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Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings

Corrosion reviews, 2017-08, Vol.35 (3), p.141-165

2017

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Phenomenology of BWR fuel assembly degradation

Journal of nuclear materials, 2018-03, Vol.500, p.119-140

2018

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Oxidation behavior and microstructure evolution of alumina-forming austenitic & high entropy alloys in steam environment at 1200 °C

Corrosion science, 2020-07, Vol.170, p.108654, Article 108654

2020

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Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

Thermo, 2021-09, Vol.1 (2), p.151-167

2021

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High-temperature reaction of oxygen-stabilized α-Zr(O) with nitrogen

Journal of nuclear materials, 2014-04, Vol.447 (1-3), p.46-55

Steinbrück, Martin

2014

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Deposition, characterization and high-temperature steam oxidation behavior of single-phase Ti2AlC-coated Zircaloy-4

Corrosion science, 2018-05, Vol.135, p.87-98

2018

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High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment

Journal of nuclear materials, 2021-04, Vol.547, p.152806, Article 152806

2021

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Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures

Journal of nuclear materials, 2009-08, Vol.392 (3), p.531-544

Steinbrück, Martin

2009

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Experimental and modelling results of the QUENCH-20 experiment with BWR test bundle

Nuclear engineering and design, 2023-08, Vol.410, p.112391, Article 112391

2023

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Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam

Journal of nuclear materials, 2018-12, Vol.511, p.496-507

2018

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Eutectic reaction and oxidation behavior of Cr-coated Zircaloy-4 accident-tolerant fuel cladding under various heating rates

Journal of nuclear materials, 2023-09, Vol.583, p.154538, Article 154538

2023

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Decoding the oxidation mechanism of Zircaloy-4 via in situ synchrotron X-ray diffraction and computational elucidation

Journal of alloys and compounds, 2024-07, Vol.992, p.174554, Article 174554

2024

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Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release

Nuclear engineering and design, 2021-08, Vol.379, p.111267, Article 111267

2021

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High-temperature oxidation and hydrothermal corrosion of textured Cr2AlC-based coatings on zirconium alloy fuel cladding

Surface & coatings technology, 2021-08, Vol.419, p.127263, Article 127263

2021

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The oxidation behavior and reaction thermodynamics and kinetics of the Mg-X (X = Ca/Gd/Y) binary alloys

Corrosion science, 2023-12, Vol.225, p.111609, Article 111609

2023

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Oxidation of Zircaloy-4 in steam-nitrogen mixtures at 600–1200 °C

Journal of nuclear materials, 2017-07, Vol.490, p.226-237

2017

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Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment

Journal of nuclear materials, 2023-07, Vol.580 (C), p.154433, Article 154433

2023

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Phase formation, structure and properties of quaternary MAX phase thin films in the Cr-V-C-Al system: A combinatorial study

Journal of the European Ceramic Society, 2024-12, Vol.44 (15), p.116763, Article 116763

2024

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Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500 °C in steam

Journal of nuclear materials, 2022-06, Vol.564, p.153696, Article 153696

2022

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Influence of boron carbide on core degradation during severe accidents in LWRs

Annals of nuclear energy, 2014-02, Vol.64, p.43-49

Steinbrück, Martin

2014

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Synthesis of V2AlC thin films by thermal annealing of nanoscale elemental multilayered precursors: Incorporation of layered Ar bubbles and impact on microstructure formation

Applied surface science, 2023-08, Vol.629, p.157340, Article 157340

2023

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An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures

High temperature corrosion of materials, 2024, Vol.101 (4), p.621-647

2024

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Oxidation of Silicon Carbide Composites for Nuclear Applications at Very High Temperatures in Steam

Coatings (Basel), 2022-07, Vol.12 (7), p.875

2022

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Hafnium oxidation at high temperature in steam

Journal of nuclear materials, 2021-07, Vol.550, p.152901-14, Article 152901

2021

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Textured growth of polycrystalline MAX phase carbide coatings via thermal annealing of M/C/Al multilayers

Journal of vacuum science & technology. A, Vacuum, surfaces, and films, 2020-01, Vol.38 (1)

2020

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Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings

Phenomenology of BWR fuel assembly degradation

Oxidation behavior and microstructure evolution of alumina-forming austenitic & high entropy alloys in steam environment at 1200 °C

Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

High-temperature reaction of oxygen-stabilized α-Zr(O) with nitrogen

Deposition, characterization and high-temperature steam oxidation behavior of single-phase Ti2AlC-coated Zircaloy-4

High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment

Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures

Experimental and modelling results of the QUENCH-20 experiment with BWR test bundle

Influence of composition and heating schedules on compatibility of FeCrAl alloys with high-temperature steam

Eutectic reaction and oxidation behavior of Cr-coated Zircaloy-4 accident-tolerant fuel cladding under various heating rates

Decoding the oxidation mechanism of Zircaloy-4 via in situ synchrotron X-ray diffraction and computational elucidation

Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release

High-temperature oxidation and hydrothermal corrosion of textured Cr2AlC-based coatings on zirconium alloy fuel cladding

The oxidation behavior and reaction thermodynamics and kinetics of the Mg-X (X = Ca/Gd/Y) binary alloys

Oxidation of Zircaloy-4 in steam-nitrogen mixtures at 600–1200 °C

Analysis of iron-chromium-aluminum samples exposed to accident conditions followed by quench in the QUENCH-19 experiment

Phase formation, structure and properties of quaternary MAX phase thin films in the Cr-V-C-Al system: A combinatorial study

Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500 °C in steam

Influence of boron carbide on core degradation during severe accidents in LWRs

Synthesis of V2AlC thin films by thermal annealing of nanoscale elemental multilayered precursors: Incorporation of layered Ar bubbles and impact on microstructure formation

An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures

Oxidation of Silicon Carbide Composites for Nuclear Applications at Very High Temperatures in Steam

Hafnium oxidation at high temperature in steam

Textured growth of polycrystalline MAX phase carbide coatings via thermal annealing of M/C/Al multilayers

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