Published 1995 | Version v1
Book

The solubility of UO22+ in dilute sodium chloride solutions and in high-ionic strength sodium sulfate and chlorine brines

  • 1. Lawrence Livermore National Lab., CA (United States)

Description

Uranium is a major component of high-level nuclear waste. In an oxidizing environment, UO22+ 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 UO22+ and the solubility-controlling U(VI) solids in high-ionic strength brines as a function of pH. We have studied the solubility of UO22+ by precipitation of solid phase in 0.001 molal NaCl, 5.2 molal NaCl, and saturated Na2SO4 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

Additional details

Publishing Information

Publisher
American Chemical Society.
Imprint Place
Washington, DC (United States)
Imprint Title
209th ACS national meeting
Imprint Pagination
2088 p.
Journal Page Range
p. 1112, Paper NUCL 99.

Conference

Title
209. American Chemical Society (ACS) national meeting.
Dates
2-6 Apr 1995.
Place
Anaheim, CA (United States).

Optional Information

Secondary number(s)
CONF-950402--.