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Gamma and Alpha Radiolysis of Salt Brines

Published online by Cambridge University Press:  26 February 2011

W. J. Gray
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, Washington 99352.
S. A. Simonson
Affiliation:
Pacific Northwest Laboratory, P. 0. Box 999, Richland, Washington 99352.
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Abstract

Gamma radiolysis of Permian Basin brine leads to equilibrium gas pressure of about 100 atm. at 75°C and about 40 atm. at 150°C, providing the gas space is very small and/or the total dose is very high. Dose rate dependence is being investigated but is not yet established. Alpha radiolysis of Permian Basin brine is still being evaluated, but it is clear that equilibrium gas pressures will be much higher than with gamma radiolysis. In addition, alpha radiolysis of brine results in a very high solution redox potential. Gas compositions in all cases have been about two parts H2 to one part O2. Efforts to simulate these results with computer models have been quite successful.

Type
Research Article
Copyright
Copyright © Materials Research Society 1985

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References

1. Jenks, G. H. and Claiborne, H. C.. 1981. Brine Migration in Salt and Its Implications in the Geologic Disposal of Nuclear Waste. ORNL-5818, Oak Ridge National Laboratory, Oak Ridge, TN 37380.Google Scholar
2. O'Donnell, J. H. and Sangster, D. F.. 1970. Principles of Radiation Chemistry. American Elsevier, Inc., New York, NY 10017.Google Scholar
3. Burns, W. G., Hughes, A. E., Marples, J. A. C., Nelson, R. S. and Stoneham, A. M.. 1982. “Effects of Radiation on the Leach Rates of Vitrified Radioactive Waste.” J. Nucl. Mater. 107:245.Google Scholar
4. Gray, W.J. 1984. “Gamma Radiolysis of Groundwaters Found Near Potential Radioactive Waste Repositories.” Advances in Ceramics, Vol.8, ed. Wicks, G. G. and Ross, W. A., pp. 5761. The American Ceramic Society, Columbus, Ohio.Google Scholar
5. Pederson, L. R., Clark, D. E., Hodges, F. N., McVay, G. L. and Rai, D.. 1984. “The Expected Environment for Waste Packages in a Salt Repository.” In Mater. Res. Soc. Symposia Proceedings Scientific Basis for Nuclear Waste Management VII, ed. McVay, G. L., pp. 417426. North-Holland, New York, NY Google Scholar
6. Carver, M. D., Hanely, D. Y. and Chaplin, K. R.. 1979. MAKSIMA-CHEMIST: A Program for Mass Action Kinetics Simulation by Automatic Chemical Equation Manipulation and Integration Using Stiff Techniques, AECL-6413, Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada.Google Scholar
7. Uchida, S., Ibe, E. and Katsura, R.. 1983. “Effects of Irradiation on Corrosion Circumstances in Boiling Water.” Phys. Chem. 22(305): 515526.Google Scholar
8. Simonson, S. A. and Kuhn, W. L.. 1984. “Predicting Amounts of Radiolytically Produced Species in Brine Solutions.” In Scientific Basis for Nuclear Waste Management VII, ed. McVay, G. L., pp. 781787. Elsevier Science Publishing Company, New York, NY.Google Scholar