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Journal Articles Corrosion Science Year : 2020

Effect of a pre-oxidation on the hydrogen desorption from Zircaloy-4

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Abstract

During the transport of nuclear spent fuel, part of the tritium formed by ternary fission in core of nuclear reactors is susceptible to desorb from the oxidized cladding. This study aimed at identifying the rate-limiting step in the hydrogen desorption process from pre-oxidized Zircaloy-4 specimens. Controlled-thickness oxide scales shifted the hydrogen desorption from the alloy towards higher temperatures during a temperature ramp under vacuum. Scanning electron microscopy observations and finite elements modelling of the oxide layer dissolution led to the conclusion that, in such conditions, hydrogen desorption from the alloy was controlled by the oxide dissolution kinetics.
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Dates and versions

cea-02931992 , version 1 (06-06-2022)

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Attribution - NonCommercial - CC BY 4.0

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Clara Juillet, Marc Tupin, Frantz Martin, Quentin Auzoux, Sophie Bosonnet, et al.. Effect of a pre-oxidation on the hydrogen desorption from Zircaloy-4. Corrosion Science, 2020, 173, pp.108762. ⟨10.1016/j.corsci.2020.108762⟩. ⟨cea-02931992⟩
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