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Radioactive nuclides recovery from spent solvent in STRAD project, 1; Zr recovered by alkaline solutions

STRADプロジェクトにおける使用済廃溶媒からの放射性核種回収,1; アルカリ溶液によるZr回収

荒井 陽一; 渡部 創; 久保田 俊夫*; 野村 和則

Arai, Yoichi; Watanabe, So; Kubota, Toshio*; Nomura, Kazunori

In order to recover U and Pu from the degraded solvents as a part of waste liquid management program STRAD (Systematic Treatments of RAdioactive liquid wastes for Decommissioning), recovery of loaded cations in simulated degraded solvents into alkali solutions were experimentally examined. A target solvent of this study was TRUEX solvent involving CMPO and TBP in n-dodecane. Zr was used as a simulant of Pu, and recovery performance and mechanism of Zr from simulated spent solvent into NaOH or Na$$_{2}$$CO$$_{3}$$ solutions were evaluated. Zr was recovered in NaOH solution as precipitate, while back extraction of Zr into Na$$_{2}$$CO$$_{3}$$ solution was progressed by forming carbonate complex. Similar recovery mechanisms are also expected for U and Pu loaded in the solvent.

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