Leaching behavior of prototypical corium samples: A step to understand the interactions between the fuel debris and water at the Fukushima Daiichi reactors - Mines Paris Accéder directement au contenu
Article Dans Une Revue Nuclear Engineering and Design Année : 2020

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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Géochimie

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hal-02460935 , version 1 (30-01-2020)

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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, 2020, 360, pp.110522. ⟨10.1016/j.nucengdes.2020.110522⟩. ⟨hal-02460935⟩
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