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Dissolution of glass in cementitious solutions: An analogue study for vitrified waste disposal

Published online by Cambridge University Press:  27 February 2018

Colleen Mann
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sheffield, United Kingdom, S1 3JD.
Tjin Le Hoh
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sheffield, United Kingdom, S1 3JD.
Clare L. Thorpe
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sheffield, United Kingdom, S1 3JD.
Claire L. Corkhill*
Affiliation:
NucleUS Immobilisation Science Laboratory, Department of Materials Science and Engineering, The University of Sheffield, Sheffield, United Kingdom, S1 3JD.
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Abstract

The dissolution of a soda-lime silicate glass in two cement leachate compositions, Young Cement Water (YCW) and Ca(OH)2, was investigated, as an analogue for dissolution of vitrified nuclear waste in a cementitious geological disposal facility. Dissolution was performed at repository temperatures (50°C) and under CO2-exclusion. Dissolution rates were observed to be a factor of 20 times higher in YCW than in Ca(OH)2, as result of the high potassium content of YCW solutions. The precipitation of the zeolite phase, K-phillipsite (K(Si,Al)8O16·6H2O), is thought to be responsible for elevated dissolution rates. Conversely, in Ca(OH)2 solutions, the precipitation of calcium- and silica-containing phases, such as tobermorite (Ca5Si6O16(OH)·4H2O), acted to reduce rates of dissolution by forming a barrier to diffusion. These results show that dissolution of vitrified nuclear waste materials in a cementitous repository may be significant during the early stages of cement leaching in groundwater.

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Articles
Copyright
Copyright © Materials Research Society 2018 

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