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Reducing the uncertainty of nuclear fuel dissolution: an investigation of UO2 analogue CeO2

Published online by Cambridge University Press:  25 January 2013

Claire L. Corkhill ,
Daniel J. Bailey ,
Stephanie M. Thornber ,
Martin C. Stennett  and
Neil C. Hyatt
Claire L. Corkhill
Affiliation:
The Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, UK, S1 3JD.
Daniel J. Bailey
Affiliation:
The Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, UK, S1 3JD.
Stephanie M. Thornber
Affiliation:
The Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, UK, S1 3JD.
Martin C. Stennett
Affiliation:
The Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, UK, S1 3JD.
Neil C. Hyatt
Affiliation:
The Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, UK, S1 3JD.
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Abstract

In this investigation, CeO2 analogues, which approximate as closely as possible the characteristics of fuel-grade UO2, were characterised after dissolution under a wide range of conditions. Powdered samples were subject to a range of aggressive and environmentally relevant alteration media with different solubility controls, and reacted at 70 °C and 90 °C. Dissolution kinetics were monitored through analysis of the coexisting aqueous solution. Monolith samples were monitored for development of surface defects such as pores and dissolution pits, in addition to morphological changes at grain boundaries and surface pores upon dissolution under aggressive conditions. The surfaces were analysed using confocal profilometry, vertical scanning interferometry and scanning electron microscopy. Dissolution rates were found to be greatest in low pH solutions and at higher temperatures. Preferential dissolution appears to occur at grain boundaries and on particular grains, suggesting a crystallographic control on dissolution.

Keywords

nuclear materialscorrosiongrain boundaries
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1518: Symposium LL – Scientific Basis for Nuclear Waste Management XXXVI , 2012 , pp. 151 - 156
Copyright
Copyright © Materials Research Society 2013 

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References

REFERENCES

Shoesmith, D. W., Journal of Nuclear Materials 282, 1 (2000).CrossRefGoogle Scholar
Ollila, K. and Oversby, V, SKB Technical Report TR-05-07 (2005).Google Scholar
Ollila, K., Posiva Work Report 2008-75 (2008).Google Scholar
Stennett, M. C., Corkhill, C. L., Marshall, L. A. and Hyatt, N. C. Journal of Nuclear Materials 432, 182 (2013).CrossRefGoogle Scholar
Claparede, L., Clavier, N., Dacheux, N., Moisy, P., Podor, R. and Ravaux, J., Inorganic Chemistry 50, 9059 (2011).CrossRefGoogle Scholar
Icenhower, J. P., Strachan, D. M., Lindberg, M. M., Rodriguez, E. A. and Steele, J. L. PNNL Report 14252 (2003).Google Scholar
Godinho, J. R. A., Piazolo, S., Stennett, M. C. and Hyatt, N. C. Journal of Nuclear Materials 419, 46 (2011).CrossRefGoogle Scholar
Godinho, J. R. A., Piazolo, S. and Evins, L. Z.. Geochimica et Cosmochimica Acta 86, 392 (2012).CrossRefGoogle Scholar