報告書番号

N04033

タイトル（和文）

コンクリートキャスク用低放射化・高性能材料の開発

タイトル（英文）

Development of High Performance and Low Radio Activation Concrete Material for Concrete Cask

概要 （図表や脚注は「報告書全文」に掲載しております）

使用済燃料のコンクリートキャスクによる長期的な貯蔵において、耐久性や耐熱性に富み、EuとCoの含有量の小さい低放射化高性能コンクリート材料の開発を行った。まず、放射化計算により、クリアランスレベルを満足する材料中のEuとCo含有量の許容存在範囲を明らかにした。次に、各種候補材料の放射化分析を行い、粗骨材に石灰石，細骨材にアルミナ骨材，流度調整材にフライアッシュを用いる配合を候補材料とした。さらに、これら材料の施工性、高温強度、熱伝導性を確認すると共に、円筒試験体を用いた温度ひび割れ試験を実施し，耐熱性や耐久性の観点から有望であることを示した。

概要 （英文）

For the realization of the long-term storage of the nuclear spent fuel with the concrete cask technology, a low radio activation high performance concrete was developed, which contains extremely small quantity of Eu and Co and assures enough heat-resistance and durability for degradation. Firstly, the activation analysis was performed to estimate the allowable content limit of their quantities according to the rules issued by Japanese government for determining the classification of the radioactive waste. Secondly, various candidate materials were sampled and irradiated to find out the activation level. As a result, as the optimum concrete mix, the combination of limestone and white fused alumina aggregates with fry-ash was chosen. Moreover, the basic characteristics of the candidate concrete (workability, strength under high temperature, heat conductivity and so on) were evaluated, and the thermal cracking test was executed with hollow cylinders. Finally, the developed concrete material seems to be suitable for the long-term use of concrete cask considering the low activation, high heat resistance and durability during storage.

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