铝合金经Si离子辐照后的力学性能及微观组织变化研究  

Research on Mechanical Properties and Microstructure Changes of Aluminum Alloy after Si Ion Irradiation

作　　者：王星雨 卞伟[1] 郭丽娜[1] 陆燕玲[2] 李德辉[2] 彭顺米 WANG Xingyu;BIAN Wei;GUO Lina;LU Yanling;LI Dehui;PENG Shunmi(China Institute of Atomic Energy,Beijing 102413,China;Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China)

机构地区：[1]中国原子能科学研究院,北京102413 [2]中国科学院上海应用物理研究所,上海201800

出　　处：《热加工工艺》2023年第14期55-59,共5页Hot Working Technology

摘　　要：采用核用LT21铝合金作为研究对象,用1.2MeVSi^(5+)对其进行辐照实验,并通过SEM、TEM和纳米压痕等手段,对辐照后材料的微观结构和力学性能变化进行分析。结果表明,经1.2MeVSi^(5+)辐照后,铝合金中析出二次相,二次相主要由硅和铁元素构成,且样品辐照后有明显的硬化趋势。LT21合金是使用在101堆重要的结构材料,研究其离子辐照后的变化规律有利于101堆退役工作的开展与进行,并为后续堆内辐照后铝合金的研究提供对照。The nuclear LT21 aluminum alloy was used as research object,and 1.2MeVSi^(5+)was used to carry out the irradiation experiment on it.By SEM,TEM and nanoindentation,the changes in the structure morphology and mechanical properties of the irradiated material were analyzed.The results show that after 1.2MeVSi^(5+)irradiation,the secondary phase precipitates in the aluminum alloy,and the secondary phase is mainly composed of silicon and iron,and the sample has a clear tendency to harden after irradiation.LT21 alloy is an important structural material used in 101 reactor.The study of its changes after ion irradiation is beneficial to the development and progress of the 101 reactor decommissioning work,which can provide a comparison for the subsequent research on the aluminum alloy after irradiation in reactor.

关 键 词：铝合金 离子辐照 Si^(5+)离子辐照 反应堆退役 

分 类 号：TG146.2[一般工业技术—材料科学与工程]