|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Effect of Neutron Irradiation on the Mechanical Properties and Microstructure of Friction Stir Processed ODS Alloys
||Ramprashad Prabhakaran, Mychailo Toloczko, 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 would cause various undesirable effects such as the coalescence of oxide dispersoids and generation of significant porosity. A number of alternative joining methods exists. Presented here is the use of friction stir welding (FSW) to join iron-based MA956 and nickel-based MA754 plates separately in a bead-on-plate configuration. Higher weld efficiencies were achieved in both alloys. Microhardness and miniature 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, shear punch testing, EBSD and TEM analyses.
||Planned: Supplemental Proceedings volume