Nuclear reaction analysis was used to investigate the retention of deuterium (D at radiation damage in new graphites USE-15, PGI, RG-Ti-91, RG-Ti-91 with 0.5 wt%B made in Russia and in POCO AXF-5Q graphite. Samples were irradiated with C + ions to produce damage up to doses of ∼ 10 displacements per atom (dpa), and then soaked in deuterium gas at 1473 K. The concentration of D in the damaged region increased with damage and saturated for damage levels above about 1 dpa. At saturation the smallest D concentration was found in USB-15 (∼60 appm), and the largest D concentration was found in RG-Ti-91 (∼1500 appm). Based on microstructural investigations done by TEM, an attempt was made to relate differences in concentrations of retained D to variations in radiation-induced trap concentration and to kinetic limitations for D atom access to traps available. The effect of boron on D trapping in graphite was also examined.