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溶解氧对高温水中冷变形316L应力腐蚀开裂的影响规律 被引量:5

SCC Crack Growth Rate Dependence of Cold Worked 316L Stainless Steel on Dissolved Oxygen in High Temperature Water
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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0.2mg/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. 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.
出处 《上海交通大学学报》 EI CAS CSCD 北大核心 2014年第11期1644-1649,1654,共7页 Journal of Shanghai Jiaotong University
基金 大型先进压水堆核电站重大专项子项目资助(2011ZX0600400908)
关键词 316L不锈钢 高温高压 溶解氧 应力腐蚀 裂纹扩展速率 316L stainless steel high temperature and high pressure dissolved oxygen (DO) stress corrosion cracking (SCC) crack growth rate (CGR)
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参考文献14

  • 1Bamford 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.
  • 2Was G S, Andresen P L. Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments [J]. Corrosion, 2007, 63(1): 19-45.
  • 3Boursier J M, Gallet S, Rouillon Y, et al. Stress corrosion cracking of austenitic stainless steels in PWR primary water: an update of Metallurgical In- vestigations Performed on French Withdrawn Compo- nents[C]//Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors. France: Fontevraud 5 International Symposium, 2002 : 129-136.
  • 4Higgins J P. The general electric report[J]. Nuclear News, 1968, 11: 37-43.
  • 5Andresen P L, Angeliu T M, Horn R M, et al. Effect of deformation on SCC of unsensitized stainless steel i-J]. Corrosion, 2000:203.
  • 6Andresen P L, Morra M M. Stress corrosion crack- ing of stainless steels and nickel alloys in high-tem- perature water [J]. Corrosion, 2008, 64(1): 15-29.
  • 7Arioka K. Effect of temperature, hydrogen and boric acid concentration on IGSCC susceptibility of an- nealed 316 stainless steel[C]//Contribution of Mate- \ rials Investigation to the Resolution of Problems En- countered in Pressurized Water Reactors. France: Fontevraud 5 International Symposium, 2002: 149- 158.
  • 8Arioka 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]. Corro- sion, 2007, 63(12): 1114-1123.
  • 9Ilevbare 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 Per- formance of LWRs. France: Fontevraud 7 Interna- tional Symposium, 2010 : 26-30.
  • 10Suzuki S, Takamori K, Kumagai K, et al. Stress corrosion cracking in low carbon stainless steel com- ponents in BWRs [-J-]. E-Journal of Advanced Mainte- nance, 2009(1): 1-29.

二级参考文献26

  • 1CHOPRA O K,RAO A S. A review of irradiation effects on LWR core internal materials-IASCC susceptibility and crack growth rate of austenitic stainless steels[J].{H}Journal of Nuclear Materials,2011,(409):235-256.
  • 2ANDRESEN P L,WAS G S. SCC of unirradiated stainless steels and nickel alloys in hot water[A].Las Vegas,NACE,Houston:[s.n.],2008.
  • 3ANDRESEN P L. Perspective and direction of stress corrosion cracking in hot water[A].NACE.[S.l.]:[s.n.],2001.
  • 4KANE R D. Slow Strain Rate Testing for the Evaluation of Environmentally Induced Cracking[M].[S.l.]:ASTM International,1993.
  • 5TORRES P D. Stress corrosion study of PH13-8Mo stainless steel using the slow strain rate technique[R].NASA Technical Paper 2934.[S.l.]:NASA,1989.
  • 6BRETTLEJ,ORMAN S. Laboratory testing for stress corrosion cracking[J].{H}Anti-Corrosion Methods and Materials,1973,(9):3-10.
  • 7SATO Y,ATSUMI T,SHOJI T. Continuous monitoring of back wall stress corrosion cracking growth in sensitized type 304 stainless steels weldment by means of potential drop techniques[J].{H}International Journal of Pressure Vessels and Piping,2007,(84):274-283.
  • 8MERAH N. Detecting and measuring flaws using electric potential techniques[J].Journal of Quality in Maintenance Engineering,2003,(2):160-175.
  • 9ANDRESEN P L,MORRA M M. Effect of rising and falling K profiles on SCC growth rates in high temper ature water[J].Journal of Pressure Vessel Technolo gy,2007,(3):488-506.
  • 10ANDRESEN P L,HICKLING J,AHLUWALIA K S. Effects of hydrogen on SCC growth rate of Ni alloys in high temperature water[J].{H}CORROSION,2008,(9):707.

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