Hostname: page-component-586b7cd67f-gb8f7 Total loading time: 0 Render date: 2024-11-24T22:06:52.519Z Has data issue: false hasContentIssue false

A Comparison of the Performance of Nuclear Waste Glasses by Modeling

Published online by Cambridge University Press:  28 February 2011

B. Grambow
Affiliation:
Hahn-Meitner Institut, Berlin, Federal Republic of Germany
D. M. Strachan
Affiliation:
Pacific Northwest Laboratory, Richland, WA 99352
Get access

Extract

The reprocessing of spent fuel from nuclear reactors and processing of fuels for defense purposes have generated large volumes of high-level liquid waste that need to be immobilized prior to final storage. For immobilization, the wastes must be converted to a less soluble solid, and, although other waste forms exist, glass currently appears to be the choice for the transuranic-containing portion of the reprocessed waste. Once produced, this glass will be sent in canisters to a geologic repository located some 200 to 500 m below the surface of the earth.

Type
Research Article
Copyright
Copyright © Materials Research Society 1988

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. Wallace, R.M. and Wicks, G.G., in Scientific Basis for Nuclear Waste Management VI, edited by Brookins, D.G., (North Holland, New York, 1983).Google Scholar
2. Hench, L.L., Clark, D.E., and Yen-Bower, E.L., in Proceedings of the Conference on High-Level Radioactive Solid Waste Forms, edited by Casey, L.A., (NUREG/CP-0005, U.S. Nuclear Regulatory Agency, Washington, DC 1979).Google Scholar
3. Bunker, B.C., Arnold, G.W., Beauchamp, E.K., and Day, D.E., J. Non-Crystalline Solids, 58, 295322 (1983).Google Scholar
4. Malow, G., in Scientific Basis for Nuclear Waste Management V, edited by Lutze, W., (North Holland, New York, 1982).Google Scholar
5. Kuhn, W.L. and Peters, R.D., in Scientific Basis for Nuclear Waste Management XI, edited by Brookins, D.G. (North-Holland, New York, 1983).Google Scholar
6. Machiels, A.J. and Pescatore, C., Modeling of Waste Form Leaching. Part II: Mechanistic Modeling of Nuclear Waste Form Leaching by Aqueous Solutions. UILU-ENG-82–5360 (REV.7/83), University of Illinois, Urbana, IL 1982.Google Scholar
7. Harvey, K.B., Litke, C.D., and Boase, C.A., in Advances in Ceramics - Nuclear Waste Management, edited by Wicks, G.G. and Ross, W.A. (American Ceramic Society, Columbus, OH 1984).Google Scholar
8. Plodinec, M.J., Jantzen, C.M., and Wicks, G.G., in Advances in Ceramics, Vol.8, edited by Wicks, G.G. and Ross, W.A. (The American Ceramic Society, Columbus, OH 1984).Google Scholar
9. Grambow, B., PhD thesis, Freien Universitaet Berlin, Berlin, Federal Republic of Germany, 1984.Google Scholar
10. Grambow, B., Hermansson, H-P., Bjoerner, I-K., and Werme, L.O., in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L.O. and Arhlstroem, P-E (Materials Research Society, Pittsburgh, PA 1986).Google Scholar
11. JSS, Final Report JSS Project Phase IV, SKB Technical Report 87, Swedish Nuclear Fuel and Waste Management Co., Stockholm, Sweden, 1987.Google Scholar
12. Crovisier, J.L., Fritz, B., Grambow, B., and Eberhart, J.P., in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L.O. (Materials Research Society, Pittsburgh, PA 1986).Google Scholar
13. Aagaard, P. and Helgeson, H.C.. American Journal of Science, 282, 237285 (1982).CrossRefGoogle Scholar
14. Rimstidt, J.D. and Barnes, H.L., Geochimica et Cosmochimica Acta 44, 16831699 (1980).Google Scholar
15. Grambow, B., Nuclear Waste Glass Dissolution: Mechanism, Model, and Application. Report to the JSS-Project Phase IV, Hahn-Meitner-Institut, Berlin, Federal Republic of Germany, 1986.Google Scholar
16. Parkhurst, D.L., Thorstenson, D.C., and Plummer, L.N., PHREEQE - A Computer Program for Geochemical Calculations, USGS/WRI-80–96. U.S. Geological Survey, Reston, VA 1980. (This code has been modified for the following: 1. Automatic reaction progress calculations by Dr. Peter Offerman, Hahn-Meitner Institute, Berlin, FRG, and 2. Replacement of the thermodynamic data base with the data base from MINTEQ by K.M. Krupka and W.M. Howden.)Google Scholar
17. JSS, Final Report JSS Project Phase III: Static Corrosion of Radioactive Glass at 40°C and Corrosion of Radioactive Glass under Dynamic Conditions, SKB Technical Report 86–01, Swedish Nuclear Fuel and Waste Management Co., Stockholm, Sweden, 1986.Google Scholar
18. Ross, W.A., et al., Annual Report on the Characteristics of High-Level Waste Glasses, PNL-2625, Pacific Northwest Laboratory, Richland, WA 1978.Google Scholar
19. Soper, P.D., et al. Bulletin of the American Ceramic Society 62, 10131018 (1983).Google Scholar
20. Strachan, D.M., Pederson, L.R., and Lokken, R.O., Results from the Long-Term Interactions and Modelling of SRL-131 Glass with Aqueous Solutions, PNL-5654, Pacific Northwest Laboratory, Richland, WA 1985.Google Scholar
21. Wicks, G.G., Stone, J.A., Chandler, G.T., and Williams, S., Long-Term Leaching Behavior of Simulated Savannah River Plant Glass. Part I: MCC-1 Leachability Results, Four-Year Leaching Data, E.I. du Pont de Nemours & Co, Savannah River Laboratory, Aiken, SC 1986.Google Scholar
22. Dilmore, M.F., Clark, D.E., and Hench, L.L., in American Ceramic Society Bulletin 58, 1111–1114, 1117, 1124 (1979).Google Scholar
23. Grambow, B. and Strachan, D.M., in Scientific Basis for Nuclear Waste Management VII, edited by McVay, G.L., (Elsevier Science Publishing Co., Inc., New York, 1984).Google Scholar
24. Pederson, L.R., Buckwalter, C.Q., McVay, G.L., and Riddle, B.L., in Scientific Basis for Nuclear Waste Management VI, edited by Brookins, D.G. (North-Holland, New York, 1983).Google Scholar
25. Barkatt, A., Macedo, P.B., Gibson, B.C., and Montrose, C.J., in Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C.M., Stone, J.A., and Ewing, R.C. (Materials Research Society, Pittsburgh, PA 1984).Google Scholar
26. Materials Characterization Center (MCC), Final Report of the Defense High-Level Waste Leaching Mechanisms Program, PNL-5157, Pacific Northwest Laboratory, Richland, WA 1984.Google Scholar
27. Grambow, B., in 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).Google Scholar