Interaction of Liquid CsIO<sub>3</sub> with a Polycrystalline UO<sub>2</sub> Solid Surface

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  • ISHII Hiroto
    Graduate School of Engineering, Osaka University
  • OHISHI Yuji
    Graduate School of Engineering, Osaka University
  • MUTA Hiroaki
    Graduate School of Engineering, Osaka University
  • UNO Masayoshi
    Research Institute of Nuclear Engineering, University of Fukui
  • KUROSAKI Ken
    Research Institute of Nuclear Engineering, University of Fukui Institute for Integrated Radiation and Nuclear Science, Kyoto University

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Other Title
  • 液体CsIO<sub>3</sub>のUO<sub>2</sub>多結晶固体表面との相互作用
  • 液体CsIO₃のUO₂多結晶固体表面との相互作用
  • エキタイ CsIO ₃ ノ UO ₂ タケッショウ コタイ ヒョウメン ト ノ ソウゴ サヨウ

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<p>　Understanding the behavior of melted volatile fission products (FPs) on the fuel contributes to the precise assessment of the release behaviour during a severe nuclear accident. A previous study revealed that liquid CsI shows abnormally high wettability with measured contact angles of almost zero degrees against the polycrystalline UO2 solid surface. [K. Kurosaki et al., Sci. Rep. 7, Article number: 11449 (2017).]. In this study, we focus on the melting behavior of CsIO3 and revealed that liquid CsIO3 also shows high wettability on the polycrystalline UO2 solid surface. However, after melting, CsIO3 decomposed and only Cs reacted with the polycrystalline UO2 solid surface and I was only absorbed on the solid surface. When the CsI had melted on the polycrystalline UO2 solid surface, both Cs and I were able to penetrate inside the UO2 pellets. In short, when Cs and I exist as CsIO3, Cs and I will be separately released during severe accidents. These findings suggest that the release mechanisms of Cs and I could be strongly affected by the chemical species in the irradiated fuels.</p>

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