Physical erosion studies of plain and lithiated graphite

摘要: Abstract It has been observed that a thin lithium film evaporated on graphite wall tiles in tokamak fusion devices acts to improve plasma conditions. The present focus is measure the physical erosion rate of various conditions lithiated under deuterium ion bombardment help understand this effect. Sputter yields untreated ATJ-graphite, pure lithium, and lithium-on-ATJ-graphite have measured for 150, 300, 600 1500 nm at an energy 500 eV/ion, 45° incidence, sample temperatures 25 200 °C by using QCM collect sputtered material. were around 0.06 C-atoms/ion, while 0.10 Li-atoms/ion. However, combined lithium-on-carbon sputtering appeared notably lower than individual materials. TOF–SIMS analysis was used estimate relative Li/C levels collected material, as well look concentration versus depth intercalated graphite.