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Chemical Durability Study of Synroc-C Ceramics Produced by Through-Melting Method

Published online by Cambridge University Press:  03 September 2012

A. V. Kudrin
Affiliation:
Institute of Geology of Ore Deposits RAS. 109017 Staromonetnii 35, Moscow, Russia
B. S. Nikonov
Affiliation:
Institute of Geology of Ore Deposits RAS. 109017 Staromonetnii 35, Moscow, Russia
S. V. Stefanovsky
Affiliation:
SIA”Radon” 119121, 7-th Rostovskii per., 2/14, Moscow, Russia
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Abstract

An interaction between Synroc-C samples prepared by inductive melting in a cold crucible and deionized water was investigated at room temperature, 100 and 200 °C. The leachability of powdered specimens with grainsize 0.10–0.15 mm was determined by repeated static tests with regular replacement of leachant. The experimental data showed that the most leachable elements are the alkali, alkaline earths and molybdenum. The matrix elements such as titanium, zirconium, and rare earths as well are very leach resistant. Comparison of the calculated leach rates of components with reference data on leaching of alternative materials showed that cesium leachability from the studied specimens are close to borosilicate glass, but leaching behavior of other components is comparable to leachability from Synroc-C prepared by hot-pressing.

Type
Research Article
Copyright
Copyright © Materials Research Society 1997

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References

REFERENCES

1. Ringwood, A.E., Kesson, S.E., Ware, N.G., Hibberson, W. and Major, A., Nature 278, pp 219223 (1979).Google Scholar
2. Vlasov, V.I., Kedrovsky, O.L., Nikiforov, A.S., Polyakov, A.S., and Shishtchitz, I. Yu., in Back End of the Nuclear Fuel Cycle, Vienna, IAEA, p 109 (1987).Google Scholar
3. Sobolev, I.A., Stefanovsky, S.V., and Lifanov, F.A., Radiochemistry (Russ.) 33, p. 99 (1993).Google Scholar
4. Stefanovsky, S.V., Yudintsev, S.V., Nikonov, B.S., and Omelyanenko, B.I., Geoecology (Russ.), 4, pp 5875 (1996).Google Scholar
5. Knyazev, O.A., Nikonov, B.S., Omelyanenko, B.I., Stefanovsky, S.V., Yudintsev, S.V., Day, R.A., and Vance, E.R., in Nuclear and Hazardous Waste Management International Topical Meeting, Spectrum'96. Seattle, August 18–23, 1996, pp 21302137.Google Scholar
6. Nuclear Waste Sobolev, I.A., Stefanovsky, S.V., Omelyanenko, B.I., Yudintsev, S.V., Vance, E.R., and Jostsons, A., Scientific Basis for Management XX (these proceedings).Google Scholar
7. Ringwood, A.E., Kesson, S.E., Reeve, K.D., Levins, D.M. and Ramm, E.J., in Radioactive Waste Forms for the Future, edited by Lutze, W. and Ewing, R.C. (North Holland Publishers, 1988), pp 233334.Google Scholar
8. Iseghem, P.V., Jiang, W., Blanchaert, M., Hart, K. and Lodding, A., in Scientific Basis for Nuclear Waste Management XIX (Mat. Res. Soc. Symp. Proc, 412), p 305 (1995).Google Scholar
9. Mendel, J.E., Ross, W.A., Roberts, F.P., Katayama, Y., Westsik, J., Turcotte, R., Wald, J., and Bradley, D., Characteristics of High-Level Waste Glasses, Annual Report. Battelle Pacific Northwest Lab. Report BWNL-2252, UC-70, pp 199 (1977).Google Scholar
10. Oversby, V.M., Ringwood, A.E., Radioactive Waste Management, 2, pp 223238 (1982).Google Scholar