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Degradation of International Simple Glass Cracks and Surface

Published online by Cambridge University Press:  20 February 2017

R. K. Chinnam ,
C. Hutchison ,
D. Pletser  and
W.E. Lee
R. K. Chinnam*
Affiliation:
Centre for Nuclear Engineering (CNE), Department of Materials, Imperial College London, South Kensington Campus, London SW7 2AZ, UK.
C. Hutchison
Affiliation:
Centre for Nuclear Engineering (CNE), Department of Materials, Imperial College London, South Kensington Campus, London SW7 2AZ, UK.
D. Pletser
Affiliation:
Centre for Nuclear Engineering (CNE), Department of Materials, Imperial College London, South Kensington Campus, London SW7 2AZ, UK.
W.E. Lee
Affiliation:
Centre for Nuclear Engineering (CNE), Department of Materials, Imperial College London, South Kensington Campus, London SW7 2AZ, UK.
*
*(Email: [email protected])
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Abstract

Water degradation of glass waste forms has been studied extensively under a variety of conditions including of bulk glass immersed completely in static or dynamic water. In practice, the vitrified nuclear waste cracks as soon as poured into a container because of differences in thermal expansion coefficients. In addition, in repository the canisters may be only partially immersed in water. Later, water condenses on the surface of glass which corrodes releasing ions. In this work experiments have been performed to understand these effects on the degradation of International Simple Glass (ISG). Simulated cracks were found to develop pitting corrosion in the crack openings when tested by immersing ISG in water. Under load, these pits concentrated stress and grew as large planar cracks inside the glass. The condensation of water on glass surfaces leads to formation of pits and growth of calcium silicate crystals.

Keywords

waste magagementcorrosionsurface chemistry
Type
Articles
Information
MRS Advances , Volume 1 , Issue 63-64: Scientific Basis for Nuclear Waste Management XXXIX , 2016 , pp. 4215 - 4220
Copyright
Copyright © Materials Research Society 2017 

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References

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