Americium Valence Control Experiments in the Dissolved Solution of Irradiated Nuclear Fuel
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概要
- 論文の詳細を見る
A method based on valence control and solvent extraction is presented for separating minor actinides (Am, Np) from nuclear fuel reprocessing solution. With this method, Am is adjusted from trivalence to hexavalence by adding 1.6 M (NH4)2S2O8 and 0.01 M AgNO3 to the solution of irradiated nuclear fuel. In the present study, the resulting valence of Am was determined by spectrophotometry. The oxidizing reaction of Am(III) to Am(VI) is exposed to competition by the oxidation to Pu(VI) of the Pu(IV) co-present in the solution, which results in lowering of the yield of Am(VI) to 90%±4% in a solution containing 15 g/l of Pu. Removal beforehand of Pu(IV) from the solution will permit Am(III) to be oxidized quantitatively. Neptunium also is oxidized to hexavalence under the same conditions that yield Am(VI). The resulting hexavalent actinides are both extractable with TBP (tri-n-butyl phosphate). This means that both the minor actinides americium and neptunium can be recovered from raffinate solution generated from the co-decontamination step in spent fuel reprocessing.
- 一般社団法人 日本原子力学会の論文
- 1999-06-25
著者
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Kamoshida Mamoru
Power & Industrial Systems R & D Laboratory, Hitachi, Ltd.
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Kawamura F
Hitachi Works Hitachi Ltd.
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FUKASAWA Tetsuo
Power & Industrial Systems R&D Division, Hitachi, Ltd.
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FUKASAWA Tetsuo
Hitachi Works, Hitachi, Ltd.
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Kamoshida M
Power & Industrial Systems R&d Laboratory Hitachi Ltd.
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KAWAMURA Fumio
Power & Industrial Systems R&D Division, Hitachi Ltd.
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Fukasawa T
Hitachi Works Hitachi Ltd.
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