Degradation of partially immersed glass: A new perspective
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Published version
Author(s)
Chinnam, RK
Fossati, PCM
Lee, William E
Type
Journal Article
Abstract
The International Simple Glass (ISG) is a six-component borosilicate glass which was developed as a reference for international collaborative studies on high level nuclear waste encapsulation. Its corrosion behaviour is typically examined when it is immersed in a leaching solution, or when it is exposed to water vapour. In this study, an alternative situation is considered in which the glass is only partially immersed for 7 weeks at a temperature of 90ºC. In this case, half of the glass sample is directly in the solution itself, and the other half is in contact with a water film formed by condensation of water vapour that evaporated from the solution. This results in a different degradation behaviour compared to standard tests in which the material is fully immersed. In particular, whilst in standard tests the system reaches a steady state with a very low alteration rate thanks to the formation of a protective gel layer, in partially-immersed tests this steady state could not be reached because of the continuous alteration from the condensate water film. The constant input of ions from the emerged part of the sample caused a supersaturation of the solution, which resulted in early precipitation of secondary crystalline phases.
This setup mimics storage conditions once small amounts of water have entered a glass waste form containing canister. It offers a more realistic outlook of corrosion mechanisms happening in such situations than standard fully-immersed corrosion tests.
This setup mimics storage conditions once small amounts of water have entered a glass waste form containing canister. It offers a more realistic outlook of corrosion mechanisms happening in such situations than standard fully-immersed corrosion tests.
Date Issued
2018-05-01
Date Acceptance
2018-02-26
Citation
Journal of Nuclear Materials, 503, pp.56-65
ISSN
0022-3115
Publisher
Elsevier
Start Page
56
End Page
65
Journal / Book Title
Journal of Nuclear Materials
Volume
503
Copyright Statement
© 2018 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY license
(http://creativecommons.org/licenses/by/4.0/
(http://creativecommons.org/licenses/by/4.0/
License URL
Sponsor
Engineering & Physical Science Research Council (E
Grant Number
EP/L014041/1
Subjects
Science & Technology
Technology
Materials Science, Multidisciplinary
Nuclear Science & Technology
Materials Science
NUCLEAR-WASTE GLASSES
CALCIUM SILICATE HYDRATE
90 DEGREES-C
VAPOR HYDRATION
UNSATURATED CONDITIONS
AQUEOUS CORROSION
SURFACE-LAYERS
HIGH-LEVEL
DISSOLUTION
WATER
0912 Materials Engineering
Energy
Publication Status
Published
Date Publish Online
2018-02-27