(2016YFE0105200);Key Programs of Chinese Academy of Sciences(ZDRW-CN-2017-1);Key Research Program of Frontier Sciences, Chinese Academy of Sciences(QYZDY-SSW-JSC012)
全球迄今发生的核电安全事件往往是由局部腐蚀造成,而局部腐蚀从表面起始。表面状态如何影响腐蚀,以及辐照和应力与之的交互作用已经成为核电站运行安全性、可靠性、经济性保障的重要技术难题之一。本文系统总结了在过去十余年的国家系列项目支持下,针对核电用关键结构材料在不同表面加工与划伤后微观组织变化、在模拟核电站一回路水中的腐蚀、应力腐蚀和辐照促进应力腐蚀行为,并将这些腐蚀行为与材料的微观组织以及力学、辐照等多因素相关联。结果表明,打磨、划伤和切削加工都会使材料近表面产生不同程度的梯度结构,表面变形层状态存在较大差异。划伤后,在划伤底部存在大于屈服极限的残余压应力。相同粗糙度的切削加工表面,机加工参数不同可以导致深度方向上形成的纳米晶区、晶粒畸变区梯度结构明显不同。这种微观组织与局部应力应变条件使得材料抗腐蚀能力差异显著,例如划伤导致的应力腐蚀裂纹数量与划伤深度正相关。在辐照、腐蚀、应力的联合作用下,辐照促进应力腐蚀敏感性进一步升高。最后展望了未来发展趋势。
韩恩厚 , 王俭秋 . 表面状态对核电关键材料腐蚀和应力腐蚀的影响[J]. 金属学报, 2023 , 59(4) : 513 -522 . DOI: 10.11900/0412.1961.2023.00123
Global nuclear power events are often caused by local corrosion, which starts at the surface. The effect of the surface state on corrosion and the interaction among corrosion, irradiation, and stress are important technical problems affecting the safety, reliability, and economy of nuclear power plants. In this paper, supported by a series of national projects in the last 10 years, the various surface state effects, for key structural materials used in nuclear power plants after surface finishing, grinding, machining, or scratching, on corrosion and stress corrosion behaviors in the simulated primary water of nuclear power plants are reviewed. The results show that surface grinding, scratching, or cutting can cause the formation of microstructures of different gradients near the surface and also cause large differences in surface deformation. For example, the residual compressive stress is greater than the yield stress in the superficial surface of the scratch; the different cutting parameters can cause the various gradient structures of the nanocrystalline and grain distortion zones to form along the depth of the cutting surface with similar surface roughness. Such microstructures and local stress-strain conditions lead to significant differences in corrosion resistance. For example, the number of stress corrosion cracks is positively correlated with scratch depth. Under the combined action of irradiation, corrosion, and stress, irradiation-assisted stress corrosion is further enhanced. Finally, the future research trend on the topic is forecast.
