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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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Harrison, Robert W.
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Topics
Publications (13/13 displayed)
- 2023Microstructure and radiation tolerance of molybdenum-rich glass composite nuclear waste formscitations
- 2023In situ TEM study of heavy-ion irradiation-induced amorphisation and electron beam-induced recrystallisation in powellite (CaMoO4)citations
- 2022Hydrotalcite colloid stability and interactions with uranium(VI) at neutral to alkaline pH.citations
- 2019Chemical effects on He bubble superlattice formation in high entropy alloyscitations
- 2019Local chemical instabilities in 20Cr-25Ni Nb-stabilised austenitic stainless steel induced by proton irradiationcitations
- 2019Evolution of radiation-induced lattice defects in 20/25 Nb-stabilised austenitic stainless steel during in-situ proton irradiationcitations
- 2019Intermetallic Re phases formed in ion irradiated WRe alloycitations
- 2019A Transmission Electron Microscopy study of the neutron-irradiation response of Ti-based MAX phases at high temperaturescitations
- 2018Enhanced radiation tolerance of tungsten nanoparticles to He ion irradiationcitations
- 2017Thermal Evolution of the Proton Irradiated Structure in Tungsten–5 wt% Tantalumcitations
- 2016Diffusion-based and creep continuum damage modelling of crack formation during high temperature oxidation of ZrN ceramicscitations
- 2014Nuclear Applications for Ultra-High Temperature Ceramics and MAX Phasescitations
- 2014Thermophysical characterisation of ZrCxNy ceramics fabricated via carbothermic reduction-nitridationcitations
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article
Microstructure and radiation tolerance of molybdenum-rich glass composite nuclear waste forms
Abstract
Non-active molybdenum-rich Ca/Zn glass composite materials (GCM) were prepared on the Vitrification Test Rig (VTR) in the UK. The GCM samples were subjected to Ni and Au ion irradiations to simulate the effects of alpha recoil damage and to determine how the crystallinity characteristics might affect the overall radiation tolerance of high-level wastes (HLW) generated during post-operational clean-out (POCO) operations at the Sellafield nuclear site. The typical crystal phases identified in the GCM were: powellite, ruthenium dioxide, zincochromite, zircon and cerianite. Gadolinium (a proxy for radioactive elements) accumulated mainly in powellite, zircon and cerianite crystals. Scanning electron microscopy (SEM), electron backscatter diffraction (EBSD) and grazing incidence X-ray diffraction (GIXRD) analyses showed that cerianite is a highly radiation-tolerant phase, whereas powellite and zircon became amorphous and swelled considerably after the Ni and Au ion irradiations. This research shows the first evidence of powellite amorphisation under heavy-ion irradiation and suggests that powellite is susceptible to amorphisation by alpha recoils in HLW materials, in contrast to previous findings. The evolution of cooling-related and irradiation-induced microcracks is also described. In HLW glass composite materials, the formation of microcracks is expected in the middle of the canister, where relatively large powellite and zircon crystals appear.