Advances and challenges of oxide dispersion-strengthened Mo alloys for nuclear applications: A review

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Authors: Liying Yao, Yimin Gao, Zongda Yang, Yosuke Nishimura, Hiroaki Abe, Hui Wang, Yanchao Li, G.J. Zhang
Cited by: 3
References: 80

Abstract

Molybdenum (Mo) alloys are promising cladding materials for advanced nuclear reactors due to their high melting point, excellent thermal conductivity, low expansion coefficient, and good compatibility with liquid metals. However, their practical use in nuclear energy systems is limited by several drawbacks, including room-temperature embrittlement, irradiation embrittlement, and poor oxidation resistance. To address these challenges, the strategy of achieving intragranular dispersion of oxide nanoparticles while enhancing oxide/matrix interfacial bonding has been employed. This review summarizes the current progress on oxide dispersion-strengthened (ODS) Mo alloys in terms of fabrication technologies, microstructure characteristics, mechanical properties, irradiation resistance, and oxidation behavior. Although the development of ODS-Mo alloys for nuclear applications has not been fully explored, the current research findings provide a good basis for understanding the relationship between fabrication technologies, microstructure, and performance. Further efforts should focus on elucidating degradation mechanisms and characterization of material properties under conditions more closely simulating actual reactor environments.

Fields of Study & Subjects

Fusion materials and technologies Nuclear Materials and Properties Advanced materials and composites

Publication details

Journal / source
Journal of Materials Research and Technology
Publisher
Elsevier BV
Volume
40
Pages
2857–2868
Publication date
1 January 2026
Language
EN