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Radioactive molten salt waste, which would be generated from electro-metallurgical process for recovering transuranic elements in spent nuclear fuel, mainly consists of metal chorildes with the high content of alkali elements(90wt% LiCl, 10wt% fission product and a minor quantity of actinide oxides). Our research group suggested a new method named as “Gel-Route Stabilization/Solidification”(GRSS) for the final disposal of various radioactive wastes and applied it to the molten salt waste. The applied gel-forming material system(SiO2-Na2O-Al2O3-P2O5) was dissolved in water and mixed with a simulated waste solution. The mixture solution was gelled after 4 hr at 70oC and its dried product was heat-treated with a glass powder at 900oC and 1050oC. During the heat-treatment, there would be little possibility on the volatilization of Cs from the thermogravimetric analysis and elemental analysis. The PCT leaching results of solidified wastes prepared by GRSS method has shown higher leach-resistance of radionuclides than glass-bonded zeolite by ANL method. From the experimental results, it would be concluded that the GRSS method can make the volatile molten salt waste be directly applied to the vitrification process by eliminating the volatilization of Cs. The GRSS method could be considered as an effective approach to the fabrication of radioactive waste form for the final disposal of molten salt waste.