Uranium/technetium separation for the UREX process - synthesis and characterization of solid reprocessing forms.
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 {sup 238}U and 130.2 mg/L of {sup 99}Tc. After sorption on the resin, TcO{sub 4}{sup -} was eluted with NH{sub 4}OH, 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 {micro}g of {sup 238}U per gram of {sup 99}Tc. 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 U{sub 3}O{sub 8} in a yield of 88.2%, analysis indicates that the compound contains less than 0.16 {micro}g of {sup 99}Tc per gram of ammonium diuaranate.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- NE; USDOE Office of Science (SC)
- DOE Contract Number:
- DE-AC02-06CH11357
- OSTI ID:
- 993688
- Report Number(s):
- ANL/CSE/JA-63067; RAACAP; TRN: US1008111
- Journal Information:
- Radiochim. Acta, Vol. 96, Issue Feb. 26, 2008; ISSN 0033-8230
- Country of Publication:
- United States
- Language:
- ENGLISH
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