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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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Race, Christopher P.
University of Sheffield
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (17/17 displayed)
- 2024Molecular dynamics simulations of neutron induced collision cascades in Zr — Statistical modelling of irradiation damage and potential applicationscitations
- 2024Fractional densities and character of dislocations in different slip modes from powder diffraction patternscitations
- 2023Interaction of monoclinic ZrO2 grain boundaries with oxygen vacancies, Sn and Nb - implications for the corrosion of Zr alloy fuel cladding
- 2023Dislocation density transients and saturation in irradiated zirconiumcitations
- 2023Breakaway Growth Modeling of Zirconium under Irradiation: The Importance of the Formation of a-Loop Layerscitations
- 2022Simulating intergranular hydrogen enhanced decohesion in aluminium using density functional theorycitations
- 2022A novel method for radial hydride analysis in zirconium alloyscitations
- 2022Breakaway Growth Modeling of Zirconium under Irradiation: The Importance of the Formation of a-Loop Layerscitations
- 2021The Importance of Substrate Grain Orientation on Local Oxide Texture and Corrosion Performance in α-Zr Alloyscitations
- 2021The Importance of Substrate Grain Orientation on Local Oxide Texture and Corrosion Performance in α-Zr Alloyscitations
- 2021Synthesis of new M-layer solid-solution 312 MAX phases (Ta1−xTix)3AlC2 (x = 0.4, 0.62, 0.75, 0.91 or 0.95), and their corresponding MXenescitations
- 2020Modelling Hydrogen Embrittlement using Density Functional Theory: A theoretical approach to understanding environmentally assisted cracking in 7xxx series aluminium alloyscitations
- 2019Imaging three-dimensional elemental inhomogeneity in Pt–Ni nanoparticles using spectroscopic single particle reconstructioncitations
- 2019The effect of irradiation temperature on damage structures in proton-irradiated zirconium alloyscitations
- 2018The Effect of Iron on Dislocation Evolution in Model and Commercial Zirconium Alloyscitations
- 2018Advanced 3D characterisation of iodine induced stress corrosion cracks in zirconium alloyscitations
- 2017Investigating the thermal stability of irradiation-induced damage in a zirconium alloy with novel in situ techniquescitations
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article
The effect of irradiation temperature on damage structures in proton-irradiated zirconium alloys
Abstract
A study into the effects of irradiation temperature on the damage structures that form during proton-irradiation has been carried out on two commercial Zr alloys in order to develop a more mechanistic understanding of the effect of niobium on dislocation loop evolution. The two Zr alloys (Zircaloy-2 and Low-Sn ZIRLOTM) were proton irradiated to a damage level of ~2 dpa at 280°C, 350°C and 450°C. Detailed dislocation analysis was carried out using on-axis bright-field scanning transmission electron microscopy combined with spectral imaging and synchrotron x-ray line profile analysis. The analysis revealed a significant difference in the effect of irradiation temperature on loop size between the two alloys. In the case of the Nb-free Zr-alloy (Zircaloy-2), an increase in irradiation temperature results in a marked increase in a-loop diameter, by a factor of ~7.5 from 280 to 450C, and a stark decrease in the dislocation line density. In contrast, the Nb-containing Zr-alloy (Low-Sn ZIRLOTM) showed very little variation of loop size and line density over the same radiation temperature range. The STEM-based spectral imaging revealed irradiation-induced nano-clustering found throughout the matrix in Low-Sn ZIRLOTM, which is not present in the case of Zircaloy-2. Therefore, it is proposed that Nb plays a crucial role in the evolution of dislocation loops in Zr through the formation of irradiation precipitation throughout the matrix.