Abstract
The review of the ODS steel development for nuclear material application was revised. The formation process of nanosized oxide particles was explained, focusing on decomposition by MA and subsequent precipitation by annealing. Cladding manufacturing and improvement of the creep rupture strength in the hoop direction were successfully achieved by introducing α-γ reverse transformation in 9Cr-ODS steel or recrystallized processing in 12Cr-ODS steel. 9Cr-ODS steel has a unique structure consisting of tempered martensite and residual ferrite that induces superior strength through finely dispersed oxide particles. Nanostructured ferritic alloys (NFAs) containing 12%–20% Cr with full ferrite were explained as US fusion program. These alloys show extremely superior creep and tensile strengths by low temperature 850°C extrusion, thus very high density of ultrafine Y–Ti–O-enriched nanofeatures (NFs) and high dislocation density and fine grains. The Al-added ODS steel cladding has great advantage by alumina forming that provides superior resistance to oxidation and corrosion in high temperature steam. This cladding is being developed as the accident tolerant fuel for the light water reactor (LWR). Irradiation effects were extensively reviewed, however, there is still uncertainty concerning the irradiation performance of ODS steels, through oxide particle dissolution due to ballistic dissolution or their diffusion-based mechanism.
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