FOM Institute DIFFER-Dutch Institute for Fundamental Energy Research, Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, NL-3439 MN Nieuwegein, Netherlands.
Max-Planck-Institut für Plasmaphysik, Boltzmannstraße 2, D-85748 Garching, Germany.
Phys Rev Lett. 2013 Nov 27;111(22):225001. doi: 10.1103/PhysRevLett.111.225001.
Radiation-damaged tungsten is exposed to high-flux, low-energy deuterium plasmas at self-bias conditions. We observe that the fraction of deuterium that penetrates is only 10(-5)-10(-7) of the plasma flux and strongly dependent on the local surface temperature. We propose that deuterium does not directly penetrate bulk tungsten but that it thermalizes at the surface, where it forms a protective chemisorbed layer. We find an energy barrier of 1-2 eV between the surface and bulk, causing the influx of deuterium to be low as compared to the number of defects and leading to slow filling of the damaged layer.
辐射损伤的钨在自偏压条件下暴露于高通量、低能氘等离子体中。我们观察到,穿透的氘的分数仅为等离子体通量的 10(-5)-10(-7),并且强烈依赖于局部表面温度。我们提出氘不会直接穿透体钨,而是在表面热化,在那里形成保护性化学吸附层。我们发现表面和体相之间存在 1-2 eV 的能量势垒,导致氘的流入量相对于缺陷数量较低,从而导致损伤层的填充缓慢。