“…We have been studying the retention of hydrogen isotopes (H, D, T) in plasma facing graphite tiles used in the W-shaped divertor of JT-60U with the inner side pumping system [3,[5][6][7][8][9] and with the dual side pumping system [10][11][12]. We found that most of the tritium produced by D-D reactions was implanted into graphite tiles in the micrometer depth range, while hydrogen and deuterium were retained in the near surface region and the retention was influenced by the carbon deposition as well as the surface temperature of the tiles.…”