PENGOLAHAN LIMBAH DAUR BAHAN BAKAR NUKLIR YANG MENGANDUNG URANIUM MENGGUNAKAN RESIN PENUKAR ANION

ABSTRACT TREATMENT OF FUEL CYCLE WASTE CONTAINING URANIUM BY USING ANION EXCHANGE RESIN. There are several stages in the nuclear fuel cycle, all of which could potentially give rising various types of radioactive waste. One type of radioactive waste is waste containing uranium that contaminated with amount of fission product. This waste can be generated from the reprocessing of spent nuclear fuel. The principle of treatment this type of waste is to separating of uranium from the fission product. Anion resin would selectively bind the uranium in the form of complex uranium. A simulation study of waste treatment with the uranium concentration of 0.05 g / l has been carried out using anion exchange resin amberlite IRA- 400Cl by complexing the uranium with Na2CO3 and H2SO4 complexing agent respectively. The parameters of waste treatment studied are the amount of complexing agent of Na2CO3 and H2SO4 and contact time for uranium sorption. The optimal sorption of uranium obtained in the addition of Na2CO3. is 0.75 gram or ratio U / Na2CO3 ≈ 0.067, contact time of 60 minute with the uranium sorption of 88.621 %. weight. While the optimal sorption of uranium obtained in the addition of H2SO4 is 0,5 gram ratio U / H2SO4 ≈ 0.1; contact time of 60 minute with the uranium sorption of 70,468 %. weight. In the treatment of waste containing uranium, the use of Na2CO3 as complexing agent would be more economical than the H2SO4 on on the processing of waste containing uranium using anion exchange resin. Keywords: Uuranium waste, anion exchange resin, Na2CO3 complexing agent, H2SO4 complexing agent