Thermal diffusivity measurements on UO$_2$ fuels with the flash method - Archive ouverte HAL Access content directly
Conference Papers Year : 2018

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

(1) , (1)
1

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
Fichier principal
Vignette du fichier
201800003466.pdf (447.66 Ko) Télécharger le fichier
Origin : Files produced by the author(s)

Dates and versions

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

Identifiers

  • 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⟩

Collections

CEA DEN
14 View
8 Download

Share

Gmail Facebook Twitter LinkedIn More