High-temperature oxidation of non-zirconium materials for ATF

Non-zirconium materials, such as silicon carbide (SiC) and FeCrAl alloys, have attracted interest for developing Accident-Tolerant Fuel (ATF) cladding systems owing to their superior hightemperature oxidation resistance. SiC offers excellent thermal stability, high-temperature properties, irradiation tolerance, and low activation, while FeCrAl alloys provide outstanding oxidation resistance in steam and air through a stable alumina (Al2O3) layer. This study examines their oxidation behavior under simulated severe-accident conditions. Microstructural changes and mechanical integrity after exposure were analyzed using scanning electron microscopy (SEM) and ring compression tests (RCT). The analysis revealed material-specific strengths and limitations, emphasizing the role of temperature and oxidation environment.

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Publication Details

Journal
Acta Polytechnica CTU Proceedings
Published
2025-12-29
DOI
https://doi.org/10.14311/app.2025.55.0016
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.00

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article

High-temperature oxidation of non-zirconium materials for ATF

Claudia Aparicio, Martin Ševeček, Alžběta Endrychová, David Rada et al.
Acta Polytechnica CTU Proceedings
Nuclear Materials and Properties
article

High-temperature oxidation of non-zirconium materials for ATF

Claudia Aparicio, Martin Ševeček, Alžběta Endrychová, David Rada, Jakub Krejčí, Martin Cesnek
article en

Abstract

Non-zirconium materials, such as silicon carbide (SiC) and FeCrAl alloys, have attracted interest for developing Accident-Tolerant Fuel (ATF) cladding systems owing to their superior hightemperature oxidation resistance. SiC offers excellent thermal stability, high-temperature properties, irradiation tolerance, and low activation, while FeCrAl alloys provide outstanding oxidation resistance in steam and air through a stable alumina (Al2O3) layer. This study examines their oxidation behavior under simulated severe-accident conditions. Microstructural changes and mechanical integrity after exposure were analyzed using scanning electron microscopy (SEM) and ring compression tests (RCT). The analysis revealed material-specific strengths and limitations, emphasizing the role of temperature and oxidation environment.

Acta Polytechnica CTU ProceedingsVol. 55
Ujp Praha (Czechia) (CZ), Research Centre Rez (CZ), Czech Technical University in Prague (CZ)
Technology Agency of the Czech Republic, Ministerstvo Školství, Mládeže a Tělovýchovy
Openalex Percentile: Top 46%
Nuclear Materials and Properties
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