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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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Jones, Cp
University of Bristol
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (11/11 displayed)
- 2022Examination of a Ferritic-Martensitic Steel following Irradiation and High Temperature Water Corrosion
- 2022Investigating the mechanical behaviour of Fukushima MCCI using synchrotron Xray tomography and digital volume correlationcitations
- 2021Investigating the microstructure and mechanical behaviour of simulant "lava-like" fuel containing materials from the Chernobyl reactor unit 4 meltdowncitations
- 2020Effect of crack-like defects on the fracture behaviour of Wire + Arc additively manufactured nickel-base Alloy 718citations
- 2016The crystallographic structure of the air-grown oxide on depleted uranium metalcitations
- 2015Structural deformation of metallic uranium surrounding hydride growth sitescitations
- 2015An investigation into heterogeneity in a single vein-type uranium ore depositcitations
- 2015The effects of metal surface geometry on the formation of uranium hydridecitations
- 2013A surface science study of the initial stages of hydrogen corrosion on uranium metal and the role played by grain microstructurecitations
- 2013Altering the hydriding behaviour of uranium metal by induced oxide penetration around carbo-nitride inclusionscitations
- 2011An improved method to identify grain boundary creep cavitation in 316H austenitic stainless steel
Places of action
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article
Investigating the microstructure and mechanical behaviour of simulant "lava-like" fuel containing materials from the Chernobyl reactor unit 4 meltdown
Abstract
Decommissioning of the damaged Chernobyl nuclear reactor Unit 4 is a top priority for the global community. Before such operations begin, it is crucial to understand the behaviour of the hazardous materials formed during the accident. Since those materials formed under extreme and mostly unquantified conditions, modelling alone is insufficient to accurately predict their physical, chemical and, predominantly, mechanical behaviour. Meanwhile, knowledge of the mechanical characteristics of those materials, such as their strength, is a priority before robotic systems are employed for retrieval and the force expected from them to be exerted is one of the key design questions. In this paper we target to measurement of the standard mechanical properties of the materials formed during the accident by testing small-scale, low radioactivity simulants. A combined methodology using Hertzian indentation, synchrotron X-ray tomography and digital volume correlation (DVC), was adopted to estimate the mechanical properties. Displacement fields around the Hertzian indentation, performed in-situ in a synchrotron, were measured by analysing tomograms with DVC. The load applied during the indentation, combined with fullfield displacement measured by DVC was used to estimate the mechanical properties, such as Young's modulus and Poisson's ratio of these hazardous materials.