作者: Owais Ahmed Waseem , Kevin Benjamin Woller
DOI: 10.1016/J.MATCHEMPHYS.2020.123883
关键词: Surface roughness 、 Alloy 、 Composite material 、 Ion beam 、 Nanoindentation 、 Microstructure 、 Irradiation 、 Dislocation 、 Ion implantation 、 Materials science
摘要: Abstract A depth marker by ion implantation has been used for analysis of erosion on plasma-facing materials in fusion experiments. To assess the impact surface properties these under investigation, Titanium–Zirconium–Molybdenum (TZM) alloy was irradiated with 4.8 MeV F3+ ions up to 1.04 × 1017 cm−2 at 330 °C, achieving a centroid at ~1.5 μm. After implantation, there is no significant change microstructure and roughness conditions, which were samples positioned high field side Experimental Advanced Superconducting Tokamak (EAST) device analysis. Nanoindentation measurements indicate an increase hardness from ~5.5 GPa ~6.6 GPa first 300 nm surface, within eroded zone over full years experimental campaign. Within 1.5 μm where damage beam expected be generated, implanted TZM shows large number dislocation lines (i.e. 1.0 × 109 dislocations/mm2), determined TEM analysis, can account TZM. These changes due though minor, should considered when using markers materials.