Zirconium in the Nuclear Industry: 18th International Symposium 2018
DOI: 10.1520/stp159720160033
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Investigation and Modeling of the Degradation of Zirconium-Based Fuel Cladding during Corrosion in Steam and Air-Steam Mixtures at High Temperatures

Abstract: This paper presents the main results of a study conducted to quantify and to model the degradation state of Zr-based fuel claddings submitted to severe accident conditions in a nuclear reactor core: high temperatures and either pure steam or air-steam mixture. Due to the progressive thickening of a dense and protective ZrO2 layer, the oxidation kinetics of Zr-based claddings in steam at high temperatures typical of nuclear severe accidents, is generally cubic or parabolic. However, for some temperature domains… Show more

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