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面向等离子体的结构材料及其辐照性能研究是和平利用聚变能中的一个重要课题。混合堆第一壁材料除受到聚变中子的辐照,还会被逃逸出等离子体的离子轰击,所以材料除辐照肿胀外,还面临表面起泡、剥落等问题。这种情况一旦发生,将严重污染等离子体。我们在去年工作的基础上,利用1.8MeV、1.5MeV、1.0MeV的α粒子辐照316L不锈钢,以期得到起泡与辐照离子能量和剂量的关系,研究材料起泡的物理机制和孕育、发展过程。
Plasma-oriented structural materials and their irradiation performance studies are an important issue in the peaceful use of fusion energy. In addition to being irradiated by fusion neutrons, the material of the first wall of the hybrid stack is also bombarded by ions of the plasma. Therefore, the material faces problems of surface foaming and peeling, in addition to irradiation and swelling. If this happens, it will pollute the plasma severely. Based on the work of last year, we used the α particles of 1.8MeV, 1.5MeV and 1.0MeV to irradiate 316L stainless steel, in order to get the relationship between the energy of foaming and irradiation ion energy and dose, and to study the physical mechanism of foam foaming and its development process.