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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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Donnelly, Stephen
University of Huddersfield
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (18/18 displayed)
- 2024Investigation of the microstructure of He+ ion-irradiated TiBe12 and CrBe12 using ex-situ transmission electron microscopycitations
- 2022Observations of He Platelets During He Ion Irradiation in 3C SiCcitations
- 2021Nanostructuring Germanium Nanowires by In Situ TEM Ion Irradiationcitations
- 2021Comparative irradiation response of an austenitic stainless steel with its high-entropy alloy counterpartcitations
- 2020Low-temperature investigations of ion-induced amorphisation in silicon carbide nanowhiskers under helium irradiationcitations
- 2020Effect of decades of corrosion on the microstructure of altered glasses and their radiation stabilitycitations
- 2020Radiation Damage Suppression in AISI-316 Steel Nanoparticles: Implications for the Design of Future Nuclear Materialscitations
- 2019Local chemical instabilities in 20Cr-25Ni Nb-stabilised austenitic stainless steel induced by proton irradiationcitations
- 2019Understanding amorphization mechanisms using ion irradiation in situ a TEM and 3D damage reconstructioncitations
- 2019Direct Comparison of Tungsten Nanoparticles and Foils under Helium Irradiation at High Temperatures Studied via In-Situ Transmission Electron Microscopy
- 2018Synthesis and characterisation of high-entropy alloy thin films as candidates for coating nuclear fuel cladding alloyscitations
- 2016Preliminary assessment of the irradiation behaviour of the FeCrMnNi High-Entropy Alloy for nuclear applications
- 2014In-situ TEM studies of ion-irradiation induced bubble development and mechanical deformation in model nuclear materialscitations
- 2014Helium bubble formation in nuclear glass by in-situ TEM ion implantationcitations
- 2014In-situ observation and atomic resolution imaging of the ion irradiation induced amorphisation of graphenecitations
- 2008A cross-sectional transmission electron microscopy study of iron recovered from a laser-heated diamond anvil cellcitations
- 2006Single ion-induced amorphous zones in silicon
- 2005Study of nanocrystalline TiN/Si3N4 thin films deposited using a dual ion beam methodcitations
Places of action
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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.