近来提出使用低活化铁素体马氏体钢作为聚变堆远离偏滤器第一壁主壁材料，针对低活化钢与等离子体相互作用的重要性及现阶段CLAM、CLF-1钢作为第一壁主壁材料基础研究的不足，本项目拟在实验室条件下模拟边界等离子体特点，系统地研究不同等离子体辐照条件下CLAM、CLF-1以及EUROFER97低活化钢材料表面形貌、微观结构、溅射产额的变化，以及这种变化对燃料在低活化钢材料中的扩散、滞留与释放的影响，同时考察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，并与现有EUROFER、F82H数据进行对比。在此基础上总结CLAM以及CLF-1两种低活化钢作为第一壁主壁材料表面刻蚀及燃料滞留变化的规律，预判装置中低活化钢第一壁主壁材料使用寿命、失效形式、燃料滞留并界定其服役边界条件。

In recent years it has been proposed to use a bare reduced activation ferritic martensitic (RAFM) steels wall as plasma-facing material (PFM) in remote regions of the first wall. To assess if bare RAFM steels can be used as PFM in the main chamber of future fusion device, the interactions of RAFM steel with the simulated boundary plasma needs to be investigated experimentally. In this project, using laboratory plasma, the interactions between the RAFM steel grades CLAM, CLF-1 and EUROFER97 with energetic plasma species shall be studied. Primary topics are the evolution of erosion, microstructure and surface morphology as a function of incident energy, ion fluence, sample temperature and the interrelated hydrogen isotope diffusion, retention, desorption. And the influence of heavy ion bombardment to simulation the damage of neutron on fuel retention and trapping will be studied. The achieved results will be compared with the published data based on other RAFM steels, such as EUROFER97 and F82H. Based on the research results, the erosion and fuel retention performance of CLAM and CLF-1 steels as first wall materials, and the service life, failure mode as well as fuel inventory will be predicted, and the boundary condition of CLAM and CLF-1 steels as first wall materials in fusion device will be defined.