Uranium/technetium separation for the UREX process - synthesis and characterization of solid reprocessing forms

被引:23
作者
Poineau, F. [1 ]
Du Mazaubrun, J. [1 ]
Ford, D. [2 ]
Fortner, J. [3 ]
Kropf, J. [3 ]
Silva, G. W. C. [1 ]
Smith, N.
Long, K. [2 ]
Jarvinen, G. [2 ]
Czerwinski, K. [1 ]
机构
[1] Univ Nevada, Harry Reid Ctr Environm Studies, Las Vegas, NV 89154 USA
[2] Los Alamos Natl Lab, GT Seaborg Inst, Stockpile Mfg & Support Directorate, Los Alamos, NM 87545 USA
[3] Argonne Natl Lab, Div Chem Engn, Argonne, IL 60439 USA
关键词
Technetium; Uranium; Separation; UREX;
D O I
10.1524/ract.2008.1533
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
In the context of the demonstration of the UREX (uranium extraction) process, a separation of uranium and technetium using an anion exchange resin was performed on a simulant solution containing 98.95 g/L of U-238 and 130.2mg/L of Tc-99. After sorption on the resin, TCO4- was eluted with NH4OH, the eluting stream was treated, and the technetium converted to Tc metal (yield = 52.5%). The purity of the compound was analyzed: it contains less than 23.8 mu g of 131 U per gram of Tc-99. Tc metal was characterized by X-ray diffraction (XRD) and X-ray absorption fine structure (XAFS) spectroscopy; EXAFS analysis clearly confirms the hexagonal structure of the metal obtained after treatment. Uranium was converted to ammonium diuranate and to U3O8 in a yield of 88.2%, analysis indicates that the compound contains less than 0.16 mu g of Tc-99 per gram of ammonium diuaranate.
引用
收藏
页码:527 / 533
页数:7
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