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Mineralogical aspects of cement in radioactive waste disposal

Published online by Cambridge University Press:  05 July 2018

F. P. Glasser*
Affiliation:
Chemistry Department, University of Aberdeen, 033 Meston Building, Meston Walk, Old Aberdeen AB24 3UE, UK

Abstract

Some of the physical, chemical and mineralogical characteristics of Portland cement and related materials relevant to nuclear waste immobilization are defined. The ability to condition and maintain a high aqueous pH is undoubtedly the most important factor: it precipitates many species as hydrous oxides or hydroxides. However, in the longer term, many species – cationic as well as anionic – react with one or more cement components forming solubility-limiting phases. Progress on characterization of these phases is outlined. Many of the host phases have natural equivalents and this gives comfort in respect of their likely persistence over geological time. The emerging picture of immobilization in cement suggests that cement compositions can be tailored in terms of pH, Eh and internal chemistry so as to maximize immobilization potential. Nickel, uranium and chromium and chloride are used as examples.

Type
Research Article
Copyright
Copyright © The Mineralogical Society of Great Britain and Ireland 2001

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References

Atkins, M. and Glasser, F.P. (1990) Encapsulation of radioiodine in cementitious waste forms. Pp. 1522 in: Scientific Basis for Nuclear Waste Management, XIII (Oversby, F.M. and Brown, P.W., editors). Materials Res. Soc., Proceedings Pittsburgh, PA Vol.Google Scholar
Atkins, M., Kindness, A., Glasser, F.P. and Gibson, I. (1990) The use of silver as a selective precipitant for 129I in radioactive waste management. Waste Manag., 10, 303–8.CrossRefGoogle Scholar
Birnin-Yauri, U.A. and Glasser, F.P. (1998) Friedel's salt, Ca2Al(OH)6Cl,OH)´2H2O: its solid solutions and their role in chloride binding. Cement Concr. Res., 28, 1713–24.CrossRefGoogle Scholar
Burns, P.C. and Finch, R.J. (1999) Wyartite: crystallographic evidence for the first pentavalent-uranium mineral. Amer. Mineral., 84, 1456–60.CrossRefGoogle Scholar
Conner, J.R. (1990) Chemical Fixation and Solidification of Hazardous Wastes. Van Nostrand- Reinhold, New York.Google Scholar
Damidot, D. and Glasser, F.P. (1997) Thermodynamic investigation of the CaO-Al2O3-CaSO4-CaCl2-H2O system at 25°C and the influence of Na2O. Proceedings of the 10th International Congress on the Chemistry of Cement. 4, paper 4 IV 066.Google Scholar
Damidot, D., Birnin-Yauri, U.A. and Glasser, F.P. (1994) Thermodynamic investigation of the CaO-Al2O3- CaCl2-H2O system at 25°C and the influence of Na2O. Il Cimento, 4, 243–54.Google Scholar
Dickson, C.L. and Glasser, F.P. (2000) Cerium (III, IV) in cement implications for actinide (III, IV) immobilization. Cement Concr. Res., 30, 1619–23.CrossRefGoogle Scholar
Glasser, F.P., Adenot, F., Harris, A.W. Amarantos, S.G., Noe, M., Gonzalez de la Huebra, M. and van Velzen, L. (1997) Management and Disposal of Radioactive Waste (McMenamin, T., editor). Commission of the European Communities, EUR 17543 EN.Google Scholar
Hong, S.Y. and Glasser, F.P., (1999) Alkali binding in cement pastes – Part 1 – The C-S-H phase. Cement Concr. Res., 29, 1893–903.CrossRefGoogle Scholar
Kim, J.I., Fanghanel, T., Regan, L., Nitsche, H., Brendler, V., Grenthe, J., Glasser, F.P., Bruno, J. and Saxena, S. (2000) Joint European Database for Environmental Modelling. Commission of the European Communities EUR 19131 EN.Google Scholar
Kindness, A., Macias, A. and Glasser, F.P. (1994) Immobilisation of chromium in cement matrices. Waste Manag., 14, 311.CrossRefGoogle Scholar
Moroni, L.P. and Glasser, F.P. (1995) Reactions between cement components and U(VI) oxide. Waste Manag., 15, 243–54.CrossRefGoogle Scholar