Hostname: page-component-cd9895bd7-dzt6s Total loading time: 0 Render date: 2024-12-28T07:06:59.322Z Has data issue: false hasContentIssue false

The Dissolution of Uranophane in CaCl2-SiO2(aq) Test Solutions

Published online by Cambridge University Press:  17 March 2011

James D. Prikryl
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute®, San Antonio, TX 78228-0210, U.S.A., E-mail address:, jprikryl@swri.edu
William M. Murphy
Affiliation:
Department of Geological and Environmental Sciences, California State University, Chico, CA 95929-0205, U.S.A.
Get access

Abstract

Uranophane [Ca(UO2)2(SiO3OH)2 · 5H2O] is a corrosion product of long-term leaching of spent fuel under oxidizing conditions and is a weathering product of uraninite in uranium ore deposits hosted by siliceous rocks. Incorporation of radionuclides into uranophane by coprecipitation may occur as a result of spent fuel alteration. Dissolution of uranophane leading to release of these radionuclides may therefore influence the longterm dissolved concentration and mobility of radionuclides at the proposed nuclear waste repository at Yucca Mountain, Nevada. In this study, the dissolution of uranophane in Ca- and Si-rich test solutions was investigated. Batch dissolution experiments were designed to approach uranophane equilibrium from undersaturated solutions at nearneutral pH (~6.0). Test solutions had initial U concentrations of 0.0 and 10-7 mol/L in matrices of ~10-2 mol/L CaCl2 and ~10-3 mol/L SiO2(aq). The test solutions were reacted with synthetic uranophane (confirmed by XRD and chemical analyses) and analyzed periodically over 10 weeks. Reaction quotients (Log Qs) derived from aqueous speciations of experimental solutions considered to be near equilibrium with uranophane ranged from 10.54 to 11.06 for the dissolution reaction: Ca(UO2)2(SiO3OH)2 · 5H2O + 6H+ ⇔ Ca2+ + 2UO22+ + 2SiO2(aq) + 9H2O.

Type
Research Article
Copyright
Copyright © Materials Research Society 2004

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Pearcy, E. C., Prikryl, J. D., Murphy, W. M., and Leslie, B. W., Appl. Geochem. 9, 713732 (1994).Google Scholar
2. Wronkiewicz, D. J., Bates, J. K., Wolf, S. F., and Buck, E. C., J. Nucl. Mater. 238, 7895 (1996).Google Scholar
3. Finch, R. J., Buck, E. C., Finn, P. A., and Bates, J. K., in Scientific Basis for Nuclear Waste Management XXII, edited by Wronkiewicz, D. J. and Lee, J. (Mater. Res. Soc. Symp. Proc. 556, Warrendale, PA, 1999) pp. 431438.Google Scholar
4. Burns, P. C., Ewing, R. C., and Miller, M. L., J. Nucl. Mater. 245, 19 (1997).Google Scholar
5. Burns, P. C., Deely, K. M., and Skanthakumar, S., Radiochim. Acta 92, 151159 (2004).Google Scholar
6. Vochten, R., Blanton, N., Peeters, O., Springel, K. Van, and Haverbeke, L. Van, Can. Mineral. 35, 735741 (1997).Google Scholar
7. Wolery, T., EQ3/6, A Software Package for Geochemical Modeling of Aqueous Systems. UCRL-MA-110662 PT1, Lawrence Livermore National Laboratory, Livermore, CA (1992).Google Scholar
8. Nguyen, S. N., Silva, R. J., Weed, H. C., and Andrews, J. E., J. Chem. Thermodyn. 24, 359376 (1992).Google Scholar
9. Giammer, D. E. and Hering, J. G., Geochim. et Cosmochimica Acta 66, 32353245 (2002).Google Scholar
10. Chen, F., Ewing, R. C., and Clark, S. B., Amer. Mineralogist 84, 650664 (1999).Google Scholar