| 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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Steinbrück, Martin
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (35/35 displayed)
- 2024Decoding the oxidation mechanism of Zircaloy-4 via in situ synchrotron X-ray diffraction and computational elucidation
- 2024Phase formation, structure and properties of quaternary MAX phase thin films in the Cr-V-C-Al system: A combinatorial study
- 2023Synthesis of V2AlC thin films by thermal annealing of nanoscale elemental multilayered precursors : Incorporation of layered Ar bubbles and impact on microstructure formationcitations
- 2023Synthesis of V$_{2}$AlC thin films by thermal annealing of nanoscale elemental multilayered precursors: Incorporation of layered Ar bubbles and impact on microstructure formation
- 2023Nitriding model for zirconium based fuel cladding in severe accident codescitations
- 2023Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment
- 2022Phase formation and thermal stability of quaternary MAX phase thin films in the Cr-V-C-Al system: an experimental combinatorial study
- 2022The Effect of Annealing Temperature on the Microstructure and Properties of Cr–C–Al Coatings on Zircaloy-4 for Accident-Tolerant Fuel (ATF) Applicationscitations
- 2022Oxidation of silicon carbide composites for nuclear applications at very high temperatures in steamcitations
- 2022Results of metallographic analysis of the QUENCH-20 bundle with B4C absorber
- 2022Results of metallographic analysis of the QUENCH-20 bundle with B₄C absorber
- 2021Development of Cr-C-Al based coatings for enhanced accident tolerant fuel (ATF) zirconium-based alloy cladding
- 2021High-temperature oxidation and hydrothermal corrosion of textured Cr$_{2}$AlC-based coatings on zirconium alloy fuel cladding
- 2020High-Temperature Oxidation of Chrome-Nickel Alloycitations
- 2020Investigation of corrosion and high temperature oxidation of promising ATF cladding materials in the framework of the Il trovatore project
- 2018High-temperature interaction of oxygen-preloaded Zr1Nb alloy with nitrogencitations
- 2018H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHYcitations
- 2018H2 PERMEATION BEHAVIOR OF Cr2AlC AND Ti2AlC MAX PHASE COATED ZIRCALOY-4 BY NEUTRON RADIOGRAPHYcitations
- 2018Magnetron-sputtered Al-containing MAX phase carbide thin films and their application as oxidation-resistant coatings
- 2017High-temperature interaction of oxygen-preloaded Zr1Nb alloy with nitrogen
- 2017Nanocrystalline diamond protects Zr cladding surface against oxygen and hydrogen uptake : Nuclear fuel durability enhancementcitations
- 2017Lessons learned from the QUENCH-LOCA experiments
- 2017Update of the QUENCH program
- 2017UK Research in LOCA-Related Activities and Co-operation with the Karlsruhe Research Centre - A Historical Perspective
- 2016Oxidation and hydrogen uptake during high-temperature reaction of zirconium alloys in steam-nitrogen mixtures
- 2016High-temperature oxidation of SiC-Ta-SiC sandwich cladding tubes in GFR atmosphere
- 2013Results of the QUENCH-16 Bundle Experiment on Air Ingress (KIT Scientific Reports ; 7634)
- 2012Oxidation of zirconium alloys in mixed atmospheres containing nitrogen
- 2012Selected aspects of materials behavior during severe nuclear accidents in nuclear reactors
- 2012High-temperature oxidation and mutual interactions of materials during severe nuclear accidents
- 2012Separate effects experiments in the framework of the QUENCH program at KIT
- 2012Materials behavior during the early phase of a severe nuclear accident
- 2011Results of Severe Fuel Damage Experiment QUENCH-15 with ZIRLO cladding tubes. (KIT Scientific Reports ; 7576)
- 2010Separate-effects tests on the investigation of high-temperature oxidation behavior and mechanical properties of Zircaloy-2 to be used in the SFP PWR tests : Report prepared in the framework of the OECD/NEA SFP Project
- 2007Prototypical experiments on air oxidation of zircaloy-4 at high temperatures
Places of action
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article
Oxidation of silicon carbide composites for nuclear applications at very high temperatures in steam
Abstract
Single-rod oxidation and quench experiments at very high temperatures in steam atmosphere were conducted with advanced, nuclear grade SiCf/SiC CMC cladding tube segments. A transient experiment was performed until severe local degradation of the sample at maximum temperature of approximately 1845 °C. The degradation was caused by complete consumption of the external CVD-SiC sealcoat, resulting in steam access to the fiber–matrix composite with less corrosion resistance. Approaching these very high temperatures was accompanied by accelerated gas release mainly of H2 and CO2, the formation of surface bubbles and white smoke. Three one-hour isothermal tests at 1700 °C in steam with final water flooding and one three-hour experiment with fast cool-down in Ar atmosphere were run under nominally identical conditions. All isothermally tested samples survived the tests without any macroscopic degradation. The mechanical performance of these quenched clad segments was not significantly affected, while maintaining a high capability to tolerate damages. Despite these harsh exposure conditions, load transfer between SiC fibers and matrix remained efficient, allowing the composites to accommodate deformation.