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冷变形316 L不锈钢在高温高压水中的应力腐蚀
引用本文:杜东海,沈朝,陈凯,余论,张乐福,石秀强,徐雪莲.冷变形316 L不锈钢在高温高压水中的应力腐蚀[J].北京科技大学学报,2015(2):196-203.
作者姓名:杜东海  沈朝  陈凯  余论  张乐福  石秀强  徐雪莲
作者单位:1. 上海交通大学核材料腐蚀性能研究联合实验室,上海,200240;2. 上海市核电工程重点实验室,上海,200233
基金项目:国家大型先进压水堆核电站重大专项资助项目
摘    要:采用恒应力强度因子K=33 MPa·m1/2的加载方法,利用直流电压降方法在线监测核辅管道316L不锈钢在高纯水中应力腐蚀裂纹扩展速率。对比200、250、280和325℃温度下,氩气除氧和含有2 mg·L-1溶解氧的水化学环境中材料的裂纹扩展速率发现:溶解氧为2 mg·L-1时的裂纹扩展速率明显比氩气除氧时的裂纹扩展速率高。氩气除氧时,裂纹扩展速率在250℃时有一个最高点;溶解氧为2 mg·L-1的条件下,裂纹扩展速率随温度的升高而升高。

关 键 词:不锈钢  紧凑拉伸试样  高温  高压  应力腐蚀开裂  裂纹扩展速率

Stress corrosion cracking of cold worked 316 L stainless steel in high temperature and high pressure pure water
DU Dong-hai,SHEN Zhao,CHEN Kai,YU Lun,ZHANG Le-fu,SHI Xiu-qiang,XU Xue-lian.Stress corrosion cracking of cold worked 316 L stainless steel in high temperature and high pressure pure water[J].Journal of University of Science and Technology Beijing,2015(2):196-203.
Authors:DU Dong-hai  SHEN Zhao  CHEN Kai  YU Lun  ZHANG Le-fu  SHI Xiu-qiang  XU Xue-lian
Institution:DU Dong-hai;SHEN Zhao;CHEN Kai;YU Lun;ZHANG Le-fu;SHI Xiu-qiang;XU Xue-lian;Corrosion Laboratory for Nuclear Power Materials,Shanghai Jiao Tong University;Shanghai Key Laboratory for Nuclear Power Engineering;
Abstract:The stress corrosion cracking growth behavior of 316L stainless steel, which is used as nuclear auxiliary pipelines, was continuously monitored by a direct current potential drop method under a constant stress intensity factor K of 33 MPa·m1/2 . By compa-ring the cracking behavior of this material at 200, 250, 280 and 325℃ in 2 mg·L-1 oxygenated water and deoxygenated water, we found that the crack growth rate is faster in the oxygenated water than in the deoxygenated water. Experimental results also show that there is a peak of the crack growth rate of this material in the deoxygenated water at 250℃, while the crack growth rate increases with the rise of temperature in the oxygenated water.
Keywords:stainless steel  compact tensile specimens  high temperature  high pressure  stress corrosion cracking  crack growth rate
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