Abstract
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.
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References
R.M. Wallace and G.G. Wicks, in Scientific Basis for Nuclear Waste Management VI, edited by D.G. Brookins, (North Holland, New York, 1983).
L.L. Hench, D.E. Clark, and E.L. Yen-Bower, in Proceedings of the Conference on High-Level Radioactive Solid Waste Forms, edited by L.A. Casey, (NUREG/CP-0005, U.S. Nuclear Regulatory Agency, Washington, DC 1979).
B.C. Bunker, G.W. Arnold, E.K. Beauchamp, and D.E. Day, J. Non-Crystalline Solids, 58, 295–322 (1983).
G. Malow, in Scientific Basis for Nuclear Waste Management V, edited by W. Lutze, (North Holland, New York, 1982).
W.L. Kuhn and R.D. Peters, in Scientific Basis for Nuclear Waste Management XI, edited by D.G. Brookins (North-Holland, New York, 1983).
A.J. Machieis and C. Pescatore, 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.
K.B. Harvey, C.D. Litke, and C.A. Boase, in Advances in Ceramics - Nuclear Waste Management, edited by G.G. Wicks and W.A. Ross (American Ceramic Society, Columbus, OH 1984).
M.J. Plodinec, C.M. Jantzen, and G.G. Wicks, in Advances in Ceramics, Vol. 8, edited by G.G. Wicks and W.A. Ross (The American Ceramic Society, Columbus, OH 1984).
B. Grambow, PhD thesis, Freien Universitaet Berlin, Berlin, Federal Republic of Germany, 1984.
B. Grambow, H-P. Hermansson, I-K. Bjoerner, and L.O. Werme, in Scientific Basis for Nuclear Waste Management IX, edited by L.O. Werme and P-E Arhlstroem (Materials Research Society, Pittsburgh, PA 1986).
JSS, Final Report JSS Project Phase IV, SKB Technical Report 87, Swedish Nuclear Fuel and Waste Management Co., Stockholm, Sweden, 1987.
J.L. Crovisier, B. Fritz, B. Grambow, and J.P. Eberhart, in Scientific Basis for Nuclear Waste Management IX, edited by L.O. Werme (Materials Research Society, Pittsburgh, PA 1986).
P. Aagaard and H.C Helgeson. American Journal of Science, 282, 237–285, (1982).
J.D. Rimstidt and H.L. Barnes, Geochimica et Cosmochimica Acta 44, 1683–1699 (1980).
B. Grambow, Nuclear Waste Glass Dissolution: Mechanism, Model, and Application. Report to the JSS-Project Phase IV, Hahn-Meitner-Institut, Berlin, Federal Republic of Germany, 1986.
D.L. Parkhurst, D.C. Thorstenson, and L.N. Plummer, 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.)
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.
W.A. Ross, et al., Annual Report on the Characteristics of High-Level Waste Glasses, PNL-2625, Pacific Northwest Laboratory, Richland, WA 1978.
P.D. Soper, et al. Bulletin of the American Ceramic Society 62, 1013–1018 (1983).
D.M. Strachan, L.R. Pederson, and R.O. Lokken, Results from the Long-Term Interactions and Modelling of SRL-131 Glass with Aqueous Solutions, PNL-5654, Pacific Northwest Laboratory, Richland, WA 1985.
G.G. Wicks, J.A. Stone, G.T. Chandler, and S. Williams, 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.
M.F. Dilmor, D.E. Clark, and L.L. Hench, in American Ceramic Society Bulletin 58, 1111–1114, 1117, 1124 (1979).
B. Grambow and D.M. Strachan, in Scientific Basis for Nuclear Waste Management VII, edited by G.L. McVay, (Elsevier Science Publishing Co., Inc., New York, 1984).
L.R. Pederson, C.Q. Buckwalter, G.L. McVay, and B.L. Riddle, in Scientific Basis for Nuclear Waste Management VI, edited by D.G. Brookins (North-Holland, New York, 1983).
A. Barkatt, P.B. Macedo, B.C. Gibson, and C.J. Montrose, in Scientific Basis for Nuclear Waste Management VIII, edited by C.M. Jantzen, J.A. Stone, and R.C. Ewing (Materials Research Society, Pittsburgh, PA 1984).
Materials Characterization Center (MCC), Final Report of the Defense High-Level Waste Leaching Mechanisms Program, PNL-5157, Pacific Northwest Laboratory, Richland, WA 1984.
B. Grambow, in Scientific Basis for Nuclear Waste Management VIII, edited by C.M. Jantzen, J.A. Stone, and R.C. Ewing (Materials Research Society, Pittsburgh, PA 1985).
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Grambow, B., Strachan, D.M. A Comparison of the Performance of Nuclear Waste Glasses by Modeling. MRS Online Proceedings Library 112, 713–724 (1987). https://doi.org/10.1557/PROC-112-713
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DOI: https://doi.org/10.1557/PROC-112-713