Experimental evidence of oxygen thermo-migration in PWR UO2 fuels during power ramps using in-situ oxido-reduction indicators
Author:
Funder
AREVA NP
EDF
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference27 articles.
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2. Simulations of coupled heat transport, oxygen diffusion, and thermal expansion in UO2 nuclear fuel elements
3. Thèse de l’Université d’Aix-Marseille (Ecole doctorale 352-Physique et Sciences de la Matière), France;Baurens,2014
4. 3D thermo-chemical–mechanical simulation of power ramps with ALCYONE fuel code
5. Oxygen potential in the rim region of high burnup UO2 fuel
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4. First evidence of metallisation circle in a Chromium doped UO2 pellet submitted to a thermal gradient;Journal of Nuclear Materials;2024-08
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