Abstract: The present invention discloses a method for the separation of radionuclides from an aqueous radioactive waste solution, the method comprising: receiving of an aqueous radioactive waste solution, adding at least one zirconium salt to the aqueous radioactive waste solution, changing the pH of the radioactive waste solution to obtain a precipitate P, and separating the precipitate P from the radioactive waste solution. The present invention also discloses the use of zirconium salts, preferably zirconium oxychloride, zirconium nitrate or a zirconium oxynitrate or any mixture thereof, for the treatment of aqueous radioactive waste solution, preferably acidic or alkaline intermediate or low level radioactive waste solution, preferably an acidic intermediate and/or low level radioactive waste solution.

Abstract: Provided herein is a process for removal of 99Tc from liquid intermediate level waste (ILW) of spent fuel reprocessing including the steps of: adding HNO3 to ILW till the pH is 2 to destroy the carbonates, transferring the ILW derived of carbonates to a tank containing mild steel wool (msw) for 4 to 48 hrs, subjecting the ILW and MS Wool to the step of separation, discharging the supernatant solution free of 99Tc and retaining the corrosion products (goethite(FeOOH/magnetite), subjecting the said corrosion products to the step of vitrification, and storing the said vitrified 99Tc bearing waste.

Abstract: Provided herein is a process for removal of 99Tc from liquid intermediate level waste (ILW) of spent fuel reprocessing including the steps of: adding HNO3 to ILW till the pH is 2 to destroy the carbonates, transferring the ILW derived of carbonates to a tank containing mild steel wool(msw) for 4 to 48 hrs, subjecting the ILW and MS Wool to the step of separation, discharging the supernatant solution free of 99Tc and retaining the corrosion products (goethite(FeOOH/magnetite), subjecting the said corrosion products to the step of vitrification, and storing the said vitrified 99Tc bearing waste.