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Materials Characteristics and Dissolution Behavior of Spent Nuclear Fuel

Published online by Cambridge University Press:  29 November 2013

L.H. Johnson and
L.O. Werme
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Extract

The geologic disposal of spent nuclear fuel is currently under consideration in many countries. Most of this fuel is in the form of assemblies of zirconium-alloy-clad rods containing enriched (1–4% 235U) or natural (0.71% 235U) uranium oxide pellets. Approximately 135,000 Mg are presently in temporary storage facilities throughout the world in nations with commercial nuclear power stations.

Safe geologic disposal of nuclear waste could be achieved using a combination of a natural barrier (the host rock of the repository) and engineered barriers, which would include a low-solubility waste form, long-lived containers, and clay- and cement-based barriers surrounding the waste containers and sealing the excavations.

A requirement in evaluating the safety of disposal of nuclear waste is a knowledge of the kinetics and mechanism of dissolution of the waste form in groundwater and the solubility of the waste form constituents. In the case of spent nuclear fuel, this means developing an understanding of fuel microstructure, its impact on release of contained fission products, and the dissolution behavior of spent fuel and of UO2, the principal constituent of the fuel.

Information

Type
Nuclear Waste Disposal
Information
MRS Bulletin , Volume 19 , Issue 12 , December 1994, pp. 24 - 27
Copyright
Copyright © Materials Research Society 1994

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References

1.Takats, F., Gregoriev, A., and Ritchie, I.G., IAEA Bulletin 35 (1993) p. 18.Google Scholar
2.Hocking, W.H., Duclos, A.M., and Johnson, L.H., J. Nucl. Mater. 209 (1994) p. 1.CrossRefGoogle Scholar
3.Forsyth, R.S. and Werme, L.O., in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L.O. (Mater. Res. Soc. Symp. Proc. 50, Pittsburgh, PA, 1986) p. 327.Google Scholar
4.Gray, W.J., Strachan, D.M., and Wilson, C.N., in Scientific Basis for Nuclear Waste Management XV, edited by Sombret, C.G. (Mater. Res. Soc. Symp. Proc. 257, Pittsburgh, PA, 1992) p. 353.Google Scholar
5.Johnson, L.H. and Shoesmith, D.W., “Spent Fuel,” in Radioactive Waste Forms for the Future, edited by Lutze, W. and Ewing, R.C. (Elsevier Science, 1988).Google Scholar
6.Stroes-Gascoyne, S., Tait, J.C., Garisto, N.C., Porth, R.J., Ross, J.P.M., Glowa, G.A., and Barnsdale, T.R., in Scientific Basis for Nuclear Waste Management XV, edited by Sombret, C.G. (Mater. Res. Soc. Symp. Proc. 257, Pittsburgh, PA, 1992) p. 373.Google Scholar
7.Matzke, H., J. Nucl. Mater. 190 (1992) p. 101.CrossRefGoogle Scholar
8.Belle, J., Uranium Dioxide: Properties and Nuclear Applications (U.S. Atomic Energy Commission, Washington, DC, 1961).Google Scholar
9.Forsyth, R.S. and Werme, L.O., J. Nucl. Mater. 190 (1992) p. 3.CrossRefGoogle Scholar
10.Ewing, R.C., in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, C.G. and Pabalan, R.T. (Mater. Res. Soc. Symp. Proc. 294, Pittsburgh, PA, 1993) p. 559.Google Scholar
11.Shoesmith, D.W. and Sunder, S., “An Electrochemistry-Based Model for the Dissolution of UO2,” SKB Technical Report 91-63 (1991).Google Scholar
12.Thomas, L.E., Einziger, R.E., and Buchanan, H.C., J. Nucl. Mater. 201 (1993) p. 310.CrossRefGoogle Scholar
13.Janeczek, J., Ewing, R.C., and Thomas, L.E., J. Nucl. Mater. 207 (1993) p. 177.CrossRefGoogle Scholar
14.Cramer, J.J. and Sargent, F.P., in Proc. Intl. High Level Radioactive Waste Management Conf. (Am. Nucl. Soc, May 22-26, 1994, Las Vegas, NV).Google Scholar
15.Snelling, A.A., in Proc. Intl. Uranium Symposium Pine Creek Geosyncline (IAEA, 1980, Vienna) p. 487.Google Scholar
16.Curtis, D.B., Fabryka-Martin, J., Dixon, P., Aguilar, R., and Cramer, J.J., in Proc. Migration ′93 Conf., Charleston, SC, December 12-16, 1993 (in press).Google Scholar
17.Isobe, H., Murakami, T., and Ewing, R.C., J. Nucl. Mater. 190 (1992) p. 174.CrossRefGoogle Scholar
18.Cramer, J.J. and Smellie, J., Final Report of the AECL-SKB Cigar Lake Analog Study, AECL Research Report, AECL-10851 (1994).Google Scholar