| 1 | MacDonald P E, Shah V N, Ward L W, et al. Steam generator tube failures [R]. NUREG/CR-6635, Idaho National Engineering Laboratory, Lockheed Idaho Technologies Company, 1996 |
| 2 | Staehle R W. Assessment of and proposal for a mechanistic interpretation of the SCC of high nickel alloys in lead-containing environments [A]. 11th Int. Conf. Environmental Degradation of Materials in Nuclear Systems [C]. Stevenson, WA, Aug.10-14, 2003 |
| 3 | 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: 931 |
| 4 | Andresen P L. Understanding and predicting stress corrosion cracking (SCC) in hot water [A]. Stress Corrosion Cracking of Nickel Based Alloys in Water-Cooled Nuclear Reactors, The Coriou Effect [M]. Woodhead Publishing: Elsevier, 2016: 169 |
| 5 | Han E-H, Wang J Q, Wu X Q, et al. Corrosion mechanisms of stainless steel and nickel base alloys in high temperature high pressure water [J]. Acta Metall. Sin., 2010, 46: 1379 |
| 韩恩厚, 王俭秋, 吴欣强 等. 核电高温高压水中不锈钢和镍基合金的腐蚀机制 [J]. 金属学报, 2010, 46: 1379 | |
| 6 | Han E-H. Research trends on micro and nano-scale materials degradation in nuclear power plant [J]. Acta Metall. Sin., 2011, 47: 769 |
| 韩恩厚. 核电站关键材料在微纳米尺度上的环境损伤行为研究——进展与趋势 [J]. 金属学报, 2011, 47: 769 | |
| 7 | Zhang Z M, Wang J Q, Han E-H, et al. Analyses of surface oxide films on ground alloy 690TT after immersion for different times [J]. Acta Metall. Sin., 2011, 47: 823 |
| 张志明, 王俭秋, 韩恩厚 等. 打磨态690TT合金经不同时间浸泡后表面氧化膜结构分析 [J]. 金属学报, 2011, 47: 823 | |
| 8 | Zhang Z M, Wang J Q, Han E-H, et al. Analyses of surface oxide films on electropolished alloy 690TT after immersion for different times [J]. Acta Metall. Sin., 2011, 47: 831 |
| 张志明, 王俭秋, 韩恩厚 等. 电解抛光态690TT合金经不同时间浸泡后表面氧化膜结构分析 [J]. 金属学报, 2011, 47: 831 | |
| 9 | Zhang Z M, Wang J Q, Han E-H, et al. Effects of surface condition on corrosion and stress corrosion cracking of alloy 690TT [J]. J. Chin. Soc. Corros. Prot., 2011, 31: 441 |
| 张志明, 王俭秋, 韩恩厚 等. 表面状态对690TT合金腐蚀及应力腐蚀行为的影响 [J]. 中国腐蚀与防护学报, 2011, 31: 441 | |
| 10 | Zhang Z M, Wang J Q, Han E-H, et al. Influence of dissolved oxygen on oxide films of alloy 690TT with different surface status in simulated primary water [J]. Corros. Sci., 2011, 53: 3623 |
| 11 | Zhang Z M, Wang J Q, Han E-H, et al. Characterization of different surface states and its effects on the oxidation behaviours of alloy 690TT [J]. J. Mater. Sci. Technol., 2012, 28: 353 |
| 12 | Zhang Z M, Wang J Q, Han E-H, et al. Effects of surface state and applied stress on stress corrosion cracking of alloy 690TT in lead-containing caustic solution [J]. J. Mater. Sci. Technol., 2012, 28: 785 |
| 13 | Zhang Z M, Wang J Q, Han E-H, et al. Analysis of surface oxide films formed in hydrogenated primary water on alloy 690TT samples with different surface states [J]. J. Mater. Sci. Technol., 2014, 30: 1181 |
| 14 | Zhang Z M, Wang J Q, Han E-H, et al. Analysis of surface oxide film formed on eletropolished alloy 690TT in high temperature and high pressure water with sequentially dissolved hydrogen and oxygen [J]. Acta Metall. Sin., 2015, 51: 85 |
| 张志明, 王俭秋, 韩恩厚 等. 电解抛光态690TT合金在顺序溶氢/溶氧的高温高压水中表面氧化膜结构分析 [J]. 金属学报, 2015, 51: 85 | |
