In order to investigate how fuel (H+D) retention increases with discharge time, we have measured long term H+D retention of the carbon tiles exposed to plasmas in JT-60U by TDS and SEM. The H+D retention in the re-deposited carbon layers on divertor tiles linearly increases with the thickness of the re-deposited layers with a constant hydrogen concentration of (H+D)/C∼0.013. The C-deposition and H+D retention rates are in the order of ∼1×10 20 C/m 2 /s and ∼3.8×10 18 H+D atoms/m 2 /s, respectively. The H+D retentions in the near surface regions of eroded tiles both at outer divertor and outer first wall did not go over 5×10 22 H+D atoms/m 2 , suggesting hydrogen saturation at the near surface regions. However, in a little deeper region of the outer first wall tiles, direct implantation of energetic D originated from Neutral Beam Injection (NBI) caused gradual increase of the retention until saturation in the implanted depth.