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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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https://hal-cea.archives-ouvertes.fr/cea-02338478
Contributor : Bibliothèque Cadarache <>
Submitted on : Monday, February 24, 2020 - 2:55:36 PM
Last modification on : Tuesday, April 28, 2020 - 11:28:14 AM
Long-term archiving on: : Monday, May 25, 2020 - 6:20:10 PM

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  • HAL Id : cea-02338478, version 1

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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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