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Property measurements and inner state estimation of simulated fuel debris

模擬燃料デブリの物性測定と内部状態評価

廣岡 瞬 ; 加藤 正人   ; 森本 恭一 ; 鷲谷 忠博 

Hirooka, Shun; Kato, Masato; Morimoto, Kyoichi; Washiya, Tadahiro

福島第一原子力発電所におけるシビアアクシデント以来、炉心から溶融燃料を取り出すための技術開発が行われているが、炉心へのアクセス、燃料デブリの切断、臨界安全管理、フィッサイルの推定、取り出し後の保管等の課題が残っている。本研究では、模擬燃料デブリを用いた解析から燃料デブリの物性を評価し、温度分布や密度分布のような事故後経時変化するデブリの内部状況の推定を行った。融点,熱伝導率,熱膨張等の物性は、UO$$_2$$及びジルカロイから製作した模擬デブリによって取得した。

Since the severe accident at Fukushima Daiichi Nuclear Power Station, technologies to remove fuel debris from the damaged core have been developed. However, many subjects such as how to access to the core, cut the fuel debris, control criticality safety, estimate fissile materials, store removed debris and so on are still in existence. Purpose of this work is to evaluate the fuel debris properties by using analysis of simulated fuel debris and to estimate the inner state such as temperature profile and density profile which depend on elapsed time after the accident. The reported properties such as melting temperature, thermal conductivity and thermal expansion were obtained by the simulated fuel debris manufactured from UO$$_2$$ and zircaloy.

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