|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||F-3: Grain Boundary Influence on Displacement Cascades in ZrC
||Raul Fernando Florez Meza, Joseph Graham
|On-Site Speaker (Planned)
Zirconium Carbide (ZrC) is a promising structural material for nuclear applications because of its excellent thermal, neutronic, mechanical and chemical properties. Although several studies have been conducted to understand the radiation response of ZrC, there is still a limited knowledge of the influence of grain boundaries on the nucleation and evolution of radiation-induced defects in polycrystalline ZrC. In this study, near stoichiometric ZrC was irradiated with 10 MeV Au+ ions at various temperatures (800-1100 oC) and doses (0.5-30 dpa). Pre- and post-irradiated samples were examined using several transmission electron microscopy (TEM) techniques to investigate the influence of grain boundary structures on the radiation-induced dislocation evolution.
||Planned: Supplemental Proceedings volume