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- W2287202380 abstract "The vulnerability of graphite-matrix spent nuclear fuel to oxidation by the ambient atmosphere if the fuel canister is breached was evaluated. Thermochemical and kinetic data over the anticipated range of storage temperatures (200 to 400 C) were used to calculate the times required for a total carbon mass loss of 1 mgcm-2 from a fuel specimen. At 200 C, the time required to produce even this small loss is large, 900,000 yr. However, at 400 C the time required is only 1.9 yr. The rate of oxidation at 200 C is negligible, and the rate even at 400 C is so small as to be of no practical consequence. Therefore, oxidation of the spent nuclear fuel upon a loss of canister integrity is not anticipated to be a concern based upon the results of this study." @default.
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- W2287202380 date "1998-09-01" @default.
- W2287202380 modified "2023-10-16" @default.
- W2287202380 title "Graphite Oxidation Thermodynamics/Reactions" @default.
- W2287202380 doi "https://doi.org/10.2172/769038" @default.
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