辐照损伤缺陷对钨与低活化钢燃料滞留行为影响研究

钨与低活化钢分别是未来聚变装置首选第一壁与结构材料，针对这两种材料在中子辐照极端环境下与等离子体之间相互作用的重要性及现阶段基础研究的不足，本项目拟结合实验室加速器离子束辐照平台与直线等离子体源，设计辐照实验对照组，系统地研究不同重离子辐照条件下多晶W、再结晶W与CLF-1钢中氢同位素扩散迁移、键合状态、浓度分布、热脱附温度与滞留总量的变化规律。同时考察重离子模拟中子辐照损伤微观缺陷结构的形成与演变规律，并与现有中子、重离子及等离子体辐照W和EUROFER、F82H钢数据进行对比，在此基础上，理解重离子模拟中子辐照损伤对等离子体辐照后燃料滞留与捕获的影响，总结多晶W、再结晶W与CLF-1钢辐照损伤结构与燃料滞留行为变化之间联系规律，最终为预判未来商用聚变堆中钨和低活化钢材料的燃料滞留积累基础数据。

Tungsten (W) and reduced-activation ferritic martensitic (RAFM) steel are the preferred first wall and structural materials for future fusion devices, respectively. The study of the interaction between these two materials and plasma in the extreme environment of neutron irradiation is very important, and the basic research is insufficient at present. This project plans to design the irradiation experimental control group by relying on the laboratory accelerator ion beam irradiation platform and a linear experimental plasma system (LEPS). Then the project will systematically study the variation rules of hydrogen isotope diffusion and migration, bonding state, concentration distribution, thermal desorption temperature and total retention in polycrystalline W, recrystallized W and CLF-1 steel under different heavy ion irradiation conditions. At the same time, the formation and evolution of the microstructure of the heavy ion simulated neutron irradiation damage were investigated. And the achieved results will be compared with the published data based on W and other RAFM steels, such as EUROFER97 and F82H irradiated by neutron, heavy ion and plasma. Based on the research results, the influence of heavy ion bombardment to simulation the damage of neutron on fuel retention and trapping will be understood. And the relationship between irradiation damage structure and fuel retention behavior of polycrystalline W, recrystallized W and CLF-1 steel will be summarized. Finally, it will accumulate basic data for predicting fuel retention of W and RAFM steel materials in commercial fusion reactors in the future.