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Leach Models for a Commercial Nuclear Waste Glass

Published online by Cambridge University Press:  21 February 2011

William L. Kuhn
Affiliation:
Pacific Northwest Laboratory, Richland, Washington
Richard D. Peters
Affiliation:
Pacific Northwest Laboratory, Richland, Washington
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Abstract

A review of the leaching behavior of 76–68 glass shows that it cannot be explained in terms of diffusion in the glass, which has been the basis for several leach models. Instead, we present two models based on a dissolution rate impeded by surface processes: the accumulation of a protective layer of insoluble reaction products, and adsorption of reaction products on the surface. The resulting predicted time dependences are identical and predict a change from linear to parabolic rate laws for soluble species, which is found to agree with the data over a range of temperatures. Incongruent release is attributed primarily to solubility effects. The relative merits of the models are discussed on the basis of the effect of surface area-to-volume ratio in static leach tests. Their relevance to modeling repository behavior is discussed.

Type
Research Article
Copyright
Copyright © Materials Research Society 1983

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References

REFERENCES

1. Kepler, G. and Thomas, M., Glastech. Ber. 11, 205 (1933).Google Scholar
2. Lyle, A. K., J. Am. Ceram. Soc. 26, 202 (1943).Google Scholar
3. Douglas, R. W. and El Shamy, T.M., J. Am. Ceram. Soc. 50, 1 (1967).Google Scholar
4. Boksay, Z. et al. , Phys. Chem. Glasses 8, 140 (1967).Google Scholar
5. Wiley, J. R., Nuclear Technology 43, 268 (1979).Google Scholar
6. Godbee, H. W. and Joy, D. S., Assessment of the Loss of Radioactivity from Waste Solids to the Environment. Part I: Background and Theory. ORNL-TM-4333. Oak Ridge National Laboratory, Oak Ridge, Tennessee (1974).Google Scholar
7. Griffing, D. E., Progress Report on the Development of Models for the Description of Radionuclide Transport in Solids, ARH-SA-190, Atlantic Richfield Hanford Company, Richland, Washington (1974).Google Scholar
8. Machiels, A. J. and Pescatore, C., Scientific Basis for Nuclear Waste Management 3, Moore, J., Ed., Plenum Press, New York, 371 (1981).Google Scholar
9. Cohen, D. S., Leaching of Radioactive Isotopes from Waste Solids. EPA 520/8–81–001. United States Environmental Protective Agency, Washington, D.C. (1981).Google Scholar
10. Kuhn, W. L. et al. , “Development of a Leach Model for a Commercial Nuclear Waste Glass.” PNL-SA-10359, Pacific Northwest Laboratory, Richland, Washington (1982). Submitted to Nuclear Technology.Google Scholar
11. Grambow, B., “The Role of Metal Ion Solubilities in Leaching of Nuclear Waste Glasses.” PNL-SA-10079, Pacific Northwest Laboratory, Richland, Washington (1982) Presented at MRS Meeting, Berlin, June 7–10, 1982.Google Scholar
12. Wicks, G. G. and Wallace, R. M., Leachability of Waste Glass Systems - Physical and Mathematical Models. DP-MS-82–18. Savannah River Laboratory, Aiken, South Carolina (1982).Google Scholar
13. Westsik, J. H. Jr and Peters, R. D., Scientific Basis for Nuclear Waste Management 3, Moore, J., Ed., Plenum Press, New York, 355 (1981).Google Scholar
14. Strachan, D. M., “Results for a 1-Year Leach Test: Long-Term Use of MCC-1.” PNL-SA-10036. Pacific Northwest Laboratory, Richland, Washington (1982).Google Scholar
Scientific Basis for Nuclear Waste Management 5, Lutze, W., Ed., Elsevier North Holland, 1982.Google Scholar
15. Pederson, L. R. et al. “The Effects of Surface Area to Solution Volume Ratio and Surface Roughness on Waste Glass Leaching.” PNL-SA-10306. Pacific Northwest Laboratory, Richland, Washington (1982). Submitted to Nuclear Technology.Google Scholar
16. Braithwaite, J. W., Scientific Basis for Nuclear Waste Management 2, Northrup, C., Ed., Plenum Press, New York, 199 (1980).Google Scholar
17. McVay, G. L. and Buckwalter, C. Q., “The Effect of Iron on Waste Glass Leaching.” PNL-SA-10474. Pacific Northwest Laboratory, Richland, Washington (1982). Submitted to J. Am. Ceram. Soc.Google Scholar
18. Kenna, B. T. and Murphy, K. D., Scientific Basis for Nuclear Waste Management 2, Northrup, C., Ed., Plenum Press, New York, 191 (1980).Google Scholar
19. Lanza, F. and Parnisari, E., Evaluation of Long-Term Leaching of Borosilicate Glass in Pure Water pp. 238242. CUNF-790420. U.S. Department of Energy, Washington, D.C. (1979).Google Scholar