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A Coupled Chemical-Mass Transport Submodel for Predicting Radionuclide Release from an Engineered Barrier System Containing High-Level Waste Glass

Published online by Cambridge University Press:  21 February 2011

B. P. McGrail
Affiliation:
Battelle, Pacific Northwest Laboratories, P. O. Box 999, Richland, WA 99352
M. J. Apted
Affiliation:
Battelle, Pacific Northwest Laboratories, P. O. Box 999, Richland, WA 99352
D. W. Engel
Affiliation:
Battelle, Pacific Northwest Laboratories, P. O. Box 999, Richland, WA 99352
A. M. Liebetrau
Affiliation:
Battelle, Pacific Northwest Laboratories, P. O. Box 999, Richland, WA 99352
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Abstract

A mechanistic model describing a dynamic mass balance between the production and consumption of silicic acid was coupled to a near-field mass transport model to predict the dissolution kinetics of a high-level waste glass in a deep geologic repository. The effects of interactions between an iron overpack and the glass are described by a time-dependent precipitation reaction for a ferrous silicate mineral. The kinetic model is used to transform radionuclide concentration-versus-reaction progress values, predicted from a geochemical reaction path computer code, to concentration-versus-time values that are used to calculate the rate of radionuclide release by diffusive mass transfer to the surrounding host rock. The model provides for both solubility-limited and kinetically limited release; the rate-controlling mechanism is dependent on the predicted glass/groundwater chemistry.

Type
Research Article
Copyright
Copyright © Materials Research Society 1990

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References

REFERENCES

1. Liebetrau, A. M., Engel, D. W., McGrail, B. P., Apted, M. J., Sasaki, N., and Masuda, S.. 1989. “Preliminary Release Calculations Using the AREST-PNC Code.” Proceedings of the ASME High-Level Waste Management Conference, October 23–28, Kyoto, Japan.Google Scholar
2. Liebetrau, A. M. et al. 1987. The Analytical Repository Source-Term (AREST) Model: Description and Documentation. PNL-6346, Pacific Northwest Laboratory, Richland, Washington.Google Scholar
3. Chambré, P. L., et al. 1985. Mass Transfer and Transport in a Geologic Environment. LBL-19430, Lawrence Berkeley Laboratory, Berkeley, California.Google Scholar
4. Grambow, B. 1985. “A General Rate Equation for Nuclear Waste Glass Corrosion.” In Scientific Basis for Nuclear Waste Management VIII, eds. Jantzen, C. M., Stone, J. A., and Ewing, R. C.. Materials Research Society, Pittsburgh.Google Scholar
5. McGrail, B. P. 1988. “Modeling the Dissolution Behavior of Defense Waste Glass in a Salt Repository Environment.” In Scientific Basis for Nuclear Waste Management XI, Eds. Apted, M. J. and Westerman, R. E., Materials Research Society, Pittsburgh, Pennsylvania.Google Scholar
6. McVay, G. L. and Buckwalter, C. Q.. 1983. “Effect of Iron on Waste Glass Leaching.” J. Amer. Ceram. Soc. 66(3):170174.Google Scholar
7. Jantzen, C. M. 1984. “Methods of Simulating Low Redox Potential (Eh) for a Basalt Repository.” In Scientific Basis for Nuclear Waste Management VII, ed. McVay, G. L.. Elsevier Science Publishing Co., Inc., New York.Google Scholar
8. Shade, J. W. Pederson, L. R., and McVay, G. L.. 1984. “Waste Glass-Metal Interactions in Brines.” In Advances in Ceramics -Volume 8: Nuclear Waste Management, eds. Wicks, G. G. and Ross, W. A.. American Ceramic Society, Inc., Columbus, Ohio.Google Scholar
9. McGrail, B. P. 1986. “Waste Package Component Interactions with Savannah River Defense Waste Glass in a Low-Magnesium Salt Brine.” Nuc. Tech. 75(2):168186.Google Scholar
10. Grambow, B., et al. 1987. “Modeling of the Effect of Iron Corrosion Products on Nuclear Waste Glass Performance.” In Scientific Basis for Nuclear Waste Management X, eds. Bates, J. K. and Seefeldt, W. B.. Materials Research Society, Pittsburgh.Google Scholar
11. Harder, H. 1978. “Synthesis of Iron Layer Silicate Minerals under Natural Conditions.” Clays and Clay Minerals. 26(1):6572.Google Scholar
12. Pigford, T. H. and Chambré, P. L.. 1988. “Near-Field Mass Transfer in Geologic Disposal Systems: A Review.” In Scientific Basis for Nuclear Waste Management XI, Eds. Apted, M. J. and Westerman, R. E., Materials Research Society, Pittsburgh, Pennsylvania.Google Scholar