高密度等离子体与钨和碳化钨相互作用研究

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.

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。

针对碳和钨材料混用的偏滤器部件在聚变堆运行环境下的碳化物再沉积、氢对碳钨化合物的腐蚀和氢滞留行为，我们利用直线偏滤器模拟装置，结合等离子体特性研究和材料辐照实验，开展了如下实验（a）利用等离子体质量和能量分析仪和朗缪尔探针等原位诊断设备，研究了输运腔室中H2/He等离子体特性；（b）通过材料分析方法和理论相结合，研究在含碳高密度H2/He等离子体辐照下，碳化物在钨材料表面的沉积过程、H滞留行为。（c) 通过理论和实验相结合的手段，研究了高密度H2/He等离子体辐照下碳化钨材料表面溅射、刻蚀和H滞留过程。通过大量实验和理论模拟，建立了描述偏滤器模拟装置中等离子体输运过程的方法和物理模型,揭示了高密度等离子体与壁材料相互作用微观物理机制。培养了两个硕士和一个博士。发表文章17 篇，其中SCI收录6 篇。