| 摘要 |
<p>Uranium hexafluoride is recovered from spent aluminium-containing nuclear fuel by dissolving the fuel at a temperature not above 600 DEG C. in a molten salt solvent of substantially 67 KF-21ZrF4-12 AlF3 mol. per cent while passing anhydrous HF through the melt, and when the AlF3 content reaches 32 mol. per cent, removing the uranium as volatile UF6 by passing fluorine gas through the melt at about 600 DEG C. A portion of the melt is discarded and the mol. per cent composition is restored to its original value by adding KF and 2KF.ZrF4 salts. The process may then be repeated. UF6 vapour may be cooled to 100 DEG C., adsorbed on a bed of NaF, and further purified from fission products by heating the bed to 400 DEG C. and condensing volatilized UF6.</p> |
