Hostname: page-component-848d4c4894-nmvwc Total loading time: 0 Render date: 2024-06-14T01:35:29.962Z Has data issue: false hasContentIssue false
  • English
  • Français

The Development of Durable Cementitious Materials for Use in a Nuclear Fuel Waste Disposal Facility

Published online by Cambridge University Press:  28 February 2011

N. C. Burnett ,
R. D. Hooton ,
R. B. Heimann  and
M. Onofrei
N. C. Burnett
Affiliation:
Ontario Hydro, Toronto, Ontario, Canada M8Z 5S4
R. D. Hooton
Affiliation:
Ontario Hydro, Toronto, Ontario, Canada M8Z 5S4
R. B. Heimann
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment Pinawa, Manitoba, Canada ROE ILO
M. Onofrei
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment Pinawa, Manitoba, Canada ROE ILO
Get access

Abstract

This paper describes the work on cement paste development and short-term leaching tests in Standard Canadian Shield Saline Solution (SCSSS) in the presence of bentonite at 150°C. It has been found that:

-supplementary cementing materials such as silica fume or fly ash could significantly improve the properties of sulphate resistant portland cement (SRPC), in particular, permeability to water and pore size distribution.

-the addition of bentonite suppressed the normal tendency of the pH of groundwater to increase rapidly in the presence of cement.

-the presence of bentonite increased the release of potassium ions from the cements.

-– SRPC blended with 20% silica fume resulted in a groundwater pH lower than that of SRPC, with and without bentonite. Moreover, its cumulative fraction of release of potassium was significantly lower than that of SRPC.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 50: Symposium STOCKHOLM – Scientific Basis for Nuclear Waste Management IX , 1985 , 461
Copyright
Copyright © Materials Research Society 1985

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

1. Rummery, T.E. and Rosinger, E.L.J., The Canadian Nuclear Fuel Waste Management Program, AECL 7787, May 1983.Google Scholar
2. Freire-Canosa, J., Cipolla, J. and Burnett, N.C., Dry Storage Systems Evaluation at Ontario Hydro. Proceedings of an International Workshop on Irradiated Fuel Storage, Toronto, Canada, November 1984.Google Scholar
3. Hooton, R.D. and Burnett, N.C., Evaluation of Concrete Casks for the Management of Irradiated Fuel in Canada. Second International Symposium in Ceramics in Nuclear Waste Management. Advances in Ceramics 8, p. 456, (1984).Google Scholar
4. Hooton, R.D. and Burnett, N.C., Development of a Highly Durable Concrete Container for the Storage, Transportation and Disposal of Irradiated Fuel, to be published as American Concrete Institute, Special Publication.Google Scholar
5. Frape, S.K., Fritz, P. and McNutt, R.H., Water-Rock Interaction and Chemistry of Groundwaters from the Canadian Shield, Geochim. Cosmochim. Acta 48, 1617 (1984).Google Scholar
6. Feldman, R.F., Proceedings of the Fifth International Symposium on Concrete Technology, Monterrey, California, 263 (1981).Google Scholar
7. Mehta, P.K., Proceedings of the Fifth International Symposium on Concrete Technology, Monterrey, California, 263 p.35.Google Scholar
8. Feldman, R.F., Effects of Fly Ash Incorporation in Cement and Concrete, Materials Research Society Symp. Proceedings, 124 (1981).Google Scholar
9. Hooton, R.D., Permeability and Pore Structure of Cement Pastes Containing Fly Ash, Slag and Silica Fume. ASTM C-I, Symposium on Blended Cements, Denver, Colorado, June 1984.Google Scholar
10. Cheng-yi, Huang and Feldman, R.F., Influence of Silica Fume on the Microstructural Development in Cement Mortars, Cement and Concrete Research, 15, 285 (1985),Google Scholar
11. Barneyback, R.S. Jr. and Diamond, S., Expression and Analysis of Pore Fluids from Hardened Cement Pastes and Mortars, Cement and Concrete Research, 11, 279 (1981).Google Scholar
12. Page, C.L. and Vennesland, O., Pore Solution Composition and Chloride Binding Capacity of Silica Fume-Cement Paste, Materials and Structures, 16, No. 91, 19 (1983).Google Scholar
13. Heimann, R.B. and Hooton, R.D., Short-Term Dissolution Experiments of Various Cement Formulations in Standard Canadian Shield Saline Solution in the Presence of Clay, AECL Report (to be published).Google Scholar
14. Sargent, F.P., Applied Chemistry and Geochemistry Research for the Canadian Fuel Waste Management Program, Atomic Energy of Canada Limited Technical Record, TR-149, July 1982.Google Scholar
15. Goodwin, B.W. and Munday, M., A Reference Guide to SOLMN - Interactive Solution - Mineral Equilibrium Program, AECL 7800, December 1983.Google Scholar
16. Heimann, R.B. and Stanchell, M.A.T., Reaction of Ca-Saturated Montmorillonite with Groundwater of Different Ionic Strengths at Temperatures Between 25 and 200°C, Geolog. Soc. America Abstracts 16 (6), 536 (1984).Google Scholar
17. Heimann, R.B. and Hooton, R.D., Mineralogical Changes of Various Cement Formulations During Reaction with Groundwater in the Presence of Ca- and Na-Bentonite at 150°C, Can. Min., in preparation.Google Scholar
18. Hamon, R.F., Atomic Energy of Canada Limited, personal communication,1985.Google Scholar
19. Lahann, R.W. and Roberson, H.E., Dissolution of Silica from Montmorillonite: Effect of Solution Chemistry, Geochim. Cosmochim. Acta 44, 1937 (1980).Google Scholar
20. Benson, L.V., A Tabulation and Evaluation of Ion Exchange Data on Smectites, Environ. Geol. 4, 23 (1982).Google Scholar
21. Onofrei, M., Leaching Studies of Heavy Concrete Materials for Nuclear Fuel Immobilization Containers, AECL Report (to be published); also presented at the 87th Annual Meeting of the Amer. Ceram. Soc., Cincinnati, May 5–9, 1985.Google Scholar