材料辐照损伤导致的材料失效是制约核聚变发展的关键问题之一。对于一个完整的面向等离子体部件（PFC），面向等离子体材料（PFM）与热沉材料、热沉材料与结构材料之间的连接至关重要，其服役环境下的辐照损伤已经成为聚变装置发展的一个重要技术难题。这个问题的解决与否，对于聚变堆材料的抗辐照损伤性能，以及评价材料的抗辐照损伤能力，都具有至关重要的意义。本项目拟在前期工作基础上，围绕结构与性能相互关系关键基础问题，开展聚变堆面向等离子体部件材料钨钾合金-低活化钢的制备及其辐照损伤研究，包括探索钨钾合金PFM与热沉材料、热沉材料与结构材料在高热负荷环境下界面的稳定性，阐明聚其在服役环境下热冲击、离子辐照引起的材料组织结构的演化规律，并进一步澄清辐照引起的微结构变化对材料力学性能的影响，模拟研究聚变堆环境下PFC部件材料的服役性能，为未来CFETR和DEMO中PFC部件材料的研发提供重要参考数据。

Material failure caused by radiation damage is one of the key problems in the development of nuclear fusion. For a complete plasma facing component (PFC), the joining of plasma facing material (PFM)-heat sink materials as well as heat sink material-structural material is a vital issue. Its radiation damage under service environment has become an important technical problem for fusion device development. The solution of this problem is of great significance for the anti radiation performance of the fusion reactor materials and the evaluation of the radiation damage resistance of the materials. Based on the previous work, this project will explore the preparation and the irradiation damage of WK alloy-low activation steel PFC materials in order to understand the relationship between the structure and performance. The stability of WK PFM-heat sink material, heat sink material-structural material interface will be studied under heat load, and the evolution of material structure caused by thermal shock and ion irradiation will be clarified. This study will provide important reference data for the design and development of future PFC in CFETR and DEMO.