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Report No.

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

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

Simulated in-vessel and ex-vessel corium debris, fabricated in the Colima experimental facility set up in the Severe Accident 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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