[en] Surface modification and hydrogen retention of a LHD divertor tile used for plasma experiments for 6 years were analyzed by using ion beam analytical techniques. Several divertor footprints were identified on the central area of the tile surface. This area is an so called erosion dominant area. While, on the both sides of the central area, surfaces were covered mainly with Fe and Ti, respectively. The amounts of hydrogen retention were strongly dependent on the chemical composition of the surface. In the Ti rich deposition layer appeared in the private side, very strong hydrogen trapping was detected. In contrast, Fe rich area in the opposite side, the retention was much lower than that of the normal carbon surfaces. (author)