| 摘要 |
<p>In a process for recovery of uranium from an irradiated nuclear reactor fuel element also containing aluminium and silicon, the fuel element is dissolved in a limited quantity of nitric acid to give a solution containing less than the stoichiometric equivalent of nitrate ions for the cations present and containing aluminium in the basic hydroxide form, and then uranyl nitrate is extracted from the solution with an organic solvent. Preferably the solution has an acid deficiency between 0.6 M and 2 M, i.e. lacks 0.6 to 2 moles of nitrate ions per litre for stoichiometric equivalence with the cations present. Examples are given.</p> |
