李江,崔雄华,杨哲一,唐丽英,周荣灿,李季,王军民

• 1:西安热工研究院有限公司

摘要(Abstract)：

采用慢应变速率拉伸试验和应力腐蚀裂纹扩展试验方法，研究了630～700℃高参数先进超超临界机组候选镍基合金Inconel 740H在0、1、20 mg/L氯离子水环境中的应力腐蚀开裂性能及规律，并探讨了高质量浓度氯离子促进应力腐蚀裂纹的萌生和扩展的相关机理。结果表明：高质量浓度氯离子促进740H合金的应力腐蚀开裂，合金应力腐蚀敏感性指数断后伸长损失Iscc(δ)随氯离子质量浓度升高而增大；当氯离子质量浓度升高至20 mg/L时，断口中部和断口边缘均呈沿晶脆性断裂特征，断口附近有大量沿晶二次裂纹，此时合金发生了应力腐蚀开裂。在20 mg/L氯离子水环境中裂纹平均扩展速率达1.15×10–6 mm/s，是高纯水中裂纹平均扩展速率的111.7倍。

关键词(KeyWords)： Inconel 740H;应力腐蚀开裂;氯离子;慢应变速率拉伸;裂纹扩展

Abstract:

Keywords:

基金项目(Foundation): 陕西省自然科学基础研究计划项目（2023-JC-QN-0582）~~

作者(Author): 李江,崔雄华,杨哲一,唐丽英,周荣灿,李季,王军民

DOI: 10.19666/j.rlfd.202405105

参考文献(References)：

• [1]唐丽英,李季,李江,等. Sanicro25钢锅炉管实炉验证过程中的组织和性能演变[J].热力发电, 2022, 51(5):157-159.TANG Liying, LI Ji, LI Jiang, et al. Microstructure and performance evolution of Sanicro 25 boiler tube during demonstration in actual boiler[J]. Thermal Power Generation, 2022, 51(5):157-159.
• [2]钟犁,刘学莹,马辰昊,等.超临界水环境中应变速率对国产镍基合金应力腐蚀开裂敏感性的影响[J].腐蚀与防护, 2024, 3(3):7-16.ZHONG Li, LIU Xueying, MA Chenhao, et al. Effect of strain rate on stress corrosion cracking sensitivity of domestic nickel-based alloys in supercritical water environment[J]. Corrosion and Protection, 2024, 3(3):7-16.
• [3]袁勇,党莹樱,杨珍,等. 700℃先进超超临界机组末级过热器用新型镍铁基高温合金的组织与性能[J].机械工程材料, 2020, 44(1):44-50.YUAN Yong, DANG Yingying, YANG Zhen, et al.Microstructure and properties of Ni-Fe-base superalloy for 700℃advanced ultra supercritical unit final superheater[J]. Materials for Mechanical Engineering,2020, 44(1):44-50.
• [4]李季,唐丽英,李江,等. Inconel 740H在700℃关键部件验证试验平台中的性能演变研究[J].稀有金属材料与工程, 2021, 55(9):3304-3306.LI Ji, TANG Liying, LI Jiang, et al. Study on performance evolution of Inconel 740H operation on the key component test facility at 700℃[J]. Rare Metal Materials and Engineering, 2021, 55(9):3304-3306.
• [5] BERG H P. Corrosion mechanisms and their consequences for nuclear power plants with light water reactors[J]. Reliability:Theory&Applications, 2009,2(4):57-67.
• [6]刘肖,赵建仓,王淦刚,等.核电厂管道及焊接接头失效案例综述[J].失效分析与预防, 2013, 8(5):6-12.LIU Xiao, ZHAO Jiancang, WANG Gangang, et al.Failure analysis of pipelines and welding joints in nuclear power plant[J]. Failure Analysis and Prevention,2013, 8(5):6-12.
• [7]吴义兵,张裕,陈红雨,等.高温水中硫酸根阴离子对Inconel 600合金应力腐蚀开裂的影响[J].腐蚀与防护,2023, 44(4):9-14.WU Yibing, ZHANG Yu, CHEN Hongyu, et al. Effect of sulphate anions in high temperature water on stress corrosion cracking of Inconel 600 alloy[J]. Corrosion and Protection, 2023, 44(4):9-14.
• [8]夏大海,宋诗哲,王俭秋,等. 690和800合金在高温高压水中硫致腐蚀失效研究进展[J].金属学报,2017, 53(12):1541-1554.XIA Dahai, SONG Shizhe, WANG Jianqiu, et al.Research progress on sulfur-induced corrosion of alloy690 and 800 in high temperature and high pressure water[J]. Acta Metallurgica Sinica, 2017, 53(12):1541-1554.
• [9]林根仙,宋利君,刘灿帅,等.高温模拟压水堆一回路水中SO42–对690TT镍基合金SCC敏感性的影响[J].腐蚀与防护, 2022, 43(8):65-69.LIN Genxian, SONG Lijun, LIU Canshuai, et al. Effect of SO42–on SCC susceptibility of Nickel-based alloy690TT in simulated PWR primary water at high temperature[J]. Corrosion and Protection, 2022, 43(8):65-69.
• [10] ANDRESEN P L, MORRA M M. IGSCC of nonsensitized stainless steels in high temperature water[J].Nuclear Materials, 2008, 383(1):97-108.
• [11] DONG L J, PENG Q J, HAN E H, et al. Stress corrosion cracking in the heat affected zone of a stainless steel308L-316L weld joint in primary water[J]. Corrosion Science, 2016, 107:172-181.
• [12] DONG L J, PENG Q J, ZHANG Z M, et al. Effect of dissolved hydrogen on corrosion of 316NG stainless steel in high temperature water[J]. Nuclear Engineering and Science, 2015, 295:403-414.
• [13] EHRNSTéN U, ANDRESEN P L, QUE Z Q. A review of stress corrosion cracking of austenitic stainless steels in PWR primary water[J]. Journal of Nuclear Materials,2024, 588:154815.
• [14] CHO H, KIM B K, KIM I S. Low cycle fatigue behaviors of type 316LN austenitic stainless steel in310℃water-fatigue life and dislocation structure development[J]. Materials Science and Engineering A,2008, 476(1):248-256.
• [15] FORD F P. Quantitative prediction of environmentally assisted cracking[J]. Corrosion, 1996, 52(5):375-395.
• [16]肖纪美.应力作用下的金属腐蚀[M].北京:化学工业出版社, 1990:120-135.XIAO Jimei. Metal corrosion under stress[M]. Beijing:Chemical Industry Press, 1990:120-135.
• [17] EHRLICH K, KONYS J, HEIKINHEIMO L. Materials for high performance light water reactors[J]. Journal of Nuclear Materials, 2004, 327:140-147.