|About this Abstract
||2022 TMS Annual Meeting & Exhibition
||Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
||Investigation of Elemental Segregation and Precipitation in Ion-irradiated Advance Austenitic Alloy A709 Using Advance Techniques
||Dominic Piedmont, Xiang Liu, Hyosim Kim, Frank Garner, Lin Shao, T.-L. Sham, James F. Stubbins
|On-Site Speaker (Planned)
A709, an advanced austenitic alloy, has been down-selected for the next generation reactors for structural applications because of its high-temperature strength, corrosion resistance, and creep properties. Previous studies investigated the microstructural evolution at low doses and swelling behavior at high doses. This work quantifies the dose dependence of elemental segregation and precipitation behavior at high doses, using Atom Probe Tomography (APT), to link other microstructural changes, like void swelling and formation of network dislocations, to be observed with High Energy Diffraction Microscopy (HEDM). Samples were investigated after ion-irradiation by 3.5 MeV Fe2+ ions at an irradiation temperature of 575°C to peak dpa of 100, 200, and 400. This work addresses the need to accurately measure compositional differences of the matrix at different doses with atomistic resolution; critical to understanding the radiation-induced segregation and precipitation of A709 at the mesoscale. Potential interconnection between elemental segregation and void swelling is investigated.
||High-Temperature Materials, Nuclear Materials, Characterization