为降低托卡马克装置长脉冲、高参数运行条件下的靶板表面溅射和热沉积，注入杂质的辐射偏滤器物理方案已陆续在国内外装置上展开初步研究。但杂质注入条件下杂质与第一壁钨材料相互作用及其对燃料滞留行为的影响尚不明晰。通过在实验室条件下开展注入杂质等离子体与钨第一壁材料相互作用的系统研究，并与EAST装置搭载实验进行对比,理解不同杂质注入条件下钨材料表面形貌、微观结构和溅射产额的变化规律，掌握杂质元素在钨材料中的键合、滞留与释放行为，揭示注入杂质等离子体辐照钨第一壁材料对燃料（氘）滞留的影响。在此基础上，建立注入杂质等离子体辐照下钨材料表面及燃料滞留变化的物理模型，最终揭示杂质注入条件下托卡马克核聚变装置中钨第一壁材料的失效形式、使用寿命及燃料滞留行为。

Radiative divertor by impurities seeding has been applied currently in high power long pulse operation Tokamak fusion device to avoid divertor damage by excessive heat and particle fluxes. However, the interaction between seeding impurity plasmas with first wall tungsten materials and it's influence on fuel retention are still not fully understood. In this research work, systematic research about the interaction of seeding impurity plasmas with first wall tungsten material will be performed in laboratory and compare with the result obtained from samples exposed to EAST Tokamak device. The research results can help us to understand the changes of the surface morphology, microstructure and sputtering yield of tungsten caused by the seeding impurity plasmas irradiation with different parameters, comprehend the bonding state between tungsten and seeding impurities, as well as the retention and releasing behavior of seeding impurities, and grasp the influence of seeding impurity plasmas irradiation on fuel (deuterium) retention in tungsten material. Based on these research results the physical model about the influence of seeding impurity plasmas irradiation on the surface of tungsten and fuel retention will be proposed to predict the service lifetime, failure mode and fuel retention behavior of tungsten material used in Tokamak nuclear fusion device under impurity seeding condition.