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Effects of Air Oxidation on the Dissolution Rate of LWR Spent Fuel

Published online by Cambridge University Press:  01 January 1992

W. J. Gray
Affiliation:
Pacific Northwest Laboratory, P.O. Box 999, Richland, WA 99352
L. E. Thomas
Affiliation:
Pacific Northwest Laboratory, P.O. Box 999, Richland, WA 99352
R. E. Einziger
Affiliation:
Pacific Northwest Laboratory, P.O. Box 999, Richland, WA 99352
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Abstract

Dissolution rates for air-oxidized spent fuel were measured in flowthrough tests where U concentrations were kept well below the solubility limit. Results from two types of specimens, separated grains and coarse particles, both in oxidized (U4O9+x) and unoxidized (UO2) conditions indicated only minor effects of oxidation on the surface-area-normalized rates. Similar results were obtained for unirradiated specimens in three different oxidation states (UO2, U3O7, and U3O8). These observations have important practical implications for disposal of spent fuel in a geologic repository as well as implications regarding the oxidative dissolution mechanism of UO2 fuel.

Type
Research Article
Copyright
Copyright © Materials Research Society 1993

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References

REFERENCES

1. Johnson, L. H., Garisto, N. C., and Stroes-Gascoyne, S., in Waste Management '85, Vol. 1-High-Level Waste, edited by Post, R. G. (Proceedings of the Symposium on Waste Management at Tucson, Arizona, March 24-28, 1985), pp. 479482.Google Scholar
2. Apted, M. J., Liebetrau, A. M., and Engel, D. W., in Waste Management '87, Vol 2-High-Level Waste edited by Post, R. G. (Proceedings of the Symposium on Waste Management at Tucson, Arizona, March 1-5, 1987), pp. 545554.Google Scholar
3. Einziger, R. E., Thomas, L. E., Buchanan, H. C., and Stout, R. B., J. Nucl. Mater. 190, 53 (1992).Google Scholar
4. Gray, W. J. and Thomas, L. E., in Hieh Level Radioactive Waste Management, Proceedings of the Third International Conference, (American Nuclear Society, Inc., La Grange Park, IL, 1992), 2, pp. 14581464.Google Scholar
5. Johnson, L. H. and Shoesmith, D. W., “Spent Fuel,” Chapter 11 in Radioactive Waste Forms for the Future, edited by Lutze, W. and Ewing, R. C. (North-Holland Publishers, New York, 1988).Google Scholar
6. Gray, W. J. and Strachan, D. M., in Scientific Basis for Nuclear Waste Management XIV, edited by Abrajano, T., and Johnson, L. H. (Materials Research Society, Pittsburgh, PA, 1991), 212, pp. 205212.Google Scholar
7. Wilson, C. N. and Gray, W. J., in High Level Radioactive Waste Management (American Nuclear Society, Inc., La Grange Park, IL, 1990), 2, pp. 14311436.Google Scholar
8. Guenther, R. J. et al. , Characterization of Spent Fuel Approved Testing Material - ATM-105, PNL-5109-105 (Pacific Northwest Laboratory, Richland, WA, 1989).Google Scholar
9. Forsyth, R. S. and Werme, L. O., in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L. O. (Materials Research Society, Pittsburgh, PA, 1986), 50, pp. 327336.Google Scholar
10. Gray, W. J., Effect of Surface Oxidation, Alpha Radiolysis, and Salt Brine Composition on Spent Fuel and UO2 Leaching Performance, PNL/SRP-6689 (Pacific Northwest Laboratory, Richland, WA, 1988).Google Scholar
11. Wilson, C. N., Results from NNWSI Series 2 Bare Fuel Dissolution Tests, PNL-7169 (Pacific Northwest Laboratory, Richland, WA, 1990).Google Scholar
12. Katayama, Y. B., Bradley, D. J., and Harvey, C. O., Status Report on LWR Spent Fuel IAEA Leach Tests, PNL-3173 (Pacific Northwest Laboratory, Richland, WA, 1980).Google Scholar
13. Einziger, R. E. and Strain, R. V., Nucl. Tech. 75, 82 (1986).Google Scholar