Abstract
The hot-pressing behaviour of hydrated zirconium oxide (with fluoride) derived from Zircaloy nuclear waste is described. The material densifies at relatively low temperatures to give a crystalline ceramic with monoclinic ZrO2 and an oxyfluoride (Zr10O13F14) as major phases. Doping with the inactive radwaste ions U4+, Sr2+ and Cs+ has shown that these should be taken into solid solution in the ceramic at the levels at which they are likely to be present in actual waste. Dissolution tests are described which establish that the ceramics are resistant to attack by water and hence should provide suitable leachresistant hosts for the immobilization of the radwaste ions.
Similar content being viewed by others
References
A. C. Mercer andH. A. Kearsey, private communication.
R. C. Garvie, in “High Temperature Oxides, Part II”, edited by A. M. Alper (Academic Press, New York, 1970) pp. 117–66.
S. A. Selim andS. Hanafi,Surface Technology 12 (1981) 287.
J. L. Woodhead,Sci. Ceram. 4 (1968) 105.
B. Holmberg,Acta Cryst. B26 (1970) 830.
P. Joubert andB. Gaudreau,Rev. Chim. minérale 12 (1975) 289.
R. Papiernik, B. Gaudreau andB. Frit,J. Sol. State Chem. 25 (1978) 143.
W. I. Stuart, T. L. Whately andR. B. Adams,J. Australian Ceram. Soc. 8 (1972) 6.
T. Noguchi, T. Okuko andO. Yonemochi,J. Amer. Ceram. Soc. 52 (1969) 181.
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Atkinson, A., Nickerson, A.K. & Taylor, R.I. The fabrication and properties of Zr-O-F ceramics for the immobilization of Zircaloy nuclear waste. J Mater Sci 17, 2979–2989 (1982). https://doi.org/10.1007/BF00644679
Received:
Accepted:
Issue Date:
DOI: https://doi.org/10.1007/BF00644679