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

Tangirbergen A. Amangeldi N. Revankar S.T. Yergaliuly G.
1 December 2024 Elsevier Ltd

Nuclear Engineering and Design
2024 #429

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.

Accident tolerant fuel (ATF) cladding , DFT , FeCrAl alloy , Irradaiton hardening , Nanoindentation test , Oxide dispersion strengthening (ODS)

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L.N. Gumilyov, Eurasian National University, Astana, 010000, Kazakhstan
Purdue University, School of Nuclear Engineering, West Lafayette, 47907, IN, United States
National Laboratory Astana, Nazarbayev University, Astana, 010000, Kazakhstan

L.N. Gumilyov
Purdue University
National Laboratory Astana

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