核聚变反应中氢在钨中的滞留、起泡极大降低钨材料的热导率和溅射阈值，使得等离子体中钨杂质含量过高（高于20ppm）；同时，聚变氘-氚反应造成大量氚渗透到钨材料中并产生滞留，以上问题均能直接导致等离子体熄灭，聚变反应无法进行，直接关系聚变堆运行的安全性。因此，等离子体辐照下钨表面氢及氢同位素滞留、起泡问题是制约钨基壁材料应用的瓶颈问题，氘-氚反应产生的高能中子辐照会造成材料产生空位等缺陷，氢（氘、氚）-缺陷复合体在钨表面的产生机制与控制方法成为解决该瓶颈问题的关键科学问题，这与钨表面氢（氘、氚）聚集、起泡的动力学过程直接相关。本项目将采用自行研发的钨-氢体系的EAM原子间作用势，采用第一原理、分子动力学等方法研究氢（氘、氚）-缺陷复合体及团簇在钨近表面的聚集、迁移等动力学过程，提出对其控制方法，实现对钨表面氢泡的抑制，为钨基面对等离子材料在未来托卡马克及聚变装置中的应用提供重要理论依据和参考。

Hydrogen (H) retention and blistering in tungsten (W) can significantly reduce the thermal conductivity and sputtering threshold of W, leading to a too much high content of W impurity (higher than 20 ppm). Deuterium-tritium (D-T) reaction can cause a large amount of tritium penetrate into W and retain in W. The above problems result in the plasma extinguishing, making the failure of the operation of fusion reaction, which directly impacts on the safety and economy in a fusion reactor. Therefore, H and H isotopes retention and blistering at tungsten surfaces under the plasma radiation is a key issue for the application of W-based plasma facing material. The high energy neutron irradiation induced by D-T reaction can cause the formation of defect such as vacancy in W. Revealing the mechanism of the formation of H (D, T)-defect complexes and the control of H blistering at W surfaces is crucial for W application. This is related with dynamic processes of H and H isotopes retention, accumulation and blistering at W surfaces. In this project, we employ a first-principles method and a molecular dynamics simulation using a EAM potential of W-H system developed by our group, to investigate the dynamic behavior of H (D, T)-defects and its clusters at W surfaces. Based on these results, we expect to propose a controlling method for the H blistering at W surfaces. The perform of this project can provide a theoretical reference for the application of W-based plasma facing material in the future tokamak fusion devices.