Lloyd, J.W., Stennett, M.C. and Hand, R.J. (2016) Silicon oxycarbide glass for the immobilisation of irradiated graphite waste. Journal of Nuclear Materials, 469. pp. 51-56. ISSN 0022-3115
Abstract
© 2015 Elsevier B.V. Silicon oxycarbide glass has been investigated as a potential immobilisation medium for irradiated graphite waste from nuclear power generation. The glass was synthesised via sol-gel techniques using alkoxysilane precursors. Attempts to produce a wasteform via conventional sintering were unsuccessful, but dense wasteforms were achieved by spark plasma sintering (SPS). Microstructural investigations showed that the addition of graphite to the glass did not alter the structure of the matrix; no reaction between the graphite and the glass matrix was observed. Silicon oxycarbide glass is a viable candidate for encapsulation of graphite waste prior to disposal.
Metadata
Item Type: | Article |
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Authors/Creators: |
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Copyright, Publisher and Additional Information: | © 2016 Elsevier. This is an author produced version of a paper subsequently published in Journal of Nuclear Materials. Uploaded in accordance with the publisher's self-archiving policy. Article available under the terms of the CC-BY-NC-ND licence (https://creativecommons.org/licenses/by-nc-nd/4.0/) |
Dates: |
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Institution: | The University of Sheffield |
Academic Units: | The University of Sheffield > Faculty of Engineering (Sheffield) > Department of Materials Science and Engineering (Sheffield) |
Depositing User: | Symplectic Sheffield |
Date Deposited: | 19 Feb 2016 11:33 |
Last Modified: | 14 Apr 2017 05:28 |
Published Version: | https://dx.doi.org/10.1016/j.jnucmat.2015.11.034 |
Status: | Published |
Publisher: | Elsevier |
Identification Number: | 10.1016/j.jnucmat.2015.11.034 |
Open Archives Initiative ID (OAI ID): | oai:eprints.whiterose.ac.uk:95392 |