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

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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Bibliographic Details
Main Authors: Iva Betova, Martin Bojinov, Vasil Karastoyanov
Format: Article
Language:English
Published: MDPI AG 2023-03-01
Series:Materials
Subjects:
zirconium alloy
nuclear reactor primary coolant
electrochemical impedance spectroscopy
oxidation model
compressive stress
ionic space charge
Online Access:https://www.mdpi.com/1996-1944/16/7/2577

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