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The Use of High Durability Alumino-Borosilicate Glass for the Encapsulation of High Temperature Reactor (HTR) Fuel

Published online by Cambridge University Press:  14 February 2013

Paul G. Heath ,
Martin C. Stennett ,
Owen J. McGann ,
Russell J. Hand  and
Neil C. Hyatt
Paul G. Heath
Affiliation:
Department of Materials Science and Engineering, University of Sheffield, Sheffield, South Yorkshire, S1 3JD, United Kingdom.
Martin C. Stennett
Affiliation:
Department of Materials Science and Engineering, University of Sheffield, Sheffield, South Yorkshire, S1 3JD, United Kingdom.
Owen J. McGann
Affiliation:
Department of Materials Science and Engineering, University of Sheffield, Sheffield, South Yorkshire, S1 3JD, United Kingdom.
Russell J. Hand
Affiliation:
Department of Materials Science and Engineering, University of Sheffield, Sheffield, South Yorkshire, S1 3JD, United Kingdom.
Neil C. Hyatt
Affiliation:
Department of Materials Science and Engineering, University of Sheffield, Sheffield, South Yorkshire, S1 3JD, United Kingdom.
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Abstract

The development of suitable waste forms for waste produced by generation IV reactors is of critical concern for future operations. To date no accepted disposal route for Tri-Structural Isotropic (TRISO) High Temperature Reactor (HTR) fuel exists. Alumino-borosilicate glass has been studied for its ability to encapsulate TRISO particle fuels. This glass was selected for its high aqueous durability. Encapsulation was achieved by cold pressing and sintering of glass powders mixed with HTR fuel. Sintering profiles capable of eliminating interconnected porosity in the composites were developed. The chemical compatibility and wetting of the glass matrix with the fuel were analysed along with the aqueous durability of the sintered glass matrix. Composites sintered under a controlled atmosphere produced unfractured monoliths with minimal chemical interaction between the glass and the TRISO particles. The Product Consistency Test (PCT) durability assessment indicated the sintered alumino-borosilicate glass was approximately an order of magnitude more durable than an equivalent R7T7 borosilicate glass. These results suggest sintered alumino-borosilicate glass-TRISO particle composites may provide a potential disposal route for spent TRISO particle fuel.

Keywords

waste managementcorrosioncomposite
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1518: Symposium LL – Scientific Basis for Nuclear Waste Management XXXVI , 2012 , pp. 3 - 8
Copyright
Copyright © Materials Research Society 2013 

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References

REFERENCES

Cartlidge, E., Nuclear’s New Generation, in: Physics World, Institute of Physics, October (2010).Google Scholar
Fachinger, J., den Exter, M., Grambow, B., Holgersson, S., Landesman, C., Titov, M., Podruhzina, T., Nucl. Eng. Des. 236, 543–554 (2006).CrossRefGoogle Scholar
International Atomic Energy Agency, Report; Technical, institutional and economic factors important for developing a multinational radioactive waste repository, June (1998).Google Scholar
Abdelouas, A., Noirault, S., Grambow, B., J. Nucl. Mater. 358, 1–9 (2006).CrossRefGoogle Scholar
Heath, P.G., Corkhill, C. L., Stennett, M.C., Hand, R. J., Meyer, W. C., Hyatt, N. C., Submitted: J. Nucl. Mater. Septemeber (2012).Google Scholar
Gahlert, S., Ondrackek, G., in Radioactive Waste forms for the Future, edited by Ewing, R. C. and Lutze, W. (North-Holland, Amsterdam, 1988) p. 162–191 Google Scholar
ASTM Standard C 1285, Test Methods for Determining Chemical Durability of Nuclear, Hazardous and Mixed Waste Glasses: The Product Consistency Test (PCT), (2002).Google Scholar
Parkhurst, D.L., U.S. Geological Survey Water-Resources Investigations Report 95-4227 (1995)Google Scholar
Howie, R. A., Zussman, J., Wise, W.S., Framework Silicates: Silica Minerals, Feldspathoids and Zeolites, 2 nd Ed. (Geological Society, London, 2004) p. 600 Google Scholar