高密度等离子体与钨和碳化钨相互作用研究

项目名称： 高密度等离子体与钨和碳化钨相互作用研究

项目编号： No.11275135

项目类型： 面上项目

立项/批准年度： 2013

项目学科： 数理科学和化学

项目作者： 芶富均

作者单位： 四川大学

项目金额： 86万元

中文摘要： 本项目主要针对碳和钨混用的偏滤器部件在聚变堆运行环境下碳化物再沉积、氢对碳钨化合物的腐蚀和氢滞留行为，通过利用直线偏滤器模拟装置和实时分析测试手段以及理论模型相结合的方法，系统揭示模拟装置中H2/He等离子体输运特性，为进一步设计大面积、高密度等离子体源提供帮助。研究解释含碳杂质的高密度H2/He等离子体对钨材料表面辐照损伤过程，揭示影响含碳化合物的沉积过程和H滞留的主要物理因素，探索减少碳化物再沉积和H滞留的方法；研究碳化钨材料在高密度H2/He等离子体辐照下腐蚀过程,解释和预言高密度H2/He等离子体对碳化钨样品的腐蚀和氢滞留行为；探索改善壁材料抗腐蚀行为的新方法和减少杂质产生的新方法；为先进磁约束聚变装置（如HL-2A和EAST）及ITER的安全运行提供科学和技术支撑。

中文关键词： 聚变；偏滤器；滞留；溅射；等离子体

英文摘要： In ITER fusion reactor, the D/T fluxes foreseen are about 1024m-2s-1 and energy fluxes of about 10 MWm-2s-1.Carbon and tungsten are chosen as main cadidates. Due to its high thermal conductivity and high-temperature stability, graphite has been used as plasma-facing materials in tokamaks. However,the high chemical erosion rates of graphite for ITER are a critical issue for long operation. Tungsten is no chemical erosion and dust formation. However, hydrogen can be accumulated in tungsten to result in blister formation. When blisters burst, some tungsten may ejected into plasma. Even a few tungsten may stop the fusion process. Therefore, one choice is to use carbon and tungsten as divertor materials.In order to understand interactions between plasma and surfaces ocurring in fusion reactors, one linear divertor simulator has been constructed in our group. In this proposal, one project focusing on plasma interacting with tungsten and tungsten carbide is present. In this project, in order to get insight into redeposition of carbon on tungsten and H retention in fromed films, we plan to study (1) plasma properties in the divertor simulator. (2) H2/He plasma with carbon impurities interacting with tungsten. (3) H2/He plasma interacting with tungsten carbide.

英文关键词： fusion；divertor；retention；sputtering；plasma