T91和316L钢在氧控铅铋中600小时后腐蚀产物分析  

Study on Corrosion Products of T91 and 316L Steels in Oxygen Controlled LBE for 600 hrs

作　　者：李明扬 姜志忠[2] 陈刘利[2] 黄群英[2] 凤仪[1] FDS凤麟核能团队 LI Ming-yang;JIANG Zhi-zhong;CHEN Liu-li;HUANG Qun-ying;FENG Yi;FDS Team(School of Materials Science and Engineering,Hefei University of Technology,Hefei,Anhui 230009,China;Key Laboratory of Neutronics and Radiation Safety,Institute of Nuclear Energy Safety Technology,Chinese Academy of Sciences,Hefei,Anhui 230031,China)

机构地区：[1]合肥工业大学材料科学与工程学院,安徽合肥230009 [2]中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室,安徽合肥230031

出　　处：《核科学与工程》2018年第5期784-789,共6页Nuclear Science and Engineering

基　　金：国家自然科学基金资助项目(No.91026002;No.51301163;No.11302224);中国科学院战略性先导科技专项"未来先进核裂变能-ADS嬗变系统"(XDA03040000)

摘　　要：本文开展了铅铋反应堆典型候选结构材料T91和316L钢在温度480℃、氧质量分数10^(-6)%、流速0.3 m/s的铅铋合金环境中600 h的初步腐蚀实验研究。利用显微镜(SEM)、能谱仪(EDS)和X射线衍射仪(XRD)等微观测试手段,对材料的腐蚀界面形貌及产物进行了分析,初步结果显示:在实验条件下T91和316L钢基体均未发生铅铋渗透及溶解腐蚀现象,腐蚀类型均为氧化腐蚀。T91钢样品表面氧化层较厚(约11μm),且分为内外两层:外层结构疏松,主要成分为Fe_3O_4。内层结构致密,主要成分为(Fe,Cr)_3O_4;而316L钢表面单层氧化层较薄(约1μm),主要成分为(Fe,Cr)_3O_4。T91 and 316L steels are the typical candidate structural materials of Pb-Bi reactor.Corrosion of them in liquid lead-bismuth eutectic(LBE)were performed at 480℃for 600 hrs with the LBE velocity of 0.3 m/s and the concentration of oxygen dissolved in LBE of 10-6 wt%.Tests on the interface pattern and products of specimens were carried out with scanning electron microscopy(SEM),energy dispersion X-ray spectroscopy(EDS)and X-ray diffraction(XRD).The preliminary results showed that both steels were suffered by oxidation corrosion but neither dissolution nor Pb-Bi penetrating into the matrix was detected.A thick oxide film^11μm was detected on the surface of T91 specimen,the oxide was composed of two sub-layers i.e.the outer layer Fe3O4 and the inner layer(Fe,Cr)3O4;while a single^1μm thinner oxide layer(Fe,Cr)3O4 was observed on 316L specimen surface.

关 键 词：铅铋合金 腐蚀 T91 316L 

分 类 号：TL341[核科学技术—核技术及应用]