Abstract: The recovery of 137Cs from 1AW of power reactor fuels can be easily performed by adsorption on a new complex inorganic ion exchanger (titanius phosphate-AMP), which is first synthesized in our laboratory. Elution is accomplished with 5N NH4NO3 + 0.5.NHNO3 solutions at 60℃. Several experimental conditions, such as loading and number of cycles, are examined in simulation solutions of acidic waste, using 137Cs as an indicator. Its break-through capacity (C/C0 = 0.01) is found to be 0.47 meq/g for Cs+. In the mean time the loss of 241Am is less than 1 %.A series of data of batch equilibration experiments on the uptake of 137Cs from the solutions having different ratios Na/Cs are obtained, The titanius phosphate-AMP is irradiated with 60Co source and its behavior compared with unirradiated samples. Experiments are also carried out on the decontamination factor of Ce, Ru, Zr and Nb from aqueous solutions, to which a fresh fission product solution is added.The radioactive purity of recovered 137Cs is checked by means of paper chromatography and gama spectrometry. Its radioactive purity is higher than 99%.Finally, on the basis of these experiments a scheme of recovery process is suggested.