[en] From the view point of tritium safety in fusion reactors, it is important to understand effect of implantation conditions, such as temperature and energy, on chemical behavior of tritium implanted into plasma facing materials. Graphite will be employed as a material for divertor in ITER, of which temperature will be kept at approximately 700 K during operation. Therefore, it is important to understand temperature dependence on retention behavior of tritium implanted into graphite. In the present study, dynamics of deuterium implanted into graphite in various temperatures was studied, using the techniques of Thermal Desorption Spectroscopy (TDS) and X-ray Photoelectron Spectroscopy (XPS). A highly oriented pyrolytic graphite (HOPG) crystal purchased from Pechiney Co. Ltd. was used as a sample. Before deuterium ion implantation, the sample was preheated at ∼1400 K for 10 min in ultra high vacuum. Deuterium ion was implanted into HOPG with an energy of 1.0 keV D²⁺, a flux of 1.0 x 10¹⁸ D⁺ m^-2 s^-1, and a fluence of 6.4 x 10²¹ D⁺ m^-2 at various temperatures ranging from 173 to 773 K. The deuterium desorption behavior was evaluated by TDS with the heating rate of 0.5 K s^-1 up to 1400 K to investigate implantation temperature dependence of deuterium retention. It was found that deuterium implanted into HOPG was trapped in two chemical states: one is deuterium bound to carbon whose desorption temperature corresponded to approximately 900 K and the other is that remained in carbon vacancy whose temperature was at approximately 1000 K. It was also found that the decrease of deuterium retention up to around 700 K was mainly due to the recovery of carbon vacancy and the decrease of deuterium retention above 700 K was due to the detrapping from carbon and the recovery of carbon vacancy. Comparing to the deuterium retention after deuterium ion implantation at each temperature, the deuterium retention in HOPG decreased as the implantation temperature increased. The deuterium retention at 700 K was reached less than 20% compared to that at R.T. These results suggest that tritium trapped by carbon wouldn't release in ITER operation condition of approximately 700 K. In the presentation, retention behavior of deuterium implanted into graphite will be discussed more in detail by combination of TDS and XPS results. (author)