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PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II

机译:从石墨基燃料元件中回收铀和钍的工艺。第二部分

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Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO3 process, which involves simultaneous disintegration and leaching in 21 M HNO3, is applicable to all fuel elements which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranium recovered ~99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphite residue retained >50$ of the long-lived fission products. Three successive leaches of fuel containing uranium and thorium recovered ~99% of both elements. Uranium recoveries by combustion in oxygen followed by dissolution of the ash in nitric acid or fluoride-catalyzed nitric acid are quantitative only when the fuel is not coated, does not contain A2O3-coated fuel particles, and is free from impurities such as iron.

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