Long-Term Oxidation of Zirconium Alloy in Simulated Nuclear Reactor Primary Coolant—Experiments and Modeling

Oxidation of Zr-1%Nb fuel cladding alloy in simulated primary coolant of a pressurized water nuclear reactor is followed by in-situ electrochemical impedance spectroscopy. In-depth composition and thickness of the oxide are estimated by ex-situ analytical techniques. A kinetic model of the oxidation...

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Detalles Bibliográficos
Autores principales: Betova, Iva, Bojinov, Martin, Karastoyanov, Vasil
Formato: Online Artículo Texto
Lenguaje:English
Publicado: MDPI 2023
Materias:
Article
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC10094926/
https://www.ncbi.nlm.nih.gov/pubmed/37048870
http://dx.doi.org/10.3390/ma16072577

Internet

https://www.ncbi.nlm.nih.gov/pmc/articles/PMC10094926/
https://www.ncbi.nlm.nih.gov/pubmed/37048870
http://dx.doi.org/10.3390/ma16072577

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