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Solubility Limits. on Radionuclide Dissolution

Published online by Cambridge University Press:  26 February 2011

Jerry F. Kerrisk
Jerry F. Kerrisk*
Affiliation:
Los Alamos National Laboratory, Los Alamos, NM 87545 USA
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Abstract

This paper examines the effects of solubility in limiting dissolution rates of a number of important radionuclides from spent fuel and high-level waste. Two simple dissolution models were used for calculations that would be characteristic of a Yucca Mountain repository. A saturation-limited dissolution model, in which the water flowing through the repository is assumed to be saturated with each waste element, is very conservative in that it overestimates dissolution rates. A diffusion-limited dissolution model, in which element-dissolution rates are limited by diffusion of waste elements into water flowing past the waste, is more realistic, but it is subject to some uncertainty at this time. Dissolution rates of some elements (Pu, Am, Sn, Th, Zr, Sm) are always limited by solubility. Dissolution rates of other elements (Cs, Tc, Np, Sr, C, I) are never solubility limited; their release would be limited by dissolution of the bulk waste form. Still other elements (U, Cm, Ni, Ra) show solubility-limited dissolution under some conditions.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 237
Copyright
Copyright © Materials Research Society 1985

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References

1. Environmental Protection Agency, “40 CFR Part 191, Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes,” Federal Register, Vol.47, No., 250, December 29, 1982, pp. 58196–58206 and April 17, 1984 draft.Google Scholar
2. Nuclear Regulatory Commission, “10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, Technical Criteria,” Federal Register, Vol.48, No. 120, June 21, 1983, pp. 28194–28229.Google Scholar
3. Daniels, W. R., Wolfsberg, K., Rundberg, R. S., Ogard, A. E., Kerrisk, J. F., Duffy, C. J. et al., “Summary Report on the Geochemistry of Yucca Mountain and Environs,” Los Alamos National Laboratory report LA-9328-MS (December 1982).CrossRefGoogle Scholar
4. Sass, J. and Lachenbruch, A., “Preliminary Interpretation of Thermal Data from the Nevada Test Site,” US Geological Survey Open File report 82-973 (1983).CrossRefGoogle Scholar
5. Croff, A. G. and Alexander, C. W., “Decay Characteristics of Once-Through LWR and LMFBR Spent Fuels, High-Level Wastes, and Fuel-Assembly Structural Material Wastes,” Oak Ridge National Laboratory report ORNL/Th-7431 (November 1980).CrossRefGoogle Scholar
6. Neretnieks, l., “Diffusion in the Rock Matrix: An Important Factor in Radionuclide Retardation?” J. Geophys. Res. 85, 4379–4397.CrossRefGoogle Scholar
7. Ogard, A. E. and Kerrisk, J. F., “Groundwater Chemistry Along Flow Paths Between a Proposed Repository Site and the Accessible Environment,” Los Alamos National Laboratory report LA-10188-MS (in preparation).Google Scholar
8. Apps, J. A., Carnahan, C. L., Lichtner, P. C., Michel, M. C., Perry, D., Silva, R. J. et al., “Status of Geochemical Problems Relating to the Burial of High-Level Radioactive Waste, 1982,” Lawrence Berkeley Laboratory report LBL-15103 (March 1983).Google Scholar
9. Allard, B., “Solubilities of Actinides in Neutral or Basic Solutions,” in Actinides in Perspective, Edelstein, N. M., Ed., Proc. of the Actinides - 1981 Conf., Pacific Grove, California, September 10–15, 1981 (Pergamon Press, New York, 1982).Google Scholar