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The dissolution of simulant vitrified intermediate level nuclear waste in young cement water

Published online by Cambridge University Press:  24 January 2020

Colleen MannOpen the ORCID record for Colleen Mann[Opens in a new window],
Jeremy R. Eskelsen,
Donovan N. Leonard,
Eric Pierce and
Claire L CorkhillOpen the ORCID record for Claire L Corkhill[Opens in a new window]
Colleen Mann
Affiliation:
Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sir Robert Hadfield Building, Mappin Street, Sheffield S1 3JD, UK
Jeremy R. Eskelsen
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN, USA
Donovan N. Leonard
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN, USA
Eric Pierce
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN, USA
Claire L Corkhill*
Affiliation:
Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sir Robert Hadfield Building, Mappin Street, Sheffield S1 3JD, UK
*
*Corresponding author. Email address: c.corkhill@sheffield.ac.uk (C L Corkhill)
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Abstract

It is pertinent to the safety case for geological disposal in the UK that the behaviour of vitrified wastes in proximity to cementitious materials is understood. In this study, vitrified simulant intermediate level nuclear waste (ILW) was subject to dissolution in a synthetic cement water solution to simulate disposal conditions. Results show that the presence of alkali / alkaline earth elements in the cementitious solution can be favourable, at least in the short-term, leading to lower dissolution rates associated with incorporation of these elements into the altered layer of the glass.

Keywords

glassscanning transmission electron microscopy (STEM)waste management

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Type
Articles
Information
MRS Advances , Volume 5 , Issue 3-4: Scientific Basis for Nuclear Waste Management XLIII , 2020, pp. 131 - 140
Copyright
Copyright © Materials Research Society 2020

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References

Vasconcelos, R. G. W., Beaudoin, N., Hamilton, A., Hyatt, N. C., Provis, J. L., and Corkhill, C. L., ‘Characterisation of a high pH cement backfill for the geological disposal of nuclear waste: The Nirex Reference Vault Backfill’, Appl. Geochemistry, vol. 89, no. July 2017, pp. 180–189, 2018.Google Scholar
Lothenbach, B., Le Saout, G., Gallucci, E., and Scrivener, K., ‘Influence of limestone on the hydration of Portland cements’, Cement and Concrete Research, Jun. 2008.CrossRefGoogle Scholar
dit Coumes, C., Low pH cements for waste repositories: A review. 2008.Google Scholar
Ribet, S. and Gin, S., ‘Role of neoformed phases on the mechanisms controlling the resumption of SON68 glass alteration in alkaline media’, J. Nucl. Mater., vol. 324, no. 2–3, pp. 152–164, 2004.CrossRefGoogle Scholar
Mercado-Depierre, S., Angeli, F., Frizon, F., and Gin, S., ‘Antagonist effects of calcium on borosilicate glass alteration’, J. Nucl. Mater., vol. 441, no. 1–3, pp. 402–410, Oct. 2013.CrossRefGoogle Scholar
Gin, S.et al., ‘The fate of silicon during glass corrosion under alkaline conditions: A mechanistic and kinetic study with the International Simple Glass’, Geochim. Cosmochim. Acta, vol. 151, pp. 68–85, 2015.CrossRefGoogle Scholar
Mann, C.et al., ‘Influence of young cement water on the corrosion of the International Simple Glass’, npj Mater. Degrad., vol. 3, no. 1, pp. 1–9, 2019.CrossRefGoogle Scholar
Corkhill, C. L., Cassingham, N. J., Heath, P. G., and Hyatt, N. C., ‘Dissolution of UK High-Level Waste Glass Under Simulated Hyperalkaline Conditions of a Colocated Geological Disposal Facility’, Int. J. Appl. Glas. Sci., vol. 4, no. 4, pp. 341–356, Dec. 2013.CrossRefGoogle Scholar
Utton, C. A., Hand, R. J., Bingham, P. A., Hyatt, N. C., Swanton, S. W., and Williams, S. J., ‘Dissolution of vitrified wastes in a high-pH calcium-rich solution’, J. Nucl. Mater., vol. 435, no. 1–3, pp. 112–122, 2013.CrossRefGoogle Scholar
Utton, C. A., Hyatt, N. C., and Swanton, S. W., ‘Interactions of vitrified wastes with NRVB A report to NDA RWMD’, 2012.Google Scholar
Utton, C. A., Hand, R. J., Hyatt, N. C., Swanton, S. W., and Williams, S. J., ‘Formation of alteration products during dissolution of vitrified ILW in a high-pH calcium-rich solution’, Journal of Nuclear Materials, 2013.Google Scholar
Ferrand, K., Liu, S., and Lemmens, K., ‘The Interaction Between Nuclear Waste Glass and Ordinary Portland Cement’, Int. J. Appl. Glas. Sci., vol. 4, no. 4, pp. 328–340, Dec. 2013.CrossRefGoogle Scholar
Int’l, A., ‘Standard Test Methods for Determining Chemical Durability of Nuclear , Hazardous , and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test ( PCT ) 1’.Google Scholar
Giffaut, E.et al., ‘Andra thermodynamic database for performance assessment: ThermoChimie’, Appl. Geochemistry, vol. 49, pp. 225–236, 2014.CrossRefGoogle Scholar
Abrajano, T. A., Bates, J. K., Woodi-and, A. B., and Bourcier, W. L., ‘Secondary phase formation during nuclear waste-glass dissolution’, Clays Clay Miner ., vol. 38, no. 5, pp. 537–548, 1990.CrossRefGoogle Scholar
Schofield, J. M.et al., ‘Experimental studies of the chemical durability of UK HLW and ILW glasses. First interim progress report (RWM005105)’, 2013.Google Scholar