|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||2016 Technical Division Young Professional Poster Competition
||YP-9: Effect of Neutron Irradiation on Friction Stir Processed ODS Alloys
||Ramprashad Prabhakaran, Yaqiao Wu, Jatu Burns, James Cole, Indrajit Charit, Rajiv S Mishra, KL Murty
|On-Site Speaker (Planned)
Efforts are ongoing to examine the feasibility of using oxide dispersion strengthened (ODS) alloys in advanced nuclear reactors. Conventional fusion welding of ODS alloys could cause various undesirable effects such as the coalescence of oxide dispersoids and generation of significant porosity. Hence, friction stir welding (FSW) was used to weld iron-based MA956 plates and nickel-based MA754 alloys separately in a bead-on-plate configuration. Higher weld efficiencies were achieved in both alloys. Microhardness and mini-tensile testing of the parent and processed materials were carried out to evaluate the mechanical properties. EBSD, TEM and APT were used to evaluate the microstructural characteristics of the parent and processed materials. Both parent and processed specimens were irradiated in the Advanced Test Reactor (ATR) for 1 and 2 dpa. The irradiated materials were characterized using microhardness testing, EBSD and TEM analyses.
||Definite: None Selected