ITER中国液态锂铅实验包层模块第一壁等离子体注入氚滞留分析  

Analysis on plasma-driven accumulation of tritium in the first wall of DFLL-TBM in ITER

作　　者：宋勇[1] 黄群英[1] 吴宜灿[1] FDS团队 

机构地区：[1]中国科学院等离子体物理研究所,安徽合肥230031

出　　处：《核科学与工程》2008年第3期263-267,共5页Nuclear Science and Engineering

基　　金：国家自然科学基金项目(10775135和10675123);中科院知识创新工程项目

摘　　要：对等离子体注入ITER中国液态锂铅实验包层模块第一壁滞留的氚进行了分析,考虑了第一壁温度梯度、材料表面清洁度、加挂Be瓦及结构材料内缺陷等因素对氚滞留量的影响。分析结果显示,滞留的氚主要存在于中子辐照引起的缺陷内;氚滞留量对第一壁面向等离子体侧的清洁度及加挂Be瓦很敏感;总的氚滞留量约0.58 mg,不会对ITER真空室内氚滞留造成显著影响。The plasma-driven accumulation of tritium in the First Wall （FW） for the DuM-Functional Lithium-Lead Blanket Module （DFLL-TBM） has been evaluated. The influence of surface conditions on the FW, temperature gradient, beryllium layer clad on the plasma facing side, and trapping in defects on the tritium accumulation have been considered. The results show that most of the tritium accumulation is in the neutronproduced defects. And it is very sensitive to the surface conditions on plasma facing side and the beryllium layer clad on the front side of the FW. The total tritium inventory is about 0.58 mg, and can＇t evidently influence the tritium accumulation in the vacuum vessel of ITER.

关 键 词：氚滞留 第一壁 等离子体 实验包层模块 

分 类 号：TL64[核科学技术—核技术及应用]