Phase-field modeling with the TAF-ID of incipient melting and oxygen transport in nuclear fuel during power transients
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
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1. Modeling oxygen transport in Cr doped UO2 fuel with the TAF-ID during power transients;Journal of Nuclear Materials;2025-01
2. ALCYONE: the fuel performance code of the PLEIADES platform dedicated to PWR fuel rods behavior;Annals of Nuclear Energy;2024-11
3. First evidence of metallisation circle in a Chromium doped UO2 pellet submitted to a thermal gradient;Journal of Nuclear Materials;2024-08
4. Presentation of the xM3 Test Case of the P2M Simulation Exercise and Modeling with the Fuel Performance Code ALCYONE;Nuclear Technology;2023-10-10
5. A fully coupled Hydraulic Mechanical Chemical approach applied to cementitious material damage due to carbonation;npj Materials Degradation;2023-07-27
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