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The dissolution of simulant UK Ca/Zn-modified nuclear waste glass: Insight into Stage III behavior

Published online by Cambridge University Press:  27 January 2020

Adam J. Fisher ,
Mike T. Harrison ,
Neil C. Hyatt ,
Russell J. Hand  and
Claire L. Corkhill Open the ORCID record for Claire L. Corkhill [Opens in a new window]
Adam J. Fisher*
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, S1 3JD, UK
Mike T. Harrison
Affiliation:
National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG, UK
Neil C. Hyatt
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, S1 3JD, UK
Russell J. Hand
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, S1 3JD, UK
Claire L. Corkhill
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, S1 3JD, UK
*
*(Email: ajfisher1@sheffield.ac.uk)
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Abstract

The dissolution of the United Kingdom’s vitrified high-level-waste simulant, CaZn MW28, was investigated following the Product Consistency Test-B protocol for 112 d at 90 °C and in ultra-high-quality water. Residual rate dissolution (stage II) and rate resumption (stage III), after 28 d, was observed. Thermodynamic modelling suggested that solutions were saturated with respect to Mg- and Zn-bearing phases, and the presence of Mg- and Zn-smectite clays was tentatively observed. The formation of these phases was concurrent with a significant increase in the dissolution rate, similar to Stage III behavior seen in other nuclear waste simulant glass materials, indicating that the addition of Mg and Zn to high-level-waste glass (7.3 wt. % combined) significantly influences the dissolution rate.

Keywords

glasscorrosionnuclear materialsZnMg
Type
Articles
Information
MRS Advances , Volume 5 , Issue 3-4: Scientific Basis for Nuclear Waste Management XLIII , 2020 , pp. 103 - 109
Copyright
Copyright © Materials Research Society 2020

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