摘要
针对压力容器密封面材料在核工程应用中发生的腐蚀问题,研究了反应堆压力容器密封面材料非正常工况下的腐蚀性能。利用静态高压釜研究308L不锈钢在不同Cl-浓度条件下的腐蚀行为,采用金相显微镜和扫描电镜(SEM)对样品进行观察和分析。结果表明,在270℃、5.5 MPa条件下,Cl-浓度低于1 mg/L时308L不锈钢没有发生点腐蚀、缝隙腐蚀和应力腐蚀;随着Cl-浓度提高,308L不锈钢对点腐蚀、缝隙腐蚀和应力腐蚀的敏感性显著增加。
Based on the corrosion issue of sealing surface material for RPV in some nuclear projects,the corrosion properties of sealing surface material for RPV under abnormal working conditions were investigated.The corrosion behavior of 308L stainless steel were studied by using autoclave in different contents of Cl-solutions,and these samples were observed and analyzed by means of the metalloscope and Scanning electron microscope（SEM）.Results show that no pitting,crevice and stress corrosion occurred,when the content of Cl-was lower than 1 mg/L at the temperatures of 270℃ and the pressure of 5.5 MPa.However,with the increase of the content of Cl-,the susceptibility to pitting,crevice and stress corrosion of 308L was enhanced remarkably.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2012年第1期83-87,共5页
Nuclear Power Engineering
