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

Authors :
Duguay, C.
Soulon, M.
CADARACHE, Bibliothèque
CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN))
Commissariat à l'énergie atomique et aux énergies alternatives (CEA)
Source :
NuMat2018-The Nuclear Materials Conference, NuMat2018-The Nuclear Materials Conference, Oct 2018, Seattle, United States
Publication Year :
2018
Publisher :
HAL CCSD, 2018.

Abstract

International audience; 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, swellingKnowledge 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

Details

Language :
English
Database :
OpenAIRE
Journal :
NuMat2018-The Nuclear Materials Conference, NuMat2018-The Nuclear Materials Conference, Oct 2018, Seattle, United States
Accession number :
edsair.dedup.wf.001..16f39c623b31be0bb65cdb216de230cc