| 摘要 |
<p>1,219,146. Reprocessing nuclear fuel. ATOMENERGI A.B. 18 April, 1968 [21 April, 1967], 18456/68. Heading G6R. Plutonium and uranium are recovered from a plurality of nuclear fuel elements which have been irradiated, e.g. in a fast reactor, to different levels, by extracting Pu with a selective solvent from a solution of the highly irradiated elements, combining the residual solution with a solution of the less irradiated elements, extracting U and Pu from this combined solution with a different solvent, and separating the Pu and U extracted. The highly irradiated elements may be dissolved in nitric acid and extracted with trilauryl amine or trilauryl methylamine, which is treated with acetic acid to re-extract the Pu. The residual aqueous phase is combined with a nitric acid solution of the less irradiated elements and extracted with tributyl phosphate, dibityl carbitol, diamyl butyl phosphonate, or dibutyl phenyl phosphonate. Pu is selectively extracted from the organic phase by contact with a reducing solution of U (IV) nitrate or Fe(II) sulphamate. Pu having different isotope contents may be obtained by recovery from the different solutions separately.</p> |
