Abstract
The development of a wasteform for the disposal of I-129 would enable a change in waste management of iodine from recycling of nuclear fuel. Initial results investigating the encapsulation of iodide-loaded metallated silica sorbents into a geopolymer matrix are presented. Two silica materials, with a mercapto and a thiourea functionality, were found in scoping trials to have modest iodide loading capacities [72.9 ± 5 mg(I)/g, 119.5 ± 5 g(I)/g]]. Loaded sorbents were encapsulated in a geopolymer (GP) matrix at a conservative 2 wt% loading of capture material to test whether a wasteform could be created. A Blast Furnace Slag:Portland Cement (BFS:PC) cement was created as a benchmark reference. Successful formation of both BFS:PC and GP wasteforms was achieved, but the silica matrix in the GP samples was found to break down due to the high pH (~ 14) of the fresh geopolymer paste. Bleed water from one of the GP samples was analysed showing formation of Ag2S.
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Acknowledgements
This work was funded under the £46m Advanced Fuel Cycle Programme as part of the Department for Business, Energy and Industrial Strategy’s (BEIS) £505m Energy Innovation Programme. On behalf of all authors, the corresponding author states that there is no conflict of interest. All data generated or analysed during this study are included in this published article and its supplementary information file.
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Kearney, S., Robshaw, T.J., Turner, J. et al. Encapsulation of iodine-loaded metallated silica materials by a geopolymer matrix. MRS Advances 7, 105–109 (2022). https://doi.org/10.1557/s43580-022-00207-4
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DOI: https://doi.org/10.1557/s43580-022-00207-4