Hostname: page-component-586b7cd67f-g8jcs Total loading time: 0 Render date: 2024-11-29T07:50:37.010Z Has data issue: false hasContentIssue false

Effects of Surface Area-to-Solution Volume Ratio on Chemical Durability of Nuclear Waste Glasses

Published online by Cambridge University Press:  21 February 2011

X. Feng
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington D. C. 20064
I. L. Pegg
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington D. C. 20064
Y. Guo
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington D. C. 20064
AA. Barkatt
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington D. C. 20064
P. B. Macedo
Affiliation:
Vitreous State Laboratory, The Catholic University of America, Washington D. C. 20064
Get access

Abstract

We report data on the relationship between nuclear waste glass durability, as measured by leachate concentrations and leach rates, and the ratio of glass surface area to solution volume, S/V. The study includes West Valley non-radioactive production glasses (SF6 and SF10), West Valley glasses containing U and Th designed at CUA (WVCM47, WVCM50, and WVCM59), Savannah River SRLTDS-131 glass, and Hanford waste glass HW-39 (for which existing literature data is used). While some of these glasses show departures of leachate concentrations from simple (S/V)t scaling others conform well. The departures are, in all cases, most evident at high values of S/V. It is therefore important, therefore to understand how glass composition determines which corrosion mechanism is dominant in order to assess the region of validity of extrapolations based on (S/V)t scaling. While leach rates show a general tendency to decrease with S/V and time, exceptions are evident for the less durable glasses which show minima and maxima in the S/V-dependence at fixed time.

Type
Research Article
Copyright
Copyright © Materials Research Society 1990

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] Pederson, L. R., Buckwalter, C. Q., Mcvay, G. L. and Riddle, B. L., “Glass Surface Area to solution Volume ratio and its implications to accelerated leach testing”, Mat. Res. Soc. Symp. Proc. 15, 4754(1983)Google Scholar
[2] Shade, John W., “Current Technical Issues Related To Near-field Materials Testing”, Mat. Res. Soc. Symp. Vol.44, 775781 (1985)Google Scholar
[3] Barkatt, Aa., Macedo, P. B., Montrose, C. J. et.al, “Final Report of the Defense High-level Waste Leaching Mechanisms”, PNL-5157 1.1 (1984)Google Scholar
[4] Oversby, V. M., “Leach Testing of Waste Forms Interrelationship of ISO and MCC Type Tests,” USDOE Report UCRL-87621, Lawrence Livermore Laboratory, Livermore, CA, May, 1982; G. T. Chandler, G. G. Wicks, and R. M. Wallace, “Effects of SA/V and Saturation on the Chemical Durability of SRP Waste Glass”, Advances in Ceramics, 20, 455-463 (1986).Google Scholar
[5] Bazan, F. and Rego, J., “Parametric Testing of A DWPF Borosilicate Glass”, Mat. Res. Soc Symp. Proc. 44, 303 (1985)Google Scholar
[6] Adiga, R. B., Akomer, E. P. and Clark, D. E., “Effects of Flow Parameters on the Leaching of Nuclear Waste Glass”, Scientific Basis for Nuclear Waste Management VIII. Ed. Jantzen, C. M., Stone, J. A. and Ewing, R. C., 4554 (1985)Google Scholar
[7] Barkatt, Aa., Macedo, P. B., et.al, “The Use of a Flow Test and a Flow Model in Evaluating the Durability of Vitreous Nuclear Waste-Form Materials”, Nucl. Chem. Waste Mang. 4, 153169 (1983)Google Scholar
[8] Zwicky, H. U., Grambow, B., Magsabi, C., Aerne, E. T., Bradley, R., Barnes, B., Graber, Th., Mohos, M., Werme, L. O., “Corrosion Behavior of British Magnox Waste Glass in Pure Water”, Scientific Basis for Nuclear Waste Management V.XII, Ed. Lutze, W., Ewing, R. C., 129136 (1988)Google Scholar
[9] Ethridge, E. C., Clark, D. E., Phys. Chem. Glasses, 20, 35 (1978)Google Scholar
[10] Grambow, B., “A General Rate Equation for Nuclear Waste Glass Corrosion”, Scientific Basis for Nuclear Waste Management VIII, Ed. Jantzen, C. M., Stone, J. A., Ewing, R. C., 1521 (1985)Google Scholar
[11] Machiels, A. J. and Pescatore, C., “The Functional Dependence of Leaching on the Surface Area-to-Solution Volume Ratio”, Mat. Res. Soc. Symp. Proc. 15, 209216 (1983)Google Scholar
[12] Bates, S. O., Piepel, G. F., Johnston, J. W., “Leach Testing of Simulated Hanford Waste Vitrification Plant Reference Glass HW-39“. US DOE Report PNL-6884, Pacific Northwest Laboratory, Richland, Washington, May, 1989 Google Scholar
[13] Eisenstatt, L. R., Chapman, C. C., Bogart, L. R., “A Method for Showing Compliance with High-Level Waste Acceptance Specifications”, “Waste Management '86”, Univeristy of Arizona, Tucson, Arizona, 513519, 1986.Google Scholar
[14] Barkatt, Aa., Adiga, R., Adel-Hadadi, A., Barkatt, Al., Feng, X., Finger, S., Sousanpour, W., “Development of QC and Predictive Leach Tests for West Valley Glasses”, Waste Management'88, Vol.2, Ed. Post, R. G., 473481 (1988).Google Scholar
[15] Feng, X., Pegg, I. L., Barkatt, Aa., Macedo, P. B., Cucinell, S. J., and Lai, S., “Correlation between composition effects on glass durability and the structural role of the constituent oxides”, Nucl. Tech., 85, 334345 (1989).Google Scholar
[16] Bourcier, W. L., Peifer, D. W., Knauss, K. G., McKeegan, K. D., and Smith, D. K.. “A Kinetic Model for Borosilicate Glass Dissolutions Based on the Dissolution Affinity of a SurfaceGoogle Scholar