| 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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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
Local chemical instabilities in 20Cr-25Ni Nb-stabilised austenitic stainless steel induced by proton irradiation
Abstract
We have assessed the local solute redistribution at defect sinks in 20Cr-25Ni Nb-stabilised austenitic stainless steel after proton irradiation at three temperatures, i.e. 420, 460 and 500°C, up to a maximum damage level of 0.8dpa. This material is currently being used as cladding in advanced gas-cooled reactors (AGR), and potential local Cr depletions would compromise its resistance to intergranular corrosion attack during wet storage of spent fuel elements. Irradiation induces the depletion of Cr, Fe and, to a lesser extent, Mn from grain boundaries, whereas Ni and Si become enriched at those locations. The elemental profiles are symmetric and primarily W-shaped at 420°C, whereas at higher temperatures asymmetric and double-peaked profiles are also detected, most likely as a result of grain boundary migration. High-angle grain boundaries with a misorientation angle 􀀀40° become mobile at 460°C and especially at 500°C, and also experience a relatively large solute redistribution, with local Cr contents in a significant number of boundaries falling below 12wt.% and profile widths 􀀀100nm. However, coincidence site lattice boundaries (CSL) Σ3 boundaries prove to be resistant to Cr depletion and to boundary mobility. Local elemental patterns at radiationinduced dislocations seem to mimic those at grain boundaries, but do not trigger the formation of Ni3Si precipitates. Additionally, Ni and Si form a shell-like structure around the pre-existing Nb(C,N) precipitates, potentially leading to the transition into G-phase at higher damage levels.