堆用不锈钢在模拟一回路中腐蚀的穆斯堡尔研究  

Mssbauer corrosion steady of reactor stainless steel with the simulated first loop

作　　者：黄红波[1] 吴东岷[1] 施海蓉[1] 肖煜明[1] 李世民[1] 夏元复[1] 

机构地区：[1]南京大学物理系,南京210093

出　　处：《核技术》2001年第2期94-101,共8页Nuclear Techniques

基　　金：国家自然科学基金!(19835050);高校博士学科点专项科研基金!(98-00);江苏省自然科学基金资助!(BK-97041

摘　　要：用透射、内转换电子和内转换Ｘ射线发射三种穆斯堡尔谱学方法，配合Ｘ射线衍射和俄歇电子能谱研究核电站用不锈钢Ｆ３１６Ｔｉ的腐蚀。钝化膜和腐蚀产物的组分及微观结构，提供了研究堆用不锈钢腐蚀的微观结构研究基础。通过腐蚀机理，可以与宏观腐蚀的数据相印证。结果表明，抗蚀不仅与碳含量有关，尤其与热处理过程以及表层团溶状态有关。The stainless steel (F316Ti) used in reactor have been studied with the methods Of Mossbauer spectroscopy, including transmission, conversion electron and conversion X -- ray spectroscopy, and assisted with X -- ray diffraction and Auger electron spectroscopy. The components and microstructure of the passivation layer and corrosion products provided the foundation in studying the microstructure of corrosion about the reactor stainless steel. The result could be confirmed by the macroscopic results with corrosion mechanism. The experiment indicated that the erosion resistance is not only related with the content of carbon, but most importantly with the heat treatment process of solid solution and solid solution condition.

关 键 词：穆斯堡尔谱学 核反应堆 奥氏体不锈钢 一回路模拟 材料 腐蚀 抗腐蚀性能 

分 类 号：TL341[核科学技术—核技术及应用] TG171[金属学及工艺—金属表面处理]