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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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Henry, J.
Royal Academy of Engineering
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (21/21 displayed)
- 2021Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technology
- 2021Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technologycitations
- 2021Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technologycitations
- 2021Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation
- 2021Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon contentcitations
- 2021Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditionscitations
- 2021Fabrication routes for advanced first wall design alternatives
- 2021Fabrication routes for advanced first wall design alternativescitations
- 2020Bio-inspired non-self-similar hierarchical microstructures for damage tolerancecitations
- 2018Thermally Deposited Sb2S3: Bi Thin Films for Solar Cell Absorbercitations
- 2018Radiation-induced bcc-fcc phase transformation in a Fe-3%Ni alloycitations
- 2018Radiation-induced bcc-fcc phase transformation in a Fe-3percentNi alloy
- 2017Virtual testing framework for hybrid aligned discontinuous compositescitations
- 2016Effect of chromium on void swelling in ion irradiated high purity Fe–Cr alloyscitations
- 2016Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature servicecitations
- 2014Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe-Cr alloyscitations
- 2013He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe-5.40 wt.% Cr: A transmission electron microscopy studycitations
- 2013Single- and dual-beam in situ irradiations of high-purity iron in a transmission electron microscope: Effects of heavy ion irradiation and helium injectioncitations
- 2011Dual-beam irradiation of α-iron: Heterogeneous bubble formation on dislocation loopscitations
- 2008Tensile behaviour of 9Cr–1Mo tempered martensitic steels irradiated up to 20 dpa in a spallation environmentcitations
- 2006Assessment of the lifetime of the beam window of the MEGAPIE target liquid metal container
Places of action
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article
Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technology
Abstract
A major part in the EUROfusion materials research program is dedicated to characterize and quantify nuclear fusion specific neutron damage in structural materials. While the majority of irradiation data gives a relatively clear view on the displacement damage, the effect of transmutation – i.e. especially hydrogen and helium production in steels – is not yet explored very well. However, few available results indicate that EUROFER-type steels will reach their operating limit as soon as the formation of helium bubbles reaches a critical amount or size. At that point, the material would fail due to embrittlement at the considered load.This paper presents a strategy for the mitigation of the before-mentioned problem using the following facts:• the neutron dose and related transmutation rate decreases quickly inside the first wall, that is, only a plasma-near area is extremely loaded• nanostructured oxide dispersion strengthened (ODS) steels may have an enormous trapping effect on helium and hydrogen, which would suppress the formation of large helium bubbles• compared to conventional steels, ODS steels show improved irradiation tensile ductility and creep strengthIn summary, producing the plasma facing, highly neutron and heat loaded part of blankets by an ODS steel, while using EUROFER97 for everything else, would allow a higher heat flux as well as a longer operating period.Consequently, we (1) developed and produced 14 % Cr ferritic ODS steel plates. (2) We fabricated a mockup with 5 cooling channels and a plated first wall of ODS steel, using the same production processes as for a real component. And finally, (3) we performed high heat flux tests in the HELOKA facility (Helium Loop Karlsruhe at KIT) applying short and up to 2 h long pulses, in which the operating temperature limit for EUROFER97 (i.e., 550 °C) was finally exceeded by 100 K. Thereafter, microstructure and defect analyses did not reveal defects or recognizable damage. Only a heat affected zone in the EUROFER/ODS steel interface could be detected. This demonstrates that the use of ODS steel could make a decisive difference in the future design and performance of breeding blankets.