Thermal treatment of nuclear fuel-containing Magnox sludge radioactive waste
| Autor: | Neil C. Hyatt, Daniel J. Bailey, Sean T. Barlow, Lewis R. Blackburn, Claire L. Corkhill, Martin C. Stennett, Sean P. Morgan, Russell J. Hand, Adam J. Fisher |
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| Rok vydání: | 2021 |
| Předmět: |
Nuclear and High Energy Physics
Materials science Nuclear fuel Borosilicate glass Metallurgy Radioactive waste chemistry.chemical_element 02 engineering and technology Thermal treatment Uranium 021001 nanoscience & nanotechnology 01 natural sciences 010305 fluids & plasmas High-level waste Nuclear Energy and Engineering chemistry Hazardous waste 0103 physical sciences General Materials Science Vitrification 0210 nano-technology |
| Zdroj: | Journal of Nuclear Materials. 552:152965 |
| ISSN: | 0022-3115 |
| DOI: | 10.1016/j.jnucmat.2021.152965 |
| Popis: | Magnesium aluminosilicate and magnesium borosilicate glass formulations were developed and evaluated for the immobilisation of the radioactive waste known as Magnox sludge. Glass compositions were synthesised using two simplified bounding waste simulants, including corroded and metallic uranium and magnesium at waste loadings of up to 50 wt.%. The glasses immobilising corroded simulant waste formed generally homogenous and fully amorphous glasses, while those immobilising metallic wastes contained crystallites of UO2 and U3O8. Uranium speciation within the glass was investigated by micro-focus X-ray absorption near edge spectroscopy and it was shown that the borosilicate glass compositions were characterised by a slightly lower mean uranium oxidation state than the aluminosilicate counterparts. This had an impact upon the durability, and uranium within glasses of higher mean oxidation states was dissolved more readily. All material showed dissolution rates that were comparable with simulant high level radioactive waste glasses, while the borosilicate-based formulations melted at a temperature suitable for modern vitrification technologies used in radioactive waste applications. These data highlight the potential for vitrification of hazardous radioactive Magnox sludge waste in borosilicate or aluminosilicate glass formulations, with the potential to achieve >95 % reduction in conditioned waste volume over the current baseline plan. |
| Databáze: | OpenAIRE |
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