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Immobilisation of Simulated Plutonium-Contaminated Material in Phosphate Glass: An Initial Scoping Study

Published online by Cambridge University Press:  21 March 2011

Paul A. Bingham ,
Russell J. Hand  and
Charlie R. Scales
Paul A. Bingham
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD, UK
Russell J. Hand
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD, UK
Charlie R. Scales
Affiliation:
Nexia Solutions, Building B170, Sellafield, Seascale, Cumbria CA20 1PG, UK
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Abstract

Vitrification is a potential route for the immobilisation of Plutonium Contaminated Material (PCM). This is an Intermediate Level Waste (ILW) arising from operations in which there is contact with Pu isotopes. PCM consists of low levels of Pu combined with metals, masonry, glass, ceramics, polymers and other carbonaceous materials. Simulated PCM containing CeO2 as a PuO2 surrogate was mixed with a phosphate precursor and vitrified. Pre-oxidation of PCM simulant prior to vitrification minimised the violence of batch reactions. No pre-oxidation produced inhomogeneous slag-like materials with high residual metals and particulates. Pre-oxidation at 600°C in air and at 1200°C in an O2-rich atmosphere produced more favourable results, with increasingly vitreous products resulting from more oxidised PCM simulant. The most oxidised PCM simulant produced phosphate glasses with low levels of particulate inclusions, as confirmed by x-ray diffraction and scanning electron microscopy. Particulates included iron-rich metallics and aluminous oxides. Increased melting times and temperatures may have reduced the number of inclusions slightly, but O2 bubbling during melting resulted in little additional benefit. Waste loading equivalent to ∼60 weight % of untreated waste may be possible. There was little evidence of Ce partitioning, indicating that it was immobilised within the glass matrix and had little preference for metallic or crystalline phases. These results demonstrate the potential feasibility for vitrification of PCM in phosphate glass, justifying further investigation into this potentially novel solution.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 932: Symposium – Scientific Basis for Nuclear Waste Management XXIX , 2006 , 89.1
Copyright
Copyright © Materials Research Society 2006

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References

REFERENCES

1. Management of plutonium contaminated waste, Ed. Grover, J. R., Harwood Academic Publishers, London, 1981.Google Scholar
2. Donald, I. W., Metcalfe, B. L. and Taylor, N. J., J. Mat. Sci. 32, 5851 (1997).Google Scholar
3. Hyatt, N. C., personal communication.Google Scholar
4. Bingham, P. A. and Hand, R. J., J. Hazard. Mater., B119, 125 (2005).Google Scholar
5. Bingham, P. A., Hand, R. J., Forder, S. D. and Lavaysierre, A., J. Hazard. Mater., B122, 129 (2005).Google Scholar
6. Mesko, M. G. and Day, D. E., J. Nucl. Mater., 273, 27 (1999).Google Scholar
7. Kim, D. S., Vienna, J. D., Hrma, P. and Cassingham, N., Ceram. Trans., 143, 337 (2003).Google Scholar
8. Rabiger, W., Keldenich, K. and Scheffler, J., Glastech. Ber. Glass Sci. Technol. 68, 85 (1995).Google Scholar
9. Colombo, P., Brusatin, G., Bernardo, E. and Scarinci, G., Curr. Opin. Solid State Mat. Sci., 7, 225 (2003).Google Scholar
10. Tzeng, C. C., Kuo, Y. Y., Huang, T. F., Lin, D. L. and Yu, Y. J., J. Hazard. Mater., 58, 207 (1998).Google Scholar
11. Darab, J. G., Li, H., Schweiger, M. J., Vienna, J. D., Allen, P. G., Bucher, J. J., Edlestein, N. M., Shuh, D. K., Proc. Plutonium Futures '97, New Mexico, 143 (1997).Google Scholar
12. Ramsey, W. G., Bibler, N. E., Meaker, T. F., WSRC-MS-94-0550; http://www.osti.gov/bridge/servlets/purl/63953-Dcglhu/webviewable/63953.pdfGoogle Scholar