Hostname: page-component-78c5997874-mlc7c Total loading time: 0 Render date: 2024-11-02T19:00:08.720Z Has data issue: false hasContentIssue false
  • English
  • Français

The Importance of Secondary Phases in Glass Corrosion

Published online by Cambridge University Press:  28 February 2011

William L. Ebert  and
John K. Bates
William L. Ebert
Affiliation:
Chemical Technology Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439-4837
John K. Bates
Affiliation:
Chemical Technology Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439-4837
Get access

Abstract

The analytical expression used to model glass reaction in computer simulations such as EQ6 is compared to the results of experiments used to support the simulations. The expression correctly predicts the acceleration observed in experiments performed at high glass surface area/1eachant volume ratios (SA/V) upon the formation of secondary phases. High resolution microscopic analysis of reacted glass samples suggests that the accelerated nature of the reaction after secondary phase formation is due to changes in the reaction affinity (i.e., is a solution effect) and not a change in the glass reaction mechanism. The composition of solutions in contact with reacted samples reflect the effects of the secondary phases predicted in the model. Experiments which lead to the generation of secondary phases within short reaction times can be used to identify important secondary phases which must be Included in the data base of computer simulations to correctly project long-term glass reaction behavior.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 212: Symposium P – Scientific Basis for Nuclear Waste Management XIV , 1990 , 89
Copyright
Copyright © Materials Research Society 1991

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

REFERENCES

1. Aagaard, P. and Helgeson, H. C., “Thermodynamic and Kinetic Constraints on Reaction Rates Among Minerals and Aqueous Solutions. I. Theoretical Considerations,” Amer. J. Sci. 282, 237–285 (1982).CrossRefGoogle Scholar
2. Grambow, B., “A General Rate Equation for Nuclear Waste Glass Corrosion,” in Scientific Basis for Nuclear Waste Management VIII, Jantzen, C. M., Stone, J. A., and Ewing, R. C., eds., Materials Research Society, Pittsburgh, PA (1985).Google Scholar
3. Bourcier, W. L., Pfeiffer, D. W., Knauss, K. G., McKeegan, K. D., and Smith, D. K., “A Kinetic Model for BorosiUcate Glass Dissolution Based on the Dissolution Affinity of a Surface Alteration Layer,” Mat. Res. Soc. Symp. Proc. Vol. 176, 209 (1990).CrossRefGoogle Scholar
4. Breck, D. W., Zeolite Molecular Sieves, Structures, Chemistry and Uses, John Wiley and Sons, Inc., New York (1974).Google Scholar
5. Bates, J. K., “The Role of Surface Layers in Glass Leaching Performance,” this volume (1990).CrossRefGoogle Scholar
6. Allen, C. C., Lane, D. L., Johnston, R. G., Marcy, A. D., and Adec, R. R., “Hydrothermal Studies of Simulated Defense Waste Glass Plus Basalt,” Mat. Res. Soc. Symp. Proc. 44, 451 (1985).CrossRefGoogle Scholar
7. Van Iseghem, P. Ph., Timmermans, W., and DeBatist, R., “Parametric Study of the Corrosion Behavior in Static Distilled Water of Simulated European Reference High Level Wastes Glasses,” Mat. Res. Soc. Symp. Proc. 44, 55 (1985).CrossRefGoogle Scholar
8. Ebert, W. L. and Bates, J. K., “The Reaction of Synthetic Nuclear Waste Glass in Steam and Hydrothermal Solution,” Mat. Res. Soc. Symp. Proc. 176, 339–346 (1990).CrossRefGoogle Scholar
9. Bradley, J. P. and Bates, J. K., “Leached Nuclear Waste Glasses: Ultramicrotomy and Analytical Electron Microscopic Characterization,” Proc. of the 12th Int. Congress for Electron Microscopy, Seattle, WA, August 13–17, 1990, pp. 444–445 (1990).Google Scholar
10. Ebert, W. L., Bates, J. K., and Gerding, T. J., “The Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment, Part 4: SRL 165, ATM-1c, and ATM-8 Glass at 1E3 R/h and 0 R/h,” Argonne National Laboratory report ANL-90/13 (1990.CrossRefGoogle Scholar
11. Jantzen, C. M. and Ramsey, W. G., “Prediction of Radioactive Waste Durability by the Hydration Thermodynamic Model: Application to Saturated Repository Environments,” Mat. Res. Soc. Symp. Proc. Vol. 176, 217 (1990).CrossRefGoogle Scholar