中子预辐照损伤对钨中氢滞留行为影响机制的多尺度模拟  

Influence mechanisms of neutron pre-irradiation damage on hydrogen retention in tungsten:A multiscale modeling

作　　者：郑淇蓉 刘俊 李鹏迪[1,3] 魏留明 李永钢 曾雉 ZHENG Qi-Rong;LIU Jun;LI Peng-Di;WEI Liu-Ming;LI Yong-Gang;ZENG Zhi(Key Laboratory of Materials Physics,Institute of Solid State Physics,HFIPS,Chinese Academy of Sciences,Hefei,230031,China;Science Island Branch of Graduate School,University of Science and Technology of China,Hefei,230031,China;Institute for Computational Materials Science,Department of Physics,Henan University,Kaifeng 475004,China)

机构地区：[1]中国科学院合肥物质科学研究院固体物理研究所材料物理重点实验室,合肥230031 [2]中国科学技术大学科学岛分院,合肥230031 [3]河南大学物理与电子学院计算材料研究所,开封475004

出　　处：《原子与分子物理学报》2021年第3期80-88,共9页Journal of Atomic and Molecular Physics

基　　金：国家磁约束核聚变能发展研究专项资助(2018YEF0308100);国家自然科学基金(11975018,11775254,11534012);科学挑战项目专题(TZ2018004);中国科学院青年创新促进会会员项目(2016386)。

摘　　要：高温等离子体作用下的中子辐照损伤和氢氦滞留行为一直是聚变堆钨基材料面临的两个关键问题,尤其是预辐照损伤对氢氦滞留的协同作用.鉴于制约因素的复杂性和实验上的困难,相关基础问题的理论研究至关重要.我们基于发展的顺序多尺度模拟方法研究了多晶钨的中子预辐照损伤及其对低能(20 e V)氢注入下缺陷动力学演化和氢滞留分布的影响.通过定量对比有无中子预辐照的多晶钨中氢的滞留行为,我们发现中子预辐照损伤产生的稳定空位团簇作为新的氢捕获点,加剧了氢在近表面处的滞留和表面损伤,限制了其向深度的扩散,从而导致了低能氢滞留量的急剧增加.相关结果将直接为实际等离子体环境下聚变堆钨基材料的辐照损伤和氢氦效应提供理论指导与预测.Neutron radiation damage and H/He retention behavior under high-temperature plasma irradiation are two key issues for tungsten(W)-based materials in fusion reactors,especially for the synergistic effect of pre-irradiation damage on H/He retention. Considering the complexity of constraints and the difficulties in experiment,it is thus of vital importance to perform related theoretical researches on these basic issues. We study the neutron pre-irradiation damage and its effects on defect dynamic evolution and H retention distribution under low-energy(20 eV) H exposure based on a developed sequential multiscale simulation method. Through the quantitative comparison of H retention behavior in polycrystalline W with or without neutron pre-irradiation,we found that pre-irradiation damage acts as new trapping sites for H,which aggravates H retention and damage near surface,limits H diffusion into depth,and thus results in a dramatic increase in the amount of low-energy H retention. The results will directly provide theoretical support and prediction for radiation damage and H/He effects in W-based materials under plasma interaction.

关 键 词：钨基材料 预辐照损伤 氢滞留 多尺度模拟 

分 类 号：O56[理学—原子与分子物理]