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.
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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 |
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代理人 |
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主权项 |
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地址 |
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