| People | Locations | Statistics |
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| Naji, M. |
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| Motta, Antonella |
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| Aletan, Dirar |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Kononenko, Denys |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Bih, L. |
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| Casati, R. |
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| Muller, Hermance |
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| Kočí, Jan | Prague |
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| Šuljagić, Marija |
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| Kalteremidou, Kalliopi-Artemi | Brussels |
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| Azam, Siraj |
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| Ospanova, Alyiya |
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| Blanpain, Bart |
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| Ali, M. A. |
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| Popa, V. |
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| Rančić, M. |
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| Ollier, Nadège |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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| Rignanese, Gian-Marco |
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Abram, Timothy
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (12/12 displayed)
- 2024Development of high-temperature-steam Resistant UN via the addition of UB 2
- 2024Development of high-temperature-steam Resistant UN via the addition of UB2
- 2023Fabrication and thermal conductivity of UN-UB2 composites fabricated by spark plasma sinteringcitations
- 2022Development and Comparison of Field Assisted Sintering Techniques to Densify CeO2 Ceramicscitations
- 2020Steam Performance of UB2/U3Si2 Composite Fuel Pellets, Compared to U3Si2 Reference Behaviourcitations
- 2019A high density composite fuel with integrated burnable absorber: U3Si2-UB2citations
- 2018The use of gadolinium as a burnable poison within U 3 Si 2 fuel pelletscitations
- 2018The use of gadolinium as a burnable poison within U3Si2 fuel pelletscitations
- 2016Selective area laser deposition of FCC beta silicon carbide
- 2013The chemical durability of glass and graphite-glass composite doped with cesium oxidecitations
- 2012Thermal Analysis and Immobilisation of Spent Ion Exchange Resin in Borosilicate Glasscitations
- 2008Structure and mechanical properties of pyrolytic carbon produced by fluidized bed chemical vapor depositioncitations
Places of action
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article
Thermal Analysis and Immobilisation of Spent Ion Exchange Resin in Borosilicate Glass
Abstract
The underground disposal of waste arising from the nuclear industry needs constant evaluation in order to improve upon it through minimizing the volume and cost by reducing the amount of glass used without compromising the safety of any leakage from the radioactive waste form. The immobilization of the spent resin (NRW-40) in borosilicate glass was investigated to meet the acceptance criteria for disposal of nuclear waste. The organic mixed bed resin in granular form was used as a waste target. The analysis of surrogate resin doped with radioactive and non-radioactive cesium (Cs) and cobalt (Co) was carried out to investigate their thermal and chemical properties and their compatibility with an alkaline borosilicate glass. The thermal analysis indicates that the structural damage caused by 1 mSv gamma radiation to the radioactive resin has altered its properties in comparison with the non-radioactive resin, same amount of cesium (8.88 wt%) and cobalt (1.88 wt%) were used in both resins. The immobilization of residue shows that the excess sulfur in the residue caused phase crystallization in the final glass matrix. It was found that the volatilization of Cs-137 and Co-60 from the successful radioactive resin-glass matrix (HG-3-IER-500) were more than that in the non-radioactive resin-glass matrix (HG-3-IEX-500). The study demonstrates comprehensive experimental and analytical works and shows that it is possible to minimise the volume of the waste while keeping the required safety levels, however further research needs to be carried out in this area.