聚变堆第一壁部件材料面临高热场、热应力场及强辐照场等多场耦合服役环境，其综合服役性能优劣关系到聚变装置能否安全运行及其寿命。针对W基第一壁材料脆性、抗热冲击及抗等离子刻蚀等性能问题，我们历经7年探索，成功研制出高性能大块体W-0.5%wtZrC材料：韧脆转变温度≤100度；室温热冲击开裂阈值4.4 MJ/m2；抗等离子刻蚀及氢滞留等性能优于ITER-W，有望用做未来聚变堆第一壁材料。它能否真正被选用，亟需近工况多场服役条件下的考核。为此本项目以W-0.5%wtZrC材料为研究对象，依托EAST和HL-2A/M及国内相关研究平台，通过先热负荷场后辐照场、先辐照场后热负荷场的交叉实验，结合多场同时作用下的多尺度模拟，以及EAST/HL-2A/M装置中的考核实验，开展多场耦合作用下的材料服役性能评价及其演化规律研究，揭示材料组织损伤机理及性能失效机制，为中国聚变工程实验堆第一壁选材提供科学依据。

The plasma facing materials (PFMs) of fusion reactor will face multi-fields coupling interaction including high thermal field, stress field and strong irradiation field, their comprehensive servicing performance is closely related to the safe operation and using life of fusion facilities. After 7 years of exploration by focusing on the brittlement, thermal load resistance and irradiation resistance of W based PFM, we successfully fabricated bulk W-0.5%wtZrC alloy with high performance: ductility-brittle transition temperature is lower than 100oC, critical energy density for surface cracking induced by transient thermal load at room temperature is about 4.4MJ/m2; the plasma sputtering corrosion resistance and the hydrogen retention are better than the similar W based materials, which make W-0.5wt%ZrC be a promising PFM candidate. However, whether it can be truly a PFM, it is urgent to evaluate the servicing performance under the approximate working conditions. However, currently, real multi-fields coupling experimental conditions are lacked, therefore this project will rely on the EAST, HL-2A/M and domestic related experiment platform to evaluate the servicing performance and investigate its evolution law of W-0.5wt%ZrC under multi-fields coupling conditions. This programme will be realized by adopting cross experiments with first applying thermal field and then irradiation field as well as irradiation field→high thermal field, combining the multiscale simulation with coexistence of thermal field and irradiation field as well as the assessment experiments in EAST or HL-2A/M. The purpose is to build the servicing database of W-0.5wt%ZrC material under approximately working condition and to reveal the mechanisms of the microstructure damage and performance failure, finally to provide scientific basis for choosing PFMs for China Fusion Engineering Thermal Reactor.