摘要
为研究U-Zr合金与Zr-4合金之间的相容性和扩散行为,采用真空热压扩散法制备U-10wt%Zr/Zr-4扩散偶,随后在高真空中580~1100℃高温热处理样品。采用扫描电镜和透射电镜分析检测扩散偶的界面微观结构和元素分布。系统研究了两种合金之间的相容性。δ-UZr_2层和厚约20nm的富铀层形成于热压扩散法制备的样品界面。测量了合金界面扩散系数常数和扩散激活能,分别为(4.23±0.63)×10^(-6)m^2/s和(160.73±1.67) kJ/mol。结果表明U-10wt%Zr/Zr-4扩散偶的扩散系数大于U-Zr合金的,特别是在低温段。
To investigate the compatibility and diffusion behavior between U-Zr alloys and Zr-4 alloys,solid-to-solid U-10 wt% Zr/Zr-4 diffusion couples were assembled by vacuum hot pressing and then annealed under vacuum at temperatures ranging from 580 ℃ to 1100 ℃ for various time.Scanning and transmission electron microscopes were employed to analyze the microstructures and composition profiles at the interfaces of the couples.The compatibility between the two alloys was investigated.δ-UZr2 and ~20-nm-thin U-rich layers existed in the vacuum-hot-pressed samples.The interdiffusion coefficient constant and activation energy are found to be(4.23±0.63)×10^-6 m^2/s and(160.73±1.67) kJ/mol,respectively.The interdiffusion coefficients of the U-10 wt% Zr/Zr-4 alloy couples are higher than those of U–Zr alloys,especially at low temperature.
作者
张羽廷
王鑫
刘朋闯
曾钢
庞晓轩
贾建平
盛六四
张鹏程
Zhang Yuting;Wang Xin;Liu Pengchuang;Zeng Gang;Pang Xiaoxuan;Jia Jianping;Sheng Liusi;Zhang Pengcheng(Science and Technology on Surface Physics and Chemistry Laboratory,Jiangyou 621908,China;School of Nuclear Science and Technology,University of Science and Technology of China,Hefei 230029,China;Institute of Materials,China Academy of Engineering Physics,Mianyang 621907,China)
出处
《稀有金属材料与工程》
SCIE
EI
CAS
CSCD
北大核心
2018年第9期2675-2681,共7页
Rare Metal Materials and Engineering
基金
National Natural Science Foundation of China(91226203)
ITER(2012GB106004)
关键词
金属型核燃料
包壳
界面
互扩散
混合堆
metallic fuel
cladding
interface
interdiffusion
hybrid reactor