| 15 | Meng F J, Wang J Q, Han E-H, et al. Effects of scratching on corrosion and stress corrosion cracking of Alloy 690TT at 58oC and 330oC [J]. Corros. Sci., 2009, 51: 2761 |
| 16 | Meng F J, Han E-H, Wang J Q, et al. Localized corrosion behavior of scratches on nickel-base alloy 690TT [J]. Electrochim. Acta, 2011, 56: 1781 |
| 17 | Wang J Q, Huang F, Han E-H, et al. Microscopic residual stresses beneath a scratch and their effects on scratch-related crack initiation of thermally treated UNS N06690 in high temperature pressurized water [J]. Corrosion, 2013, 69: 893 |
| 18 | Yan H L, Wang J Q, Zhang Z M, et al. Effects of cutting parameter on microstructure and corrosion behavior of 304 stainless steel in simulated primary water [J]. J. Mater. Sci. Technol., 2022, 122: 219 |
| 19 | Zhang Z M, Wang J Q, Han E-H, et al. Effects of surface machining by a lathe on microstructure of near surface layer and corrosion behavior of SA182 grade 304 stainless steel in simulated primary water [J]. Corros. Sci. Technol., 2019, 18: 1 |
| 20 | Han Y L, Mei J N, Peng Q J, et al. Effect of electropolishing on corrosion of nuclear grade 316L stainless steel in deaerated high temperature water [J]. Corros. Sci., 2016, 112: 625 |
| 21 | Han Y L, Mei J N, Peng Q J, et al. Effect of electropolishing on corrosion of alloy 600 in high temperature water [J]. Corros. Sci., 2015, 98: 72 |
| 22 | Han Y L, Han E H, Peng Q J, et al. Effects of electropolishing on corrosion and stress corrosion cracking of alloy 182 in high temperature water [J]. Corros. Sci., 2017, 121: 1 |
| 23 | Guo Y L, Han E-H, Wang J Q. Effects of surface state on the electrochemical corrosion behavior of nuclear grade 316LN stainless steel [J]. Chin. J. Eng., 2016, 38: 87 |
| 郭跃岭, 韩恩厚, 王俭秋. 表面状态对核级316LN不锈钢电化学腐蚀行为的影响 [J]. 工程科学学报, 2016, 38: 87 | |
| 24 | Guo Y L, Han E-H, Wang J Q. Effects of surface states on the oxidation behavior of 316LN stainless steel in high temperature pressurized water [J]. Mater. Corros., 2015, 66: 670 |
| 25 | Ming H L, Zhang Z M, Wang J Z, et al. Effect of surface state on the oxidation behavior of welded 308L in simulated nominal primary water of PWR [J]. Appl. Surf. Sci., 2015, 337: 81 |
| 26 | Ming H L, Zhang Z M, Wang S Y, et al. Short time oxidation behavior of 308L weld metal and 316L stainless steel with different surface state in simulated primary water with 0.1 mg/L dissolved oxygen [J]. Mater. Corros., 2015, 66: 869 |
| 27 | Guo S, Wang H T, Han E-H. Computational evaluation of the influence of various uniaxial load levels on pit growth of stainless steel under mechanoelectrochemical interactions [J]. J. Electrochem. Soc., 2018, 165: C515 |
| 28 | Wang H T, Han E-H. Ab initio molecular dynamics simulation on interfacial reaction behavior of Fe-Cr-Ni stainless steel in high temperature water [J]. Comput. Mater. Sci., 2018, 149: 143 |
| 29 | Wang H T, Sun X F, Han E-H. The interactions between high temperature water and Fe3O4 (111) by first-principles molecular dynamics simulation [J]. Int. J. Electrochem. Sci., 2018, 13: 2430 |
| 30 | Sun X F, Wang H T, Han E-H. Effect of Cr doping on the surface characteristics of Ni metal studied with first-principles calculation [J]. Acta Metall. Sin. (Engl. Lett.), 2019, 32: 461 |
| 31 | Yin X R, Wang H T, Han E-H. Effects of solvation and applied potential on the adsorption behaviors of H, O, OH and H2O on Fe(110) surface [J]. Surf. Sci., 2020, 691: 121504 |
| 32 | Yin X R, Sun X F, Wang H T, et al. Adsorption and dissociation of water on halogen pre-adsorbed Ni(111) and Ni-Cr(111) surfaces: A DFT study [J]. Solid State Commun., 2020, 321: 114040 |
| 33 | Yin X R, Wang H T, Sun S, et al. Comparative study on the adsorption behaviors of O and Cl on Fe(110) surfaces with different Cr content [J]. Mater. Today Commun., 2020, 24: 101122 |
| 34 | Wang H T, Ding J W, Zhang R F, et al. Atomistic insights into interfacial reactions of FeCr2O4 oxide films in high-temperature water [J]. Int. J. Electrochem. Sci., 2020, 15: 8662 |
| 35 | Meng F J, Wang J Q, Han E-H, et al. Microstructure near scratch on alloy 690TT and stress corrosion induced by scratching [J]. Acta Metall. Sin., 2011, 47: 839 |
| 孟凡江, 王俭秋, 韩恩厚 等. 690TT合金划痕显微组织及划伤诱发的应力腐蚀 [J]. 金属学报, 2011, 47: 839 | |
| 36 | Meng F J, Wang J Q, Han E-H, et al. Stress corrosion crack initiation for scratched alloy 690TT in oxygenated high temperature water [J]. J. Chin. Soc. Corros. Prot., 2013, 33: 413 |
| 孟凡江, 王俭秋, 韩恩厚 等. 划伤690TT合金在高温含氧水中应力腐蚀裂纹萌生的研究 [J]. 中国腐蚀与防护学报, 2013, 33: 413 | |
| 37 | Meng F J, Wu B, Lv Y H, et al. Effect of surface scratch on corrosion behavior of alloy 690TT heat exchanger tubes [J]. Chin. J. Mater. Res., 2021, 35: 827 |
| 孟凡江, 吴 斌, 吕云鹤 等. 表面划伤对690TT合金传热管腐蚀行为的影响 [J]. 材料研究学报, 2021, 35: 827 | |
| 38 | Wu B, Ming H L, Zhang Z M, et al. Effect of surface scratch depth on microstructure change and stress corrosion cracking behavior of alloy 690TT steam generator tube [J]. Corros. Sci., 2021, 192: 109792 |
| 39 | Wu B, Meng F J, Zhang Z M, et al. Stress corrosion behavior of scratched alloy 690TT steam generator tube in chlorine‐containing high‐temperature pressurized water [J]. Mater. Corros., 2022, 73: 1563 |
| 40 | Wu B, Ming H L, Meng F J, et al. Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking [J]. J. Mater. Sci. Technol., 2022, 113: 229 |
| 41 | Deng P, Peng Q J, Han E-H, et al. Study of irradiation damage in domestically fabricated nuclear grade stainless steel [J]. Acta Metall. Sin., 2017, 53: 1588 |
| 邓 平, 彭群家, 韩恩厚 等. 国产核用不锈钢辐照损伤研究 [J]. 金属学报, 2017, 53: 1588 | |
| 42 | Deng P, Peng Q J, Han E-H, et al. Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water [J]. Corros. Sci., 2017, 127: 91 |
| 43 | Deng P, Peng Q J, Han E-H, et al. Effect of the amount of cold work on corrosion of type 304 nuclear grade stainless steel in high-temperature water [J]. Corrosion, 2017, 73: 1237 |
| 44 | Deng P, Sun C, Peng Q J, et al. Study on irradiation assisted stress corrosion cracking of nuclear grade 304 stainless steel [J]. Acta Metall. Sin., 2019, 55: 349 |
| 邓 平, 孙 晨, 彭群家 等. 核用304不锈钢辐照促进应力腐蚀开裂研究 [J]. 金属学报, 2019, 55: 349 | |
| 45 | Deng P, Han E-H, Peng Q J, et al. Corrosion behavior and mechanism of irradiated 304 nuclear grade stainless steel in high-temperature water [J]. Acta Metall. Sin. (Engl. Lett.), 2021, 34: 174 |
| 46 | Deng P, Peng Q J, Han E-H, et al. Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water [J]. J. Mater. Sci. Technol., 2021, 65: 61 |
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