Uranium Anodic Dissolution under Slightly Alkaline Conditions
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Abstract
Argonne National Laboratory is developing an alternative method for digesting irradiated low enriched uranium foil targets to produce 99Mo in neutral/alkaline media. This method involves the electrolytic dissolution of irradiated uranium foil in sodium bicarbonate solution, followed by the precipitation of carbonate, base-insoluble fission and activation products, and uranyl species with CaO. The addition of CaO is vital for the effective anion exchange separation of 99MoO42- from the fission products, since most of the interfering anions (e.g., CO32-) are removed from the solution while the molybdate remains in it. An anion exchange is used to retain and purify the 99Mo from the filtrate. The electrochemical dissolver has been designed and will be tested with low-burnup depleted uranium foil at Argonne and later with high-burnup targets at Oak Ridge National Laboratory.
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