发明名称 Separation of uranium from technetium in recovery of spent nuclear fuel
摘要 A method for decontaminating uranium product from the Purex process comprises addition of hydrazine to the product uranyl nitrate stream from the Purex process, which contains hexavalent (UO22+) uranium and heptavalent technetium (TcO4-). Technetium in the product stream is reduced and then complexed by the addition of oxalic acid (H2C2O4), and the Tc-oxalate complex is readily separated from the uranium by solvent extraction with 30 vol. % tributyl phosphate in n-dodecane.
申请公布号 US4528165(A) 申请公布日期 1985.07.09
申请号 US19840559501 申请日期 1984.06.13
申请人 THE UNITED STATES OF AMERICA AS REPRESENTED BY THE UNITED STATES DEPARTMENT OF ENERGY 发明人 FRIEDMAN, HORACE A.
分类号 C01G99/00;C22B3/32;C22B60/02;G21C19/46;(IPC1-7):C01G43/00;C01G57/00 主分类号 C01G99/00
代理机构 代理人
主权项
地址