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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.
in Cooperation with on an Cooperation-Score of 37%
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
Enhanced radiation tolerance of tungsten nanoparticles to He ion irradiation
Abstract
Materials exposed to plasmas in magnetic confinement nuclear reactors will accumulate radiation-induced defects and energetically implanted gas atoms (from the plasma and transmutations), of which insoluble helium (He) is likely to be the most problematic. The large surface-area-to-volume ratio exhibited by nanoporous materials provides an unsaturable sink with the potential to continuously remove both point defects and He. This property enhances the possibilities for these materials to be tailored for high radiation-damage resistance. In order to explore the potential effect of this on the individual ligaments of nanoporous materials, we present results on the response of tungsten (W) nanoparticles (NPs) to 15 keV He ion irradiation. Tungsten foils and various sizes of NPs were ion irradiated concurrently and imaged in-situ via transmission electron microscopy at 750 °C. Helium bubbles were not observed in NPs with diameters less than 20 nm but did form in larger NPs and the foils. No dislocation loops or black spot damage were observed in any NPs up to 100 nm in diameter but were found to accumulate in the W foils. These results indicate that a nanoporous material, particularly one made up of ligaments with characteristic dimensions of 30 nm or less, is likely to exhibit significant resistance to He accumulation and structural damage and, therefore, be highly tolerant to radiation.