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Uranium (VI) Solubility in Carbonate-Free ERDA-6 Brine

Published online by Cambridge University Press:  01 February 2011

Jean-Francois Lucchini ,
Hnin Khaing  and
Donald T. Reed
Jean-Francois Lucchini
Affiliation:
[email protected], Los Alamos National Laboratory, Earth and Environmental Sciences Division, Carlsbad, New Mexico, United States
Hnin Khaing
Affiliation:
[email protected], Los Alamos National Laboratory, Earth and Environmental Sciences Division, Carlsbad, New Mexico, United States
Donald T. Reed
Affiliation:
[email protected], Los Alamos National Laboratory, Earth and Environmental Sciences Division, Carlsbad, New Mexico, United States
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Abstract

When present, uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant (WIPP), uranium is present in significant quantities, with about 647 metric tons to be placed in the repository [1]. Therefore, the chemistry of uranium, and especially its solubility, needs to be determined under WIPP-relevant conditions.

Long-term experiments were performed to measure the solubility of uranium (VI) in carbonate-free ERDA-6 brine, a simulated WIPP brine, at pCH+ values between 8 and 12.5. These data, obtained from the over-saturation approach, were the first WIPP repository-relevant data for the VI actinide oxidation state. The solubility trends observed pointed towards low uranium solubility in WIPP brine and a lack of amphotericity. At the expected pCH+ in the WIPP (˜ 9.5), measured uranium solubility approached 10-7 M. The objective of these experiments was to establish a baseline solubility to further investigate the effects of carbonate complexation on uranium solubility in WIPP brines, during the ongoing research program in actinide solubility under WIPP-relevant conditions.

Keywords

actinideUscanning electron microscopy (SEM)
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1265: Symposium AA – Scientific Basis for Nuclear Waste Management XXXIV , 2010 , 1265-AA01-04
Copyright
Copyright © Materials Research Society 2010

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References

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