This Oxide Dispersion Strengthened (ODS) ferritic steels are considered promising candidate materials for advanced nuclear reactor applications due to their superior high-temperature strength, creep resistance, radiation tolerance, and thermal stability. Future fusion and Generation-IV nuclear systems demand materials capable of operating under extreme conditions, including elevated temperatures, intense neutron irradiation, and high heat flux. Conventional ferritic and martensitic steels often exhibit degradation in mechanical properties and reduced creep resistance under such environments, highlighting the need for advanced materials like ODS steels. This study presents a comparative analysis of 12Cr and 14Cr ODS ferritic steels based on reported experimental investigations. The comparison includes chemical composition, microstructure, thermo-physical properties, mechanical performance, creep behavior, and high heat flux response. The incorporation of nano-sized Y₂O₃ particles significantly enhances strength, radiation resistance, and microstructural stability. The analysis reveals that both steels perform well under reactor-relevant conditions; however, 14Cr ODS steel generally exhibits higher hardness, improved tensile strength, better thermal conductivity, and enhanced structural stability. Overall, both materials are suitable for advanced nuclear applications, with 14Cr ODS steel showing comparatively superior performance for future fusion and Generation-IV reactor systems.

Keywords— Oxide Dispersion, Chromium, Ferritic Steels, Nuclear Applications .