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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

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https://hal-mines-paristech.archives-ouvertes.fr/hal-02460935
Contributor : Laurent de Windt <>
Submitted on : Thursday, January 30, 2020 - 1:06:10 PM
Last modification on : Thursday, September 24, 2020 - 4:34:27 PM

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A. Nakayoshi, C. Jegou, Laurent de Windt, S. Perrin, T. Washiya. Leaching behavior of prototypical corium samples: A step to understand the interactions between the fuel debris and water at the Fukushima Daiichi reactors. Nuclear Engineering and Design, Elsevier, 2020, 360, pp.110522. ⟨10.1016/j.nucengdes.2020.110522⟩. ⟨hal-02460935⟩

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