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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, Graeme
University of Huddersfield
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (26/26 displayed)
- 2024Investigation of the microstructure of He+ ion-irradiated TiBe12 and CrBe12 using ex-situ transmission electron microscopycitations
- 2023From high-entropy alloys to high-entropy ceramics : The radiation-resistant highly concentrated refractory carbide (CrNbTaTiW)Ccitations
- 2022Investigating Irradiation Creep of Zircaloy-4 Using In-Situ Proton Irradiation and Transmission Electron Microscopy
- 2022Observations of He Platelets During He Ion Irradiation in 3C SiCcitations
- 2021Nanostructuring Germanium Nanowires by In Situ TEM Ion Irradiationcitations
- 2021Helium implantation damage resistance in nanocrystalline W-Ta-V-Cr high entropy alloyscitations
- 2021Comparative irradiation response of an austenitic stainless steel with its high-entropy alloy counterpartcitations
- 2020Prototypic Lightweight Alloy Design for Stellar-Radiation Environmentscitations
- 2020Low-temperature investigations of ion-induced amorphisation in silicon carbide nanowhiskers under helium irradiationcitations
- 2020Synthesis and in situ ion irradiation of A-site deficient zirconate perovskite ceramicscitations
- 2020In-Situ Helium Implantation and TEM Investigation of Radiation Tolerance to Helium Bubble Damage in Equiaxed Nanocrystalline Tungsten and Ultrafine Tungsten-TiC Alloycitations
- 2020Radiation Damage Suppression in AISI-316 Steel Nanoparticles: Implications for the Design of Future Nuclear Materialscitations
- 2019Thermodynamics of an austenitic stainless steel (AISI-348) under in situ TEM heavy ion irradiationcitations
- 2019Radiation-induced precipitation with concurrent bubbles formation in an austenitic stainless steel (AISI-348)citations
- 2019Understanding amorphization mechanisms using ion irradiation in situ a TEM and 3D damage reconstructioncitations
- 2019Thermal stability and irradiation response of nanocrystalline CoCrCuFeNi high-entropy alloycitations
- 2019Direct Comparison of Tungsten Nanoparticles and Foils under Helium Irradiation at High Temperatures Studied via In-Situ Transmission Electron Microscopy
- 2019Investigating sluggish diffusion in a concentrated solid solution alloy using ion irradiation with in situ TEMcitations
- 2018Energetic particle irradiation study of TiN coatingscitations
- 2017Grain size threshold for enhanced irradiation resistance in nanocrystalline and ultrafine tungstencitations
- 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
- 2014In-situ TEM observation of the response of ultrafine- and nanocrystalline-grained tungsten to extreme irradiation environmentscitations
- 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
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article
Investigation of the microstructure of He+ ion-irradiated TiBe12 and CrBe12 using ex-situ transmission electron microscopy
Abstract
<p>Titanium and chromium beryllides, TiBe<sub>12</sub> and CrBe<sub>12</sub>, are materials of potential future importance as neutron multipliers for tritium breeding in nuclear fusion reactors. Beryllium experiences extremely high transmutation according to a n →2n transmutation reaction in which both tritium and helium are produced, which normally form bubbles in solids at the relevant concentration range. Neutron irradiation from the fusion plasma also introduces point defects into solids. The ensuing effect of this environment on the beryllides’ microstructure is poorly characterised, but important for understanding beryllides’ mechanical properties and their evolution in the irradiative environment inside a fusion reactor. This study is intended to initially determine and describe the microstructural features that occur in TiBe<sub>12</sub> and CrBe<sub>12</sub> when He and fast-particle-induced point defects have been introduced at fusion reactor neutron breeder relevant temperatures. In this study, beryllide samples were implanted with 300 kV He at a range of temperatures between 387 and 900 °C, sectioned down through the implantation surface with a focused ion beam post-irradiation, and the resulting microstructures examined using transmission electron microscopy, electron-dispersive X-ray spectroscopy (EDX/EDS) and precession diffraction mapping. Nanometre-scale bubbles grew in both TiBe<sub>12</sub> and CrBe<sub>12</sub> at 600 °C and larger (100+ nm) bubbles, some faceted, grew at 900 °C. Some bubbles in CrBe<sub>12</sub> were lined with Cr, with some of the Cr oxidised. TiBe<sub>12</sub> developed planar faults, on {110} planes at 600 °C and below but on to {111} at 900 °C. Faults were preferentially associated with large bubbles. The displacement vectors of faults on the {110} planes had some commonality with previous studies that found displacement vectors of the two types R=[Formula presented]〈110〉; the present study also found faults that did not match either previously found type. CrBe<sub>12</sub> also developed planar faults but the appearance of these was quite different from the typical striped appearance of planar stacking faults and their nature remains unknown. Oxide particles from manufacture were found in both beryllides, most prominently in CrBe<sub>12.</sub></p>