A review of irradiation-induced hardening in FeCrAl alloy systems for accident-tolerant fuel cladding

Despite nuclear energy being a clean, sustainable source, its safety is a major concern, especially after the Chernobyl and Fukushima accidents. Designing accident-tolerant fuel (ATF) clad materials is a key solution. This review examines the development and behavior of FeCrAl alloys, a promising ATF cladding candidate, under irradiation. FeCrAl alloys show excellent resistance to high-temperature corrosion and oxidation, but irradiation can significantly alter their mechanical properties. This paper consolidates experimental and theoretical studies on irradiation hardening in FeCrAl alloys, highlighting dislocation loops and Cr-rich α’ precipitates as primary hardening contributors. It discusses compositional adjustments, such as adding oxide dispersion strengthening (ODS) materials, and evaluates advanced techniques to mitigate irradiation-induced damage and improve alloy performance. Theoretical frameworks of irradiation hardening and computer simulation methods are overviewed. This review provides a comprehensive understanding of irradiation hardening mechanisms in FeCrAl alloys and suggests future research directions for enhancing nuclear reactor safety and efficiency.