The solubility of UO{sub 2}{sup 2+} in dilute sodium chloride solutions and in high-ionic strength sodium sulfate and chlorine brines
- Lawrence Livermore National Lab., CA (United States); and others
Uranium is a major component of high-level nuclear waste. In an oxidizing environment, UO{sub 2}{sup 2+} would be expected to be the dominant dissolved species in solution. In addition to dilute solutions, because high-level nuclear waste may be stored in repositories containing salt, it is important to characterize the aqueous chemistry of UO{sub 2}{sup 2+} and the solubility-controlling U(VI) solids in high-ionic strength brines as a function of pH. We have studied the solubility of UO{sub 2}{sup 2+} by precipitation of solid phase in 0.001 molal NaCl, 5.2 molal NaCl, and saturated Na{sub 2}SO{sub 4} at pH values ranging from 5 to 12. The solution concentrations were measured by alpha particle liquid scintillation counting. The precipitated solids were characterized by powder x-ray diffraction, electron microscopy, infrared spectroscopy, and x-ray photoelectron spectroscopy.
- OSTI ID:
- 126711
- Report Number(s):
- CONF-950402-; TRN: 96:004698
- Resource Relation:
- Conference: 209. American Chemical Society (ACS) national meeting, Anaheim, CA (United States), 2-6 Apr 1995; Other Information: PBD: 1995; Related Information: Is Part Of 209th ACS national meeting; PB: 2088 p.
- Country of Publication:
- United States
- Language:
- English
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