|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||2018 Technical Division Student Poster Competition
||SPG-38: Microstructural Characterization of W-ODS Materials for Nuclear Applications
||Ryan DeMott, Alan Xu, Dhriti Bhattacharyya, Sophie Primig
|On-Site Speaker (Planned)
Nuclear fusion is a promising solution for meeting the world’s ever-increasing energy demands but development of fusion reactors is limited by the performance of materials in extreme environments. Plasma facing components (PFCs) need to be able to resist extreme thermal stresses, radiation damage, and erosion. Tungsten materials are good candidates for PFCs due to their high melting temperature, thermal properties, and low sputtering yield, but they lack ductility at room temperature and are susceptible to embrittlement from radiation damage and recrystallization. One means of enhancing the performance of tungsten is oxide dispersion strengthening. Oxide dispersion strengthening can improve the mechanical properties of tungsten and may provide sinks for defects created by neutron bombardment and thus reduce the degree of radiation damage experienced. The current research focuses on microstructural characterization of pure tungsten and W-1%La2O3 in both recrystallized and deformed conditions, as a preliminary study prior to irradiation and mechanical testing.