溶解氧对高温水中冷变形316L应力腐蚀开裂的影响规律

摘要/Abstract

摘要：

摘要：为研究冷变形不锈钢材料在不同溶解氧含量时的开裂规律，使用经冷弯变形的管道316L不锈钢在模拟压水堆一回路温度和压力的条件下进行实验.使用直流电压降法，原位在线测量材料在水中不同含氧量下的裂纹扩展速率.实验结果：材料的裂纹扩展速率随溶解氧含量的升高而升高.在含氧量小于0.2 mg/L时这种变化趋势非常的显著，而当超过该值后，这种变化趋势变得缓慢.对这一现象产生的原因进行了分析.

关键词: 316L不锈钢, 高温高压, 溶解氧, 应力腐蚀, 裂纹扩展速率

Abstract:

Abstract： The cold bent 316L pipe was used to study the dependence of crack growth rate on dissolved oxygen in simulated temperature and pressure of primary side water environment. The crack growth rates were measured insitu realtime using the direct current potential drop method. Experimental results indicate that the crack growth rates increase with the increase of dissolved oxygen. When the oxygen content is less than 0.2 mg/L, the increase of the crack growth rate is very significant, while above this value, it becomes unconspicuous. This result was compared with those of other researchers’ and possible reasons were analyzed.

Key words: 316L stainless steel； high temperature and high pressure, dissolved oxygen (DO);stress corrosion cracking (SCC), crack growth rate (CGR)

中图分类号:

TL 341

杜东海1，陆辉1，陈凯1，张乐福1，石秀强2，徐雪莲2. 溶解氧对高温水中冷变形316L应力腐蚀开裂的影响规律[J]. 上海交通大学学报（自然版）, 2014, 48(11): 1644-1649.

DU Donghai1，LU Hui1，CHEN Kai1，ZHANG Lefu1,SHI Xiuqiang2，XU Xuelian2. SCC Crack Growth Rate Dependence of Cold Worked 316L Stainless Steel on Dissolved Oxygen in High Temperature Water[J]. Journal of Shanghai Jiaotong University, 2014, 48(11): 1644-1649.

参考文献

［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: 131139.

［2］Was G S, Andresen P L. Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments ［J］. Corrosion, 2007, 63(1): 1945.

［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of austenitic stainless steels in PWR primary water: an update of Metallurgical Investigations Performed on French Withdrawn Components［C］∥Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors.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, 2002:129136.

［4］Higgins J P. The general electric report［J］. Nuclear News, 1968, 11: 3743.

［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 hightemperature water ［J］. Corrosion, 2008, 64(1): 1529.

［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: 149158.

［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 hightemperature water ［J］. Corrosion, 2007, 63(12): 11141123.

［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, 2010：2630

［10］Suzuki S, Takamori K, Kumagai K, et al. Stress corrosion cracking in low carbon stainless steel components in BWRs ［J］. EJournal of Advanced Maintenance, 2009(1): 129.

［11］Kain V, Chandra K, Adhe K N, et al. Effect of cold work on lowtemperature sensitization behaviour of austenitic stainless steels ［J］. Journal of Nuclear Materials, 2004, 334(2): 115132.

［12］Andresen P L, Morra M M. IGSCC of nonsensitized stainless steels in high temperature water ［J］. Journal of Nuclear Materials, 2008, 383(1): 97111.

［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): 2530.

DU Donghai, 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): 2530.

［14］Andresen P L. Emerging issues and fundamental processes in environmental cracking in hot water ［J］. Corrosion, 2008, 64(5): 439464.

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