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Modeling of the Effect of Iron Corrosion Products on Nuclear Waste Glass Performance

  • B. Grambow (a1), H. U. Zwicky (a2), G. Bart (a2), I. K. Bjorner (a3) and L. O. Werme (a4)...

Abstract

Experiments [1], performed in the frame of the JSS-project (joint Japanese [CRIEPI], Swiss [NAGRA], Swedish [SKB] project), demonstrated that the effect of iron corrosion products on the long-term stability of HLW-glass depends on the effective surface area of the corrosion products. The experimental results were described quantitatively by thermodynamic and kinetic modeling with the computer codes GLASSOL and PHREEQE. The model interprets the effect in terms of surface sorption of a monolayer of silica molecules from solution. Silica saturation occurs in solution only, when all surface sites are occupied. The effect of bentonite is also considered. The agreement between calculations and experiment is about as good as in the case of modeling the glass-water reaction only.

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1. Bart, G., Zwicky, H. U., Aerne, E. T., Graber, Th., Z'Berg, D., Tokiwai, M., “Borosilicate Glass Corrosion in the Presence of Steel Corrosion Products,” presented at this conference.
2. Grambow, B., Hermansson, H. P., Björner, I. K., Werme, L., ”Glass/Water Reaction with and without Bentonite Present - Experiment and Model,” Scientific Basis for Nuclear Waste Management IX, edited by Werme, L. (Materials Research Society, Pittsburgh, PA, 1986) pp. 187195.
3. Grambow, B., “A General Rate Equation for Nuclear Waste Glass Corrosion,” Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C. M., Stone, J. A., and Ewing, R. C. (Materials Research Society, Pittsburgh, PA, 1985), pp. 1524.
4. Grambow, B., Hermansson, H. P., Bjorner, I. K., Christensen, H., Werme, L., “Reaction of Nuclear Waste Glass with Slowly Flowing Solutions,” Ceramic Advances 20, Amer. Ceram. Soc., in press (1986).
5. Buckwalter, C. Q. and Pederson, L. R., “Inhibition of Nuclear Waste Glass Leaching by Chemisorption,” J. Am. Ceram. Soc. 65, 9, pp. 431436 (1982).
6. Bazan, F. and Rego, J., “Parametric Testing of a DWPF Borosilicate Glass,” Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C. M., Stone, J. A., and Ewing, R. C. (Materials Research Society, Pittsburgh, PA, 1985), pp. 303310.
7. McVay, G. L. and Buckwalter, C. Q., “Effect of Iron on Waste-Glass Leaching,” J. Am. Ceram. Soc. 66, 3, 170174 (1983).
8. Parkhurst, D. L., Thorstensen, D. C.. Plummer, L. N., “PHREEQE - A Computer Program for Geochemical Calculations,” Water-Resources Investigations 80-96, U.S. Geological Survey, Reston, VA, USA (1980) - extension to run precipitation controlled reactions by Offermann, P., Hahn-Meitner-Institut, Berlin, FRG (1983) - updated with the MINTEQ data base by W. Howden and K. Kruppka, Pacific Northwest Laboratories, Richland, WA, USA (1984).
9. Jantzen, C. M. and Bibler, N. E., “The Role of Groundwater Oxidation Potential and Radiolysis on Waste Glass Performance in Crystalline Repository Environments,” Scientific Basis for Nuclear Waste Management IX, edited by Werme, L. (Materials Research Society, Pittsburgh, PA, 1986) pp. 219230.
10. Shade, J. W., Ames, L. L., and McGarrah, J. E., “Actinide and Technetium Sorption on Iron-Silicate and Dispersed Clay Colloids,” in Geochemical Behavior of Disposed Radioactive Waste, edited by Barney, G. S., Navratil, J. D., and Schulz, W. W., ACS Symposium Series 246 (American Chemical Society, Washington, DC, 1984) pp. 6777.
11. Müller-Vonmoos, M. and Kahr, G., “Mineralogische Untersuchungen von Wyoming Bentonite MX-80 und Montigel,” Technischer Bericht 83-12, Nagra, Baden, Switzerland (1983).
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  • EISSN: 1946-4274
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