Complex formation and Solvent used in Separation of uranium
Complex formation constants of UO2
| No | Reaction | Equilibrium |
| 1 | UO2 2+ + NO3 - | 0.5 |
| 2. | UO2 2+ +Cl - → UO2 Cl+ | 0.8 |
| 3. | UO2 2+ + HF → UO2 F + | 27 |
| 4. | UO2 2+ + SO4 2- → UO2 SO4 | 50 |
| 5. | UO2 2+ + 2 SO4 2- → UO2 SO4 2- | 350 |
| 6. | UO2 2+ + 3 SO4 2- → UO2 SO4 4- | 2500 |
| 7. | UO2 2+ + 2CO3 2- → UO2CO3 2- | 4x10 14 |
| 8. | UO2 2+ + 3 CO3 2- → UO2CO34- | 2x10 18 |
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Solvent used in separation of uranium by solvent extraction
| No. | Solvent | Formula | Application |
| 1. | Diethyl Ether | (C2H5)2O | Uranium purification |
| 2. | Methyl isobuthyl ketone | CH3(CO)C4H9 | Irradiated fuel |
| 3. | Dibuthyl Ether/Diethylene glycol | (C4H9OC2H4)2O | Irradiated fuel |
| 4. | Tri glycol dichloride | (ClC2H4O)2C2H4 | Irradiated fuel |
| 5. | Tri buthyl phospate | (C4H9)3PO4 | Uranium purification |
| 6. | Di(2 Ethyl hexyl) phosphoric acid | (C8H17O)PO(OH) | Extract U from leach liquors |
| 7. | Tri Octhylamine | (C8H17)N | Extract U from leach liquors |
Literature
Benedict M, Pigford TH, Levi HW, “Nuclear Chemical Engineering”, second Edition
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