Sorption characteristics of UO{sub 2}{sup 2+} in nitric acid on Reillex{sup {trademark}}-HPQ columns
Conference
·
OSTI ID:126577
- Los Alamos National Lab., NM (United States); and others
In an effort to reduce the total volume of the nuclear materials inventory at the DOE sites and to better utilize the space available in the proposed geologic repositories, the recovery of uranium from nuclear waste is required. The subject of this work is the application of ion exchange technology for the separation of uranium from complex waste streams as an alternative to more traditional solvent extraction techniques. We have continued to characterize the sorption and elution behavior for uranium in nitric acid solutions for the Reillex{trademark}-HPQ anion exchange system. We will discuss the effect of flow rate, uranium concentration, column size, and speciation on the breakthrough and elution properties of uranium on the Reillex{trademark}-HPQ column.
- OSTI ID:
- 126577
- Report Number(s):
- CONF-950402--
- Country of Publication:
- United States
- Language:
- English
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