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Uranium crystallization for dissolver solution of irradiated FBR MOX fuel

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矢野 公彦 ; 柴田 淳広 ; 野村 和則 ; 小泉 務; 小山 智造

Yano, Kimihiko; Shibata, Atsuhiro; Nomura, Kazunori; Koizumi, Tsutomu; Koyama, Tomozo

先進湿式再処理の一部として開発されているウラン晶析工程は使用済燃料溶解液から大部分のウランを硝酸ウラニル結晶として分離回収する技術である。結晶の大きさに対する冷却速度の影響やプルトニウム(IV)と比較した核分裂生成物の挙動を調べるため、使用済燃料の実溶解液を用いたウラン晶析試験を実施した。冷却速度が早いほうが大きな結晶が得られたが大きな結晶が必ずしも除染性能がよいとは限らないという結果が得られた。また、核分裂生成物の挙動について今回の試験では、ユーロピウムはプルトニウム(IV)とよく似た挙動となることが示されたが、セシウムはウランに同伴して結晶中へ移行した。

The uranium crystallization process has been developed as part of advanced aqueous reprocessing system. In the process, the great part of uranium is separated from the dissolver solution by crystallization as uranyl nitrate hydrate. The uranium crystallization test was carried out with the dissolver solution of irradiated FBR MOX fuel to investigate the influence of cooling rate on the crystal size and the behavior of fission products compared with that of tetravalent plutonium with the real dissolver solution. In regard to the influence of the cooling rate, it was obvious that the crystal size was smaller as the cooling ratio was faster. However, it was suggested that a large crystal produced by crystallization was always not high purity. Concerning the behavior of fission products, europium behaved similarly to tetravalent plutonium. Cesium accompanied with uranium into the crystals under the condition of this test.

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