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Conference Papers Year : 2018

Thermal diffusivity measurements on UO$_2$ fuels with the flash method

Abstract

Thermal conductivity of the nuclear fuel : -A key parameter to understand the performance of the fuel under irradiation -Highly dependent on microstructure, porosity and its distribution -Influences almost all important processes such as fission gas release, swelling Knowledge of the nuclear fuel thermal conductivity (derived from a thermal diffusivity measurement): - A fundamental data for a better prediction of fuel performance in reactor - Must be measured accurately (including a reliable uncertainty assessment
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Dates and versions

cea-02338478 , version 1 (24-02-2020)

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  • HAL Id : cea-02338478 , version 1

Cite

C. Duguay, M. Soulon. Thermal diffusivity measurements on UO$_2$ fuels with the flash method. NuMat2018 - The Nuclear Materials Conference, Oct 2018, Seattle, United States. ⟨cea-02338478⟩

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