It is important to evaluate the influence of re-deposited tungsten formed on plasma facing wall on tritium retention in the vessel of a fusion reactor from a viewpoint of safety.In this work,deposited tungsten samples with different thickness and porosities produced by the sputtering method on polycrystalline tungsten substrates were used to simulate the re-deposited tungsten,and retention behavior of hydrogen isotopes were investigated after the exposure to plasma in Experimental Advanced Superconductive Tokamak(EAST).