| People | Locations | Statistics |
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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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Martin, Tomas L.
University of Bristol
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (38/38 displayed)
- 2024Microstructural Analysis of Ex-Service Neutron Irradiated Stainless Steel Nuclear Fuel Cladding by High-Speed AFM
- 2024The Transient Thermal Ageing of Eurofer 97 by Mitigated Plasma Disruptions
- 2024Creep Cavitation Imaging and Analysis in 9%Cr-1%Mo P91 Steels
- 2024Under the microscope:Reduced Activation Ferritic Martensitic Steel Eurofer-97 Following Ion‑Irradiation and High‑Temperature High‑Pressure Water Exposure
- 2024A correlative approach to evaluating the links between local microstructural parameters and creep initiated cavitiescitations
- 2024Effect of grain boundary misorientation and carbide precipitation on damage initiationcitations
- 2024Creep cavitation evolution in polycrystalline copper under conditions of stress relaxationcitations
- 2023A novel approach for evaluating creep damage and cavitation in copper bicrystals subject to constant loadcitations
- 2023Microstructural modelling and characterisation of laser-keyhole welded Eurofer 97citations
- 2022Examination of a Ferritic-Martensitic Steel following Irradiation and High Temperature Water Corrosion
- 2022Stress Corrosion Cracking in Stainless Steelscitations
- 2021The Effects of Fusion Reactor Thermal Transients on the Microstructure of Eurofer-97 Steelcitations
- 2021Observation of stress corrosion cracking using real-time in situ high-speed atomic force microscopy and correlative techniquescitations
- 2021Comparing Techniques for Quantification of Creep Cavities
- 2021The role of grain boundary ferrite evolution and thermal aging on creep cavitation of type 316H austenitic stainless steelcitations
- 2021Sample Preparation Methods for Optimal HS-AFM Analysis:Duplex Stainless Steelcitations
- 2021Sample Preparation Methods for Optimal HS-AFM Analysiscitations
- 2020The role of niobium carbides in the localised corrosion initiation of 20Cr-25Ni-Nb advanced gas-cooled reactor fuel claddingcitations
- 2020The role of grain boundary orientation and secondary phases in creep cavity nucleation of a 316h boiler headercitations
- 2020The effect of sodium hydroxide on niobium carbide precipitates in thermally sensitised 20Cr-25Ni-Nb austenitic stainless steelcitations
- 2019The role of replicated service atmosphere on deformation and fracture behaviour of carburised AISI type 316H steelcitations
- 2019Chemistry and corrosion research and development for the water cooling circuits of European DEMOcitations
- 2019Development of Fatigue Testing System for in-situ Observation of Stainless Steel 316 by HS-AFM & SEMcitations
- 2019Atom probe tomography of Au-Cu bimetallic nanoparticles synthesized by inert gas condensationcitations
- 2018The effect of phase chemistry on the extent of strengthening mechanisms in model Ni-Cr-Al-Ti-Mo based superalloyscitations
- 2018A novel ultra-high strength maraging steel with balanced ductility and creep resistance achieved by nanoscale β-NiAl and Laves phase precipitatescitations
- 2018Understanding irradiation-induced nanoprecipitation in zirconium alloys using parallel TEM and APTcitations
- 2018A study of dynamic nanoscale corrosion initiation events by HS-AFMcitations
- 2018Chemistry and Corrosion in the irradiated cooling circuits of a prototype fusion power station
- 2017A SANS and APT study of precipitate evolution and strengthening in a maraging steelcitations
- 2017Precipitation in a novel maraging steel F1Ecitations
- 2016Atomic-scale Studies of Uranium Oxidation and Corrosion by Water Vapourcitations
- 2016Continuous and discontinuous precipitation in Fe-1 at.%Cr-1 at.%Mo alloy upon nitriding; crystal structure and composition of ternary nitridescitations
- 2016Insights into microstructural interfaces in aerospace alloys characterised by atom probe tomographycitations
- 2015Light Metals on Oxygen-Terminated Diamond (100)citations
- 2015Practical Issues for Atom Probe Tomography Analysis of III-Nitride Semiconductor Materials.
- 2015Practical Issues for Atom Probe Tomography Analysis of III-Nitride Semiconductor Materialscitations
- 2014A New Polycrystalline Co-Ni Superalloycitations
Places of action
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conferencepaper
Chemistry and Corrosion in the irradiated cooling circuits of a prototype fusion power station
Abstract
Irradiated water cooling circuits in the EU DEMO fusion reactor will experience a combination of conditions which has the potential to influence the performance of coolant-facing structural materials. In common with LWR primary circuits, heat transfer plant in the Breeding Blanket, Divertor and First Wall locations will be exposed to high temperature, high pressure water within an intense neutron and beta/gamma irradiation field. The neutron energy of 14 MeV is significantly higher than thermal fission plant and components will experience significant fluences over their expected plant lives. In addition, the influence of strong magnetic fields and highly tritiated water (due to tritium fuel breeding) are possible exacerbating factors which are less well understood. In order to ensure that the possible effects of these parameters are adequately controlled, a conceptual water chemistry programme has previously been proposed and is now under development.<br/><br/>This paper outlines several strands of work that are ongoing to address these challenges within a wider technology development programme under the EUROfusion framework, and their implications to the further chemistry programme development:<br/><br/>• Review of relevant operating experience from fission LWR plant<br/>• Radiolysis modelling to assess options for suppression of oxidising species under high energy neutron irradiation<br/>• High temperature water corrosion testing for chemistry optimisation<br/>• Influence of intense magnetic fields and tritium on high temperature corrosion<br/>• Approaches for assessing environmental degradation of highly irradiated new materials<br/><br/>The project aims to further transfer experience from the worldwide fission power station fleet as well as being a strategic theme for capability development in the UK with relevance to near term new build and small modular reactor designs.<br/>