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Leaching behavior of prototypical Corium samples; A Step to understand the interactions between the fuel debris and water at the Fukushima Daiichi reactors

原型的なコリウムの溶出挙動; 福島第一原子力発電所のデブリと水の反応の理解のステップ

仲吉 彬; Jegou, C.*; De Windt, L.*; Perrin, S.*; 鷲谷 忠博

Nakayoshi, Akira; Jegou, C.*; De Windt, L.*; Perrin, S.*; Washiya, Tadahiro

Simulated in-vessel and ex-vessel fuel debris, fabricated in the Colima experimental facility set up in the PLINIUS platform at CEA Cadarache, were selected and leaching experiments were carried out under oxidizing conditions. In parallel, geochemical modeling was performed to better understand the experimental concentrations, pH evolutions and secondary phase's formation. Finally, the Fractional Release Rates of the (U, Zr)O$$_{2}$$ matrix for the two kinds of samples (in-vessel and ex-vessel) were found to be close to or one order of magnitude lower than that of SF under oxidizing conditions (from 10$$^{-6}$$ to 10$$^{-7}$$ per day), but the release processes are different.

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パーセンタイル:100

分野:Nuclear Science & Technology

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