铁离子辐照对核用304不锈钢在高温水中腐蚀行为的影响  

Effect of Iron Irradiation on Corrosion Behaviors of 304 Stainless Steel in High Temperature Water

作　　者：闫红林 张志明[1] 王俭秋[1] 韩恩厚[1] YAN Honglin;ZHANG Zhiming;WANG Jianqiu;HAN Enhou(Key Laboratory of Nuclear Materials and Safety Assessment,Institute of Metal Research,Chinese Academy of Sciences,Shenyang 110016,China;School of Materials Science and Engineering,University of Science and Technology of China,Shenyang 110016,China)

机构地区：[1]中国科学院金属研究所中国科学院核用材料与安全评价重点实验室,沈阳110016 [2]中国科学技术大学材料科学与工程学院,沈阳110016

出　　处：《腐蚀与防护》2022年第2期10-17,38,共9页Corrosion & Protection

基　　金：国家自然科学基金(51771211);国家重点研发计划(2016YFE0105200;2017YFB0702100);中科院前沿科学重点研究计划(QYZDY-SSWJSC012);中科院重点任务(ZDRW-CN-2017-1)。

摘　　要：利用3.5 MeV的铁离子对304不锈钢进行模拟辐照,研究了辐照对核电结构材料腐蚀行为的影响,并对材料内部微观结构、平均腐蚀速率、腐蚀产物形貌、结构及成分等进行了表征。结果表明,辐照使材料内部引入大量位错缺陷,增加了材料在高温水环境中的平均腐蚀速率。辐照试样腐蚀后形成的氧化膜更加不均匀,同时氧化膜内Cr含量有所降低。辐照试样中的离子扩散过程加速是导致氧化膜保护性变差,进而腐蚀加速的根本原因。Using 3.5 MeV iron ions to simulate irradiating 304 stainless steel,the effect of irradiation on the corrosion behavior of nuclear power structure materials was studied.The internal microstructure,average corrosion rate,morphology,structure and composition of corrosion products were characterized.The results showed that irradiation introduced a large number of dislocation defects inside the material,which increased the average corrosion rate of the material in a high-temperature water environment.The oxide film formed after the irradiated sample corroded was more uneven,and the Cr content in the oxide film was reduced.The acceleration of the ion diffusion process in the irradiated sample was the root cause of the deterioration of the protection of the oxide film and the acceleration of corrosion.

关 键 词：不锈钢 辐照 缺陷 腐蚀 

分 类 号：TG174[金属学及工艺—金属表面处理]