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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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Greaves, G.
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (10/10 displayed)
- 2021<i>In situ</i> He<SUP>+</SUP> irradiation of the double solid solution (Ti<sub>0.5</sub>,Zr<sub>0.5</sub>)<sub>2</sub>(Al<sub>0.5</sub>,Sn<sub>0.5</sub>)C MAX phase: Defect evolution in the 350-800 °C temperature rangecitations
- 2019Chemical effects on He bubble superlattice formation in high entropy alloyscitations
- 2019A candidate accident tolerant fuel system based on a highly concentrated alloy thin filmcitations
- 2019Intermetallic Re phases formed in ion irradiated WRe alloycitations
- 2019New Microscope and Ion Accelerators for Materials Investigations (MIAMI-2) system at the University of Huddersfieldcitations
- 2017Effect of He implantation on the microstructure of zircaloy-4 studied using in situ TEMcitations
- 2016Hybrid glasses from strong and fragile metal-organic framework liquids.citations
- 2014Helium bubble formation in nuclear glass by in-situ TEM ion implantationcitations
- 2014Kink Band Formation in Graphite under Ion Irradiation at 100 and 298Kcitations
- 2012A transmission electron microscopy study of inert gases in silicon and iron
Places of action
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article
Effect of He implantation on the microstructure of zircaloy-4 studied using in situ TEM
Abstract
Zirconium alloys are of great importance to the nuclear industry as they have been widely used as cladding materials in light-water reactors since the 1960s. This work examines the behaviour of these alloys under He ion implantation for the purposes of developing understanding of the fundamental processes behind their response to irradiation. Characterization of zircaloy-4 samples using TEM with in situ 6 keV He irradiation up to a fluence of 2.7×1017ions·cm−2in the temperature range of 298 to 1148 K has been performed. Ordered arrays of He bubbles were observed at 473 and 1148 K at a fluence of 1.7×1017ions·cm−2in αZr, the hexagonal compact (HCP) and in βZr, the body centred cubic (BCC) phases, respectively. In addition, the dissolution behaviour of cubic Zr hydrides under He irradiation has been investigated.