Graphite Oxidation Thermodynamics/Reactions | Zendy

W.A. Propp | Zendy

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Graphite Oxidation Thermodynamics/Reactions

Author(s) -

W.A. Propp

Publication year - 1998

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/769038

Subject(s) - graphite , nuclear graphite , spent nuclear fuel , atmosphere (unit) , atmospheric temperature range , carbon fibers , chemistry , materials science , thermodynamics , radiochemistry , nuclear chemistry , metallurgy , physics , composite material , composite number

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

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