In situ dissolution of the international simple glass (ISG-1 & ISG-2) and UK high-level-waste glass in extreme γ-radiation environments

Abstract

In situ γ-irradiated dissolution of the International Simple Glass (ISG) 1 & 2 and a UK high-level waste glass (post-operational-clean-out (POCO)) was investigated following a modified Product Consistency Test-B protocol for 158 d at 40 °C in ultra-high-quality water. Tests were conducted under atmospheric conditions and received a total dose of 21.6 MGy delivered at a rate of 0.137 MGy d–1. The normalised mass loss of B, Na, Ca and Mg were slightly higher in γ-irradiated tests when compared to non-irradiated tests whilst the normalised mass loss of Si was comparable or slightly lower. Boron-normalised mass losses of 0.87 ± 0.31, 0.60 ± 0.04 and 0.68 ± 0.07 g m–2 were calculated for γ-irradiated ISG-1, ISG-2 and POCO, respectively, whilst normalised mass losses in non-irradiated controls were 0.62 ± 0.01, 0.57 ± 0.01 and 0.41 ± 0.06 g m–2. The difference was tentatively attributed to acidification during irradiation.

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Item Type:	Article
Authors/Creators:	Fisher, A.J. Thorpe, C.L. https://orcid.org/0000-0002-2860-8611 Haigh, L.T. https://orcid.org/0000-0001-8752-8374 Pepper, S.E. https://orcid.org/0000-0002-8570-3156 Edge, R.
Copyright, Publisher and Additional Information:	© The Author(s) 2025. This article is licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons licence, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons licence, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons licence and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this licence, visit http://creativecommons.org/licenses/by/4.0/.
Keywords:	Nuclear Waste; Glass; Nuclear Fission; Decay Processes; Glass-ionomer cement; Radiation Dosimetry and Protection
Dates:	Submitted: 24 March 2025 Accepted: 15 April 2025 Published (online): 30 April 2025 Published: 30 April 2025
Institution:	The University of Sheffield
Academic Units:	The University of Sheffield > Faculty of Engineering (Sheffield) > Department of Materials Science and Engineering (Sheffield) The University of Sheffield > Faculty of Engineering (Sheffield) > School of Chemical, Materials and Biological Engineering
Funding Information:	Funder Grant number ENGINEERING AND PHYSICAL SCIENCE RESEARCH COUNCIL EP/S012400/1 Engineering and Physical Sciences Research Council EP/T011424/1
Depositing User:	Symplectic Sheffield
Date Deposited:	14 May 2025 11:08
Last Modified:	14 May 2025 11:08
Status:	Published online
Publisher:	Springer Science and Business Media LLC
Refereed:	Yes
Identification Number:	10.1557/s43580-025-01268-x
Open Archives Initiative ID (OAI ID):	oai:eprints.whiterose.ac.uk:226652

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In situ dissolution of the international simple glass (ISG-1 & ISG-2) and UK high-level-waste glass in extreme γ-radiation environments

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