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Multicomponent Leach Tests in Standard Canadian Shield Saline Solution on Glasses Containing Simulated Nuclear Waste

Published online by Cambridge University Press:  25 February 2011

Robert B. Heimann ,
Donald D. Wood  and
Richard F. Hamon
Robert B. Heimann
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba ROE ILO, Canada
Donald D. Wood
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba ROE ILO, Canada
Richard F. Hamon
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba ROE ILO, Canada
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Abstract

Leaching experiments on borosilicate glass frit and simulated nuclear waste glasses were performed as a preliminary to leaching experiments on glasses incorporating radioactive waste. The experimental design included (i) simulated waste glass, (ii) ASTM Grade-2 titanium container material, (iii) clay buffer material, (iv) Standard Canadian Shield Saline Solution, and (v) granitic rock.

Cumulative fractions of release for boron were determined, as well as the solution concentrations of silicon, iron, strontium and cesium. The leach rates for boron after 28 d were approximately 5x10-6 kg.m-2 .8-1 for experiments in stainless steel vessels, and 2xl0-7 kg.m-2 .s-1 in Hastelloy* vessels. There is an apparently strong relationship between the clay/groundwater ratio, the concentration of iron in the solution, and the concentrations of silicon, strontium, and cesium.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 191
Copyright
Copyright © Materials Research Society 1984

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References

REFERENCES

1. Boulton, J. ed., “Management of Radioactive Fuel Wastes: The Canadian Disposal Program,” Atomic Energy of Canada Limited Report, AECL-6314 (1978).Google Scholar
2. Heimann, R.B. and Johnson, L.H., “Design of Multicomponent Systems Tests on High-Level Nuclear Waste Forms,” in: Advances in Ceramics, Vol. 8 (Nuclear Waste Management). (American Ceramic Society, in press).Google Scholar
3. Burrill, K.A., “Development of a Batch Process for Immobilizing Some CRNL Radioactive Wastes in Glass.” Proc. Second Annual Conference of the Canadian Nuclear Society, Ottawa, 1981 June. Atomic Energy of Canada Limited Report, AECL-7334.Google Scholar
4. Morey, G.W., Fournier, R.O., and Rowe, J.J., J. Geophys. Res. 69, 1995 (1964).Google Scholar
5. Barkatt, A., Macedo, P.B., Sousanpour, W., Boroomand, M.A., Szoke, P. and Rogers, V.L., “Aluminosilicate Saturation as a Solubility Control in Leaching of Nuclear Waste-Form Materials.” MCC Workshop on the Leaching Mechanisms of Nuclear Waste Forms, Gaithersburg, MD., 1982 May 19–21.Google Scholar
6. Goto, K., J. Chem. Soc. Jap. Pure Chem. Sect. 76, 1364 (1955).Google Scholar
7. Iler, R.K., The Chemistry of Silica (J. Wiley & Sons, New York, (1979) pp. 45, 48.Google Scholar
8. Krauskopf, K.B., Geochim. Cosmochim. Acta 10, 1 (1956).Google Scholar
9. Sanders, D.M. and Hench, L.L., J. Amer. Ceram. Soc. 56, 373 (1973),CrossRefGoogle Scholar
9a Ethridge, E.C., “Mechanisms and Kinetics of Binary Alkali Silicate Glass Corrosion”, Ph.D. Thesis, Univ. of Florida, 1977.Google Scholar
10. Haines, R.I., pers. communication.Google Scholar
11. Seyfried, W.E. and Mottl, M.J., Geochim. Cosmochim. Acta 46, 985 (1982).Google Scholar
12. McVay, G.L. and Buckwalter, C.Q., “The Effect of Iron on Waste Glass Leaching,” Pacific Northwest Laboratory, PNL-SA-10474 (1982).Google Scholar
13. Brindley, G.W., XRPDF #29-1491, 1977.Google Scholar
14. Foster, M.D., Amer. Min. 36, 717 (1951).Google Scholar
15. Sargent, F.P., “Applied Chemistry and Geochemistry Research for the Canadian Nuclear Fuel Waste Management Program,” Atomic Energy of Canada Limited Technical Record, TR-149 (1982). Unrestricted, unpublished report available from SDDO, Atomic Energy of Canada Limited Research Company, Chalk River, Ontario KOJ 1JO.Google Scholar
16. Kharaka, Y.K. and Barnes, I., “SOLMNEQ: Solution-Mineral Equilibrium Computations,” U.S. Nat. Tech. Inform. Ser. PB Report 215899/6, (1973).Google Scholar
17. Bischoff, J.L. and Seyfried, W.E., Amer. J. Sci. 278, 838 (1978).CrossRefGoogle Scholar
18. Hathaway, J.C. and Sachs, P.L., Amer. Min. 50, 852 (1965).Google Scholar