Hostname: page-component-77c89778f8-9q27g Total loading time: 0 Render date: 2024-07-20T00:34:03.593Z Has data issue: false hasContentIssue false

HIPed Tailored Ceramic Waste Forms for the Immobilisation of Cs and Sr

Published online by Cambridge University Press:  01 February 2011

Melody L. Carter
Affiliation:
Australian Nuclear Science and Technology Organisation, Institute of Materials Engineering, Menai, NSW 2234, Australia
E. R. Vance
Affiliation:
Australian Nuclear Science and Technology Organisation, Institute of Materials Engineering, Menai, NSW 2234, Australia
Get access

Abstract

This paper illustrates the benefits of hot isostatically pressed (HIPed) tailored ceramic waste forms for the immobilisation of Cs and Sr separated from spent nuclear fuel. Experimental data on microstructure and aqueous durability are presented for Cs- and Sr-bearing hollanditerich tailored ceramics prepared with 12-18 wt% waste (on an oxide basis). MCC-1 type leach testing, on the sample containing 12 wt% waste at 90°C for 28 days revealed extremely low normalised 7-28-day Cs and Sr release rates of 0.003 and 0.004 g/m2day respectively.

Type
Research Article
Copyright
Copyright © Materials Research Society 2008

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 Vandegrift, G. F., Regalbuto, M. C., Aase, S. B., Arafat, H. A., Bakel, A. J., Bowers, D. L., Byrnes, J. P., Clark, M. A., Emergy, J. W., Falkenberg, J. R., Gelis, A. V., Hafenrichter, L. D., Leonard, R. A., Pereira, C. Quigley, K. J., Tsai, Y. Vander Pol, M. H., and Laidler, J. J., WM'04 Conference, ‘Lab-Scale Demonstration of the UREX+ Process’ February 29, – March 4, 2004, Tucson, AZ. Google Scholar
2 Ringwood, A. E., Kesson, S. E., Ware, N. G., Hibberson, W. and Major, A. Nature, 278, 219 (1979).Google Scholar
3 Vance, E. R., J. Austr. Ceram. Soc. 38, [1], 48 (2002).Google Scholar
4 Hart, K. P., Vance, E. R., Day, R. A., Begg, B. D., and Angel, P. J., in Scientific Basis for Nuclear Waste Management XIX, ed. Murphy, W. M. and Knecht, D. A. (Mater. Res. Soc. Symp. Proc. 412, Pittsburgh, PA, 1996) pp. 281287.Google Scholar
5 Carter, M. L., Vance, E. R., Lumpkin, G. R., and Loi, G. R., Carter, M. L., Vance, E. R., Lumpkin, G. R., and Loi, G. R., in Scientific Basis for Nuclear Waste Management XXIV, ed. Hart, K. P. and Lumpkin, G. R. (Mater. Res. Soc. Symp. Proc. 663, Pittsburgh, PA, 2001) pp. 381388.Google Scholar
6 Carter, M. L., Vance, E. R., and Li, H. in Scientific Basis for Nuclear Waste Management XXVII, ed. Oversby, V. M. and Werme, L. O., (Mater. Res. Soc. Symp. Proc. 807, Pittsburgh, PA, 2004) pp. 249254.Google Scholar
7 Carter, M. L., Vance, E. R., and Li, H. in Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IX, ed. Vienna, J. and Spearing, D.. (Ceram. Trans. 155, Indianapolis, IN, 2004) pp. 2130.Google Scholar
8 PCT is based on the ASTM Designation: C 1285-02 Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT). (2002)Google Scholar
9 ASTM C 1220 – 98. “Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste”. ASTM International. (1998).Google Scholar