Hostname: page-component-745bb68f8f-mzp66 Total loading time: 0 Render date: 2025-02-09T21:50:09.965Z Has data issue: false hasContentIssue false
  • English
  • Français

Evaluation of Spent Fuel as a Waste Form In a Salt Repository

Published online by Cambridge University Press:  25 February 2011

Walter J. GRAY ,
Gary L. McVay ,
John. O. Barner ,
John W. Shade  and
Roger W. Cote
Walter J. GRAY
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA 99352;
Gary L. McVay
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA 99352;
John. O. Barner
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA 99352;
John W. Shade
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA 99352;
Roger W. Cote
Affiliation:
Battelle Memorial Institute, Office of Nuclear Waste Isolation, 505 King Avenue, Colunmus, OH 43201
Get access

Abstract

Leach tests have been performed on spent fuel in synthetic Permian Basin salt brine at 25 and 75°C. Complementary tests on unirradiated UO2 pellets have been conducted in both salt brine and deionized water in the range 25 to 150°C. Iron and/or oxidized zircaloy coupons were included in some of the tests. Uranium release from spent fuel was more than 100 times greater than from U02. In brine, iron had no significant effect on the total uranium release but substantially reduced the amount in solution by causing the uranium to plate out on the iron coupon and container walls and to precipitate as filterable particles.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 437
Copyright
Copyright © Materials Research Society 1984

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

REFERENCES

1. Barner, J.O., Gray, W. J., McVay, G. L., and Shade, J. W., Interactive Leach Tests of UO2 and Spent Fuel with Waste Package Components in Salt Brine (PNL-4898, Pacific Northwest Laboratory, Richland, WA 1983).Google Scholar
2. Johnson, L.H., Shoesmith, D.W., Lunansky, G.E., Bailey, M.G., and Tremaine, P.R., Mechanisms of Leaching and Dissolution of UO2 Fuel, (AECL-6992, Whiteshell Nuclear Research Establishment, Atomic Energy of Canada Limited, Pinawa, Manitoba, Canada 1980).Google Scholar
3. Johnson, L.H. and Joling, H. H. in: Scientific Basis for Nuclear Waste Management, Vol. 6, S.V. Topp, ed. (Elsevier, New York 1982) pp. 321–327. Google Scholar
4. Wang, R. and Katayama, Y.B. in: Scientific Basis for Nuclear Waste Management, Vol. 3, Moore, J. G., ed. (Plenum Press, New York 1981) pp. 379–386. Google Scholar
5. Pourbaix, M., Atlas of Electrochemical Equilibria in Aqueous Solutions (Pergamon Press, New York 1966).Google Scholar
6. Pederson, L.R., Clark, D.E., Hodges, F.N., McVay, G.L., and D. Rai in: (this volume) Scientific Basis for Nuclear Waste Management VII, McVay, G. L., ed. (Elsevier Science Publishing Co., New York 1984).Google Scholar