ITER第一壁部件中有两种重要的连接界面：扩散焊接的Be/CuCrZr和爆炸焊接的SS316LN/CuCrZr界面。在堆运行中含有这些界面的部件将承受高剂量的辐照损伤、高热负荷和高周热疲劳循环，严重影响其工作寿命。我国是ITER组织的成员，将向ITER反应堆批量供应第一壁部件。在此背景下，本课题拟开展上述连接界面的辐照损伤研究，旨在填补国内外这一领域的空白。通过离子辐照实验、原子尺度的晶格缺陷表征、元素分析和与连接界面相关的残余应力测试，力图揭示：1）异质界面处的辐照缺陷类型、数量与尺寸分布特点；2）界面附近的元素互扩散机制，即：有、无辐照条件下“柯肯达尔效应”的差别；3）连接工艺中引入的位错、孪晶以及残余应力对辐照后界面显微组织的影响。这些工作对聚变堆材料的研发具有重要指导意义，而且对于阐明第一壁部件连接界面的辐照损伤机理和材料中的扩散基础理论也有很高的学术价值。

The first wall components in ITER include two types of important interfaces: diffusion welded Be/CuCrZr and explosion welded SS316LN/CuCrZr. During reactor operation, these welded components are subject to high doses of radiation damage, high thermal loads and high cycles of thermal fatigue, which are detrimental to their service life. China is a member of ITER and is responsible for the supply of first wall components. This project aims to carry out radiation damage research on the joining interfaces in these components. Based on ion irradiation experiments, atomic scale characterization of crystal defects, chemical analyses and residual stress measurements, this project aims to reveal the following: (1) radiation defect types, their number density and size distributions w.r.t. the interface; (2) the diffusion mechanism of elements (the Kirkendall effect) in the presence or absence of radiation; (3) the influence of dislocations, twins and residual stress distribution from joining process upon the interface microstructure after ion irradiation. These works not only provide important guidance for the R&D of fusion reactor materials, but are also highly valuable in the fundamental study of radiation damage & diffusion theory.