|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Multiscale Irradiation Effects of Tungsten Based Materials for Nuclear Power
||Osman El-Atwani, Erika Esquivel, Mert Efe, Eda Aydogan, Stuart Maloy
|On-Site Speaker (Planned)
Development of advanced structural materials for nuclear power requires overcoming several material design and testing challenges. Here we present multiscale phenomena in irradiated tungsten materials as a step to generate a “figure of merit” correlating materials morphological and mechanical response with irradiation parameters. At the small scale, the effect of grain boundary density on limiting the irradiation damage is quantified. Irradiation damage was quantified through different ways and nanocrystalline tungsten was compared with coarse grained materials though in-situ and ex-situ TEM/irradiation. Detailed TEM analysis was performed to identify the loop Burgers vector formation at RT and high