Hostname: page-component-848d4c4894-pjpqr Total loading time: 0 Render date: 2024-07-02T22:19:23.352Z Has data issue: false hasContentIssue false
  • English
  • Français

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

Published online by Cambridge University Press:  28 February 2011

B. Grambow ,
H. U. Zwicky ,
G. Bart ,
I. K. Bjorner  and
L. O. Werme
B. Grambow
Affiliation:
Hahn-Meitner-Institut Berlin, Federal Republic of Germany
H. U. Zwicky
Affiliation:
Eidg. Institut. für Reaktorforschung, Baden, Switzerland
G. Bart
Affiliation:
Eidg. Institut. für Reaktorforschung, Baden, Switzerland
I. K. Bjorner
Affiliation:
Studsvik Energiteknik AB, Sweden
L. O. Werme
Affiliation:
SKB, Stockholm, Sweden
Get access

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.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 84: Symposium L – Scientific Basis for Nuclear Waste Management X , 1986 , 471
Copyright
Copyright © Materials Research Society 1987

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. 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.Google Scholar
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. 187–195.Google Scholar
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. 15–24.Google Scholar
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).Google Scholar
5. Buckwalter, C. Q. and Pederson, L. R., “Inhibition of Nuclear Waste Glass Leaching by Chemisorption,” J. Am. Ceram. Soc. 65, 9, pp. 431–436 (1982).CrossRefGoogle Scholar
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. 303–310.Google Scholar
7. McVay, G. L. and Buckwalter, C. Q., “Effect of Iron on Waste-Glass Leaching,” J. Am. Ceram. Soc. 66, 3, 170–174 (1983).CrossRefGoogle Scholar
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).Google Scholar
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. 219–230.Google Scholar
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. 67–77.CrossRefGoogle Scholar
11. Müller-Vonmoos, M. and Kahr, G., “Mineralogische Untersuchungen von Wyoming Bentonite MX-80 und Montigel,” Technischer Bericht 83-12, Nagra, Baden, Switzerland (1983).Google Scholar