Abstract
The possibility that spent fuel from commercial light-water reactors (LWRs) may be stored for extended periods before reprocessing or permanant disposal has led to interest to its oxidation behavior in air. Oxidation weight gain tests at 150 to 250°C indicate that spent LWR fuel oxidizes 10 to 100 times more rapidly than unirradiated UO2, but is much slower to break up into U3O8 powder. To gain insight into the mechanisms that control oxidation in spent fuel, pre- and post oxidation samples were examined by transmission electron microscopy.
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Schedule a callMore From: Proceedings, annual meeting, Electron Microscopy Society of America
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