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Characterisation of 20 Year Old Pu238 -Doped Synroc C

Published online by Cambridge University Press:  01 February 2011

M.J. Hambley ,
S. Dumbill ,
E.R. Maddrell  and
C.R. Scales
M.J. Hambley
Affiliation:
Nexia Solutions Ltd, Sellafield, Seascale, Cumbria, CA201PG, UK
S. Dumbill
Affiliation:
Nexia Solutions Ltd, Sellafield, Seascale, Cumbria, CA201PG, UK
E.R. Maddrell
Affiliation:
Nexia Solutions Ltd, Sellafield, Seascale, Cumbria, CA201PG, UK
C.R. Scales
Affiliation:
Nexia Solutions Ltd, Sellafield, Seascale, Cumbria, CA201PG, UK
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Abstract

In 1987 samples of Pu238 and Cm244 doped Synroc C were prepared in the UKAEA Laboratories at Harwell. They were studied for five years before being archived. During decommissioning of the Harwell laboratories the samples were transferred to Sellafield and the opportunity was taken to conduct further studies. Given the age of the samples, they offer a unique insight into the long term radiation stability of Synroc. To date, the three Pu238 samples have been examined. The alpha decay dose experienced by the samples is estimated to be 3 × 1019 alphas per gram.

The sample allowed to accumulate alpha decay damage (10587) was slightly heterogeneous, with an apparent grain size in the range 3–15νm. EDX analysis confirmed the phases present to be those expected in Synroc C and that the Pu had partitioned predominantly into the perovskite and zirconolite. Microcracking was observed in the hollandite and rutile but cracks arrested once they reached a zirconolite or perovskite grain.

Sample 10588 was annealed after five years, at temperatures up to 1200°C, this sample was microstructurally similar to 10587 at the 20-50νm scale but differs at small scales. A major difference is the presence of both intergranular and intragranular porosity.

Sample 10589 was annealed at the same time as 10588 but differed significantly probably due to actual fabrication temperatures being higher than those recorded.

Information on these samples will be presented, along with a discussion of the implications for the expected long term stability of titanate ceramic wasteforms.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1107: Scientific Basis for Nuclear Waste Management XXXI , 2008 , 373
Copyright
Copyright © Materials Research Society 2008

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References

1 Burns, W. G. et al. J. Nucl. Mater. 107 (1982) 245.Google Scholar
2 Marples, J. A. C.. Nuclear Instruments and Methods in Physics research. B32 (1988) 480.Google Scholar
3 Boult, K. A., Dalton, J. T., Evans, J. P., Hall, A. R., Inn, A. J., Marples, J. A. C. and Paige, E. L.. “The Preparation of Fully-Active Synroc and its Radiation Stability” Oct 87.AERE-R-13318.Google Scholar
4 Hough, A. and Marples, J. A. C. “The Radiation Stability of Synroc: Final Report”. Nov 93. AEA-ES-0201(H).Google Scholar
5 Weber, W. J., Wald, J. W. and Matzke, H. J. J. Nucl. Mater. 138 (1986) 196 Google Scholar
6 Grey, I E., Li, C., MacRae, C.M., Burshill, L.A. J. Solid State Chemistry. 127 (1996) 240–247.Google Scholar
7 Perera, D. S., Begg, B. D., Vance, E. R. and Stewart, M. W.A.: in ‘Advances in Technology of Materials and Materials Processing’ 6(4) (2004) pp214–217.Google Scholar
8 Ewing, R. C. and Headley, T. J.: J. Nucl. Mater. 119 (1983) 102–109 Google Scholar
9 Clinard, F. W. Jr , Peterson, D. E., Rohr, D. L. and Hobbs, L. W.: J. Nucl. Mater. 126 (1984) 245–254 Google Scholar
10 Cheary, R. W., Acta Cryst. B42 (1986) 229–236 Google Scholar
11 Carter, M.. (Private Communication)Google Scholar