February 15, 2024
Journal Article

Microstructural Characterization of Ion Irradiated ODS MA956 Alloy


Oxide Dispersion Strengthened (ODS) alloys are considered as promising nuclear materials for the next generation advanced nuclear reactors due to their improved elevated temperature mechanical properties and radiation damage resistance. MA956 is a commercial ODS alloy with superior oxidation resistance and creep strength at elevated temperatures. The improved properties for ODS alloys can be attributed to the presence of dispersed nanosized oxide particles. These oxide particles can act as barriers to dislocation motion and provide additional sinks and sites for point defect recombination. Hence, their stability can greatly affect the properties of the irradiated ODS alloys. Besides, irradiation will induce defects into the ODS alloys, and these defects can develop further as irradiation dose increases. The defects propagation can significantly undermine the mechanical properties of the bulk materials, resulting in irradiation hardening and lower ductility. Therefore, it is necessary to have a good understanding of the defect’s evolution with irradiation. Hence, efforts are ongoing to understand the effect of ion irradiation on ODS MA956 with emphasis on oxide particles and evolution of defects as a function of dose (2.5, 50 and 100 dpa).

Published: February 15, 2024


Lu Y., Y. Wu, R. Prabhakaran, M. Dubey, and L. Shao. 2023. Microstructural Characterization of Ion Irradiated ODS MA956 Alloy. Microscopy and Microanalysis 29, no. Suppl 1:1563–1564. PNNL-SA-182254. doi:10.1093/micmic/ozad067.804