Abstract
The oxidative decladding of UO/sub 2/ fuels was demonstrated on three- foot sections of unirradiated fuel rods and on eight-inch sections of fuel rods irradiated to 21,000 Mwd/ MTU. Decladding rates were unaffected by the extent of irradiation. Uranium dioxide that was unirradiated, irradiated, and with fissia added to simulate 100,000 Mwd/ MTU irradiation was declad at similar rates. The effect of pressure and temperature on decladding rates was determined. Puncturing the cladding greatly enhanced the rate and gave a coarser product. This product was not completely converted to U/sub 3/O/sub 8/ during oxidative decladding. Greater than 99.9% of the UO/sub 2/ fuel was removed from the cladding. There was no detectable contamination of the product by the cladding material. Little or no fissionproduct or plutonium decontamination was observed. Dissolution rates for the declad product, in 50% nitric acid, were 20 times as fast as for the as received'' UO/sub 2/ fuel. (auth)
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