Reducing hazard in spent fuel removal using colloidal silica gel
Pagano, Arianna G. and El Mountassir, Gráinne and Lunn, Rebecca J. (2022) Reducing hazard in spent fuel removal using colloidal silica gel. In: Waste Management Conference 2022, 2022-03-06 - 2022-03-10.
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Abstract
Nuclear site decommissioning involves the retrieval and handling of radioactive waste. Waste removal from nuclear reactors and/or storage facilities, such as spent fuel pools and storage silos, represents a potential hazard in terms of radiation exposure for the workforce and the surrounding environment. This study explores the suitability of colloidal silica grouting around radioactive waste to reduce radiation exposure during retrieval operations. Previous work on colloidal silica gel has proved its potential to form low-permeability hydraulic barriers, and to inhibit the diffusion of radionuclides through the gel, making it a promising material for spent fuel recovery applications. This work provides experimental evidence that colloidal silica hydrogel can maintain its integrity upon exposure to temperatures typical of the nuclear waste stored within pools and silos, both in standard conditions (up to 60 °C), and during loss of cooling/loss of coolant accidents (>100 °C).
ORCID iDs
Pagano, Arianna G. ORCID: https://orcid.org/0000-0002-9110-183X, El Mountassir, Gráinne ORCID: https://orcid.org/0000-0003-4213-8182 and Lunn, Rebecca J. ORCID: https://orcid.org/0000-0002-4258-9349;-
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Item type: Conference or Workshop Item(Paper) ID code: 82610 Dates: DateEvent10 March 2022PublishedSubjects: Technology > Engineering (General). Civil engineering (General) > Environmental engineering Department: Faculty of Engineering > Civil and Environmental Engineering Depositing user: Pure Administrator Date deposited: 06 Oct 2022 12:56 Last modified: 11 Nov 2024 17:07 URI: https://strathprints.strath.ac.uk/id/eprint/82610