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Leaching Studies of Synroc Crystalline Ceramic Waste Forms

Published online by Cambridge University Press:  26 February 2011

A. G. Solomaha  and
Hj. Matzkeb
A. G. Solomaha
Affiliation:
Institut für Chemische Technologie, Kernforschungsanlage, KFA-Jülich, Postfach 1913, D-5170 Jülich, Federal Republic of, Germany
Hj. Matzkeb
Affiliation:
European Institute for Transuranium Elements, Commission of the European Communities, Joint Research Centre, Karlsruhe, D-7500 Karlsruhe, Federal Republic of, Germany
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Abstract

The leaching performance of pressureless sintered SYNROC crystalline ceramic waste forms containing simulated high-level radioactive waste has been evaluated under different leach conditions, i.e. in deionized water and in a simulated brine (Q-brine) at different leach temperatures. The leach solutions were analyzed using inductively coupled plasma and atomic absorption spectrometry (ICPS and AAS) to determine the concentrations of the simulated waste elements and the matrix components released into the leachants. The leach rates of Ba and Ca were in the range of 0.1 to 0.02 g/(m2.d) after one week of leaching in deionized water at 150 °C. No significant difference in the leach behaviour of SYNROC was observed in distilled water and in simulated brine. The leached surfaces of SYNROC were characterized using Rutherford backscattering spectrometry (RBS), secondary ion mass spectrometry (SIMS), scanning electron microscopy (SEM) and elastic recoil detection analysis (ERDA). RBS and SIMS analyses revealed the existence of near-surface layers enriched in Ti and depleted in Ba and Ca. Elastic recoil detection analysis showed the existance of hydrated surface layers on the leached SYNROC which were much thinner than those observed in parallel work with borosilicate waste glasses. Radiation damage produced by ion implantation increased the otherwise very-small leach rates of SYNROC. At high damage levels, SYNROC was shown to become amorphous (metamict).

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 241
Copyright
Copyright © Materials Research Society 1989

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References

REFERENCES

1. Bonniaud, R., Jouan, A. and Sombret, C., J. Nucl. Chem. Waste Manag. 1, 3 (1980).Google Scholar
2. Mendel, J.E., Ross, W.A., Roberts, F.P., Katayama, Y., Westsik, J., Turcotte, R., Wald, J. and Bradley, D., Annual Report on the Characterization of High- Level Waste Glasses, Batteile Pacific Northwest Lab. Report BWNL-2252, UC-70U977).Google Scholar
3. McCarthy, G.J., Nucl. Technol. 32, 92–105 (1977).CrossRefGoogle Scholar
4. Ringwood, A.E., Safe Disposal of High-Level Nuclear Reactor Waste: A New Strategy, (Australian National University Press, Canberra, 1978).Google Scholar
5. Ringwood, A.E., Kesson, S.E., Ware, N.G., Hibberson, W. and Major, A., J. Geochem. (Jpn) 13(4), 141(1979).Google Scholar
6. Ringwood, A.E., Kesson, S.E., Ware, N.G., Hibberson, W. and Major, A., Nature (London) 278(15), 219 (1979).CrossRefGoogle Scholar
7. Solomah, A.G., Hare, T.M. and Palmour, H. J, Trans. Amer. Nucl. Soc. 34, 183(1980).Google Scholar
8. Solomah, A.G. and Zumwalt, L.R., Trans. Amer. Nucl. Soc. 35, 191(1980).Google Scholar
9. Solomah, A.G. and Zumwalt, L.R., Rad. Effects 60, 254(1982).Google Scholar
10. Solomah, A.G., J. Nucl. Technol. 63, 311(1983).Google Scholar
11. Solomah, A.G., in The Treatment and Handling of Radioactive Wastes, Blasewitz, A.G., Davis, J.M. and Smith, M.R., eds. (Battelle Press, Columbus, OH, 1982) p. 331.Google Scholar
12. Solomah, A.G., Odoj, R., Merz, E. and Thiele, D., in Transactions of European Nuclear Conference, ENC4, FORATOM IX, 1986, pp. 627.Google Scholar
13. Oversby, V.M. and Ringwood, A.E., J. Radioact. Waste Manag. 2(3), 223 (1982).Google Scholar
14. Reeve, K.D., Levins, D.M., Wolfrey, J.L. and Ramm, E.J., in Nuclear Waste Management, edited by Wicks, G. and Ross, W. (Advances in Ceramics 20 (1984) pp. 200.Google Scholar
15. White, W.B., Earth Miner. Sci. 50, 13 (1980)Google Scholar
16. Materials Characterization Centre, Nuclear Waste Materials Handbook, DOE/TIC-11400, Pacific Northwest Laboratory, Richland, Wa. (1981).Google Scholar
17. Woolfrey, J.L., Levins, D.M., St, R.. Smart, C. and Stephenson, M., Am. Ceram. Soc. Bull. 66, 1830(1987)Google Scholar
18. Matzke, Hj., in Ion Beam Modifications of Insulators, eds. Mazzoldi, P. and Arnold, G. (Elsevier Science Publishers, New York, 1987) pp. 501.Google Scholar
19. Matzke, Hj., Rad. Effects 64, 3 (1982).Google Scholar
20. Weber, W.J., Wald, J. W. and Matzke, Hj., J. Nucl. Mater. 138, 196(1986).Google Scholar
21. Weber, W.J. and Matzke, Hj., Rad. Effects 98, 93(1986).Google Scholar
22. Fielding, P.E. and White, T.J., J. Mater. Res. 2, 387 (1987)Google Scholar
23. White, T.J., personal communicationGoogle Scholar
24. Kastrissios, T., Stephenson, M., Turner, P.S. and White, T.J., J. Amer. Ceram. Soc. 70, C144(1987)CrossRefGoogle Scholar
25. Buykx, W.J., Hawkins, K., Levins, D.M., Mitamure, H., St, R.. Smart, C., Stevens, G.T., Watson, K.G., Weedon, D. and White, T.J., J. Amer. Ceram. Soc. 71, 678(1988)Google Scholar
26. Neall, F., Myhra, S., Phan, D., Smart, R. St. C. and Turner, P., review paper, these proceedings.Google Scholar