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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