ANALISIS ISOTOP 137Cs DALAM PEB U3Si2/Al DENSITAS 4,8 gU/cm3 PASCA IRADIASI DENGAN METODE PENGENDAPAN CHLOROPLATINATE DAN KOLOM PENUKAR KATION RESIN DOWEX

Abstract

SEPARATION OF CESIUM IN IRRADIATED U3Si2/Al FUEL PLATE WITH A DENSITY OF 4.8 gU/cm3 USING CHLOROPLATINATE DEPOSITION METHOD AND DOWEX RESIN CATION EXCHANGE COLUMN. Dissolution of the U₃Si₂/Al plate was carried out in hot cell 109 using 6 M HCl and 6 M HNO3 solutions. The separation of cesium and uranium in uranyl nitrate solution was carried out using chloroplatinate deposition method and a cation exchange column. In the chloroplatinate deposition, the process of removing elements that will interfere with the deposition process was performed first, then the separation of heavy elements such as uranium or plutonium was carried out by depositing the ¹³⁷Cs in the form of Cs₂PtCl₆. The isotope content of 137Cs in the Cs2PtCl6 deposition was measured with a γ spectrometer. In the Dowex resin cation exchange column method, the uranyl nitrate solution was pipetted 150 μL to be added to 2 mL of aquadest. To this solution was then added 20 μL of Cs carrier and 1 mL of 12 M HCl. The mixture of the solution was used as feed and put into the anion exchange column containing R-Cl resin. The effluent exiting the anion exchange column was fed into the cation exchange column containing R- NH4+ resin. The ¹³⁷Cs isotope bound to R NH4+ resin in the column was then eluted using 1 M HCI. The effluent was compressed until a volume of ± 2 mL was obtained. The isotope content of ¹³⁷Cs in U₃Si2 / Al plate obtained as a result of separation using the chloroplatinate method for middle slices coded M has an average of 0.000557 g/g fuel and 0.000652 g/g fuel for the bottom slices coded B, while the Dowex resin cation exchange column method gave an average of 0.000747 g/g fuel for middle slices coded M, and 0.000934 g/g fuel for bottom slices coded B. The recovery of ¹³⁷Cs separation by the anion exchange column method was greater than that of the Cs₂PtCl₆ deposition method.