10:00 AM - 10:15 AM
[2B03] The effect of deuterium plasma implantation on deuterium retention behavior for heavy ion implanted W.
Keywords:Tungsten, Plasma implantation, Heavy ion implantation, Deuterium retention behavior
Tungsten (W) is considered to be a candidate for plasma facing materials (PFMs) in fusion reactor. It will be exposed to energetic neutron escaped from plasma during the plasma operation. In that time, implantation defects which trap hydrogen isotope, will be introduced. In our previous study, D retention behavior in damaged W by iron ion implantation to simulate the implantation defect was estimated by D2+ implantation. In the actual fusion reactor, W will be exposed to low energy and high flux hydrogen plasma. Therefore, hydrogen isotope retention behavior in plasma irradiated W is expected to be quite different from that of ion implanted W. In this study, D retention behavior for Fe2+ damaged W with D plasma was compared to that with D2+ ion implantation. From this experiment, it was suggested that D was trapped by the defect in order from surface to bulk in comparison to D2+ ion implanted W. The HIDT simulation is applied to estimate of trapping energy of hydrogen isotopes in damaged W and D plasma irradiation effect will be discussed.