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SummaryThe Hanford Spent Nuclear Fuel Project focuses its efforts on determining how to safely move the degraded N-Reactor spent fuel from water-stored basins to a dry storage facility. As part of this effort, the project initiated experimental studies to address issues relating to the chemical reactivity of the degraded/corroded metallic uranium material. The studies generated a limited set of data on chemical reaction rates of the N-Reactor spent fuel in dry-air, moist-air, and moist-inert atmospheres for comparison with published data on unirradiated/irradiated metallic uranium. Based on the laboratory data, the project chose to use a conservative enhancement factor in analyzing the oxidation behavior of the spent metallic fuel. However, there is a need for the project to increase the fuel throughput for the drying-treatment process by implementing certain design optimization steps. The study discussed in this paper re-evaluated the previous laboratory data in conjunction with the cold vacuum drying (CVD) process experience and determined whether the built-in level of conservatism could accommodate the potential changes in the process without compromising public and worker safety.Evaluations based on laboratory data on samples taken from the corroded N-Reactor spent fuel showed no reactivity enhancement for the degraded metallic uranium in moist atmospheres. The established oxidation reaction-rate constant was used to accurately determine the reactive surface areas of corroded N-Reactor fuel elements. The surface areas calculated for six different N-Reactor elements that were stored in the K-West Basin and shipped to Pacific Northwest National Laboratory for drying studies ranges from as low as 0.0018 m 2 for a broken element to 8.1 m 2 for a highly corroded spent nuclear fuel (SNF) element 5744U based on the measured reaction-rate constant for the K-Basin SNF (k SNF ). On the other hand, if the literature-averaged rate constant (k Lit ) is used, the calculated areas are between 0.0002 and 1.1 m 2 .