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Transport of Actinides Through a Bentonite Backfill

Published online by Cambridge University Press:  15 February 2011

B. Torstenfelt ,
H. Kipatsi ,
K. Andersson ,
B. Allard  and
U. Olofsson
B. Torstenfelt
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden.
H. Kipatsi
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden.
K. Andersson
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden.
B. Allard
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden.
U. Olofsson
Affiliation:
Department of Nuclear Chemistry, Chalmers University of Technology, S–412 96 Göteborg, Sweden.
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Extract

Compacted bentonite has been proposed as a suitable backfill material in the Swedish concept for underground storage of high-level waste. The backfill barrier will serve both as a physical barrier, preventing convective water flow and allowing radionuclide penetration only by diffusion, and as a chemical barrier capable of chemically interacting with the radionuclides.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 11: Symposium – Scientific Basis for Nuclear Waste Management V , 1981 , 659
Copyright
Copyright © Materials Research Society 1982

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References

REFERENCES

1. “Handling of Spent Nuclear Fuel and Final Storage of Vitrified High-Level Reprocessing Waste” and “Handling and Final Storage of Unreprocessed Spent Nuclear Fuel”, Kärnbränslesäkerhet (KBS), Stockholm 1977 and 1978.Google Scholar
2. Torstenfelt, B., Andersson, K., Kipatsi, H., Allard, B., Olofsson, U., “Diffusion Measurements in Compacted Bentonite” in Topp, S. (Ed.), Scientific Basis for Nuclear Waste Management, Vol.6, Elsevier, New York 1982, in press.Google Scholar
3. Jacobsson, A., Pusch, R., “Egenskaper hos bentonitbaserat buffertmaterial” (Properties of bentonite based buffer substances), KBS-TR–32, Kärnbränslesäkerhet, Stockholm 1978 (in Swedish).Google Scholar
4. Torstenfelt, B., Andersson, K., Allard, B., “Sorption of Sr and Cs on Rocks and Minerals. Part I: Sorption in Groundwater”, Report Prav 4.29, National Council for Radioactive Waste, Stockholm 1981.Google Scholar
5. Choppin, G. R., Kullberg, L., “Protonation Thermodynamics of Humic Acid”, J. Inorg. Nucl. Chem. 40 651 (1978).Google Scholar
6. Allard, B., Olofsson, U., Torstenfelt, B., Kipatsi, H., Andersson, K., “Sorption of Actinides in Well-defined Oxidation states on Geologic Media”, Proc. Mat. Res. Soc. Ann. Meeting, Berlin, June 7–10 1982.Google Scholar
7. Crank, J., The Mathematics of Diffusion, (Oxford University Press, London 1956).Google Scholar
8. Eriksen, T., Jacobsson, A., “Ion Diffusion Through Highly Compacted Bentonite”, KBS–TR–81–06, Kärnbränslesäkerhet, Stockholm 1981.Google Scholar
9. Eriksen, T., Jacobsson, A. “Ion Diffusion in Compacted Sodium and Calcium Bentonites”, KBS–TR–81–12, Kärnbränslesäkerhet, Stockholm 1982.Google Scholar
10. Reid, R. C., Prausnitz, J. M., Sherwood, T. K., The Properties of Gases and Liquids, 3rd ed. (Mc Graw-Hill, New York 1977).Google Scholar
11. Allard, B., “Solubilities of Actinides in Neutral or Basic Solutions”, in Edelstein, N., Proc. of the Actinides–81 Conf., Pergamon Press, Oxford 1982, in press.Google Scholar
12. Amphlett, C. B., Inorganic Ion Exchangers, (Elsevier, Amsterdam 1964).Google Scholar
13. Neretnieks, I., “Transport of Oxidants and Radionuclides Through a Clay Barrier”, KBS–TR–79, Kärnbränslesäkerhet, Stockholm 1978.Google Scholar
14. Allard, B., Beall, G. W., “Actinide-retaining Backfill Materials in Underground Repositories for Alpha-Contaminated Wastes”, in Management of Alpha-Contaminated Wastes. (IAEA–SM–246/13, Vienna 1981, p. 667).Google Scholar