聚变堆材料问题是聚变能商业化能否成功的关键工程问题之一，而面向等离子体材料（PFM）比任何其它材料都要经历更严重的工况考验。在PFM服役过程中核聚变中子辐照将使材料产生严重辐照损伤，引起材料微观结构的变化，导致辐照硬化、韧脆转变温度（DBTT）升高和肿胀，从而影响材料的服役性能，严重制约核聚变工程的发展。W-K合金作为极具应用前景的聚变堆候选PFMs之一，适时开展其中子辐照损伤研究尤为必要。为此，本项目拟在已有研究基础上，利用瑞士PSI中子和HVE串列静电加速器开展W-K合金中子、离子辐照损伤等效性初步研究，包括微观结构、成分、辐照温度等因素对W-K合金中子、氢、氦及钨自离子辐照损伤性能的影响，模拟聚变中子辐照环境下的微观结构演变规律，初步揭示W-K合金的中子/离子辐照损伤行为与规律，为设计、制备服役性能更优良的PFMs及其中子辐照损伤行为评价提供实验和理论依据。

The material problem of fusion reactor is one of the key issues for the success of the commercialization of fusion energy, and plasma facing materials (PFM) have to undergo more severe working conditions than any other materials. During the service of PFM, neutron irradiation will cause serious radiation damage and change the microstructure of materials, leading to irradiation hardening, increase of ductile-brittle transition temperature (DBTT) and swelling, thus affecting the service performance of materials and seriously restricting the development of nuclear fusion engineering. W-K alloy is one of the promising candidate PFMs for fusion reactor. It is especially necessary to study neutron radiation damage in time. Therefore, on the basis of existing research, this project plans to carry out a preliminary study on the neutron and ion irradiation damage equivalence of W-K alloy using Swiss PSI neutron source and HVE accelerator, including the effects of micro-structure, composition and irradiation temperature on the damage properties of W-K alloy irradiated by neutrons, hydrogen, helium and tungsten ion. The evolution phenomena of micro-structure under fusion neutron irradiation environment will also be investigated. The damage behavior and mechanism of W-K alloy under neutron/ion irradiation are preliminarily revealed, which may provide experimental and theoretical basis for designing and preparing PFMs with better service performance, and would be helpful to evaluate their damage behavior under neutron irradiation.