Recovery of Uranium(VI) from Sulfate Leach Liquor using Modified Duolite

Silicate mercapto Duolite composite (SMDC) and activated Duolite A 101 D (AD) were prepared, characterized, and tested for uranium removal from sulfate solution using batch experiment technique. The capability of newly adsorbents for sorption of uranium was estimated and optimized under different controlling variables, including the impact of uranium initial concentration, pH of the medium, equilibrium time, temperatures, dose and interfering ions. Testing of different adsorbents for adsorption isotherms revealed that the achieved experimental data were fitting well with the Langmuir isotherm model with 68.02 mg center dot g(-1) and 208.33 mg center dot g(-1) as theoretical capacity for AD and SMDC, respectively. Thermodynamic parameters have been resulted in negative values for Delta H and Delta S indicating an exothermic and decreased randomness behavior for uranium(VI) adsorption, while negative values of Delta G indicate spontaneous uranium adsorption. The kinetics studies showed that the adsorption process was controlled expressed by pseudo-second order model. Finally, the optimized factors have been applied for uranium(VI) recovery from Gattar leach liquor producing a uranium concentrate (Na2U2O7) with uranium concentration of 70 % and purity of 93.33 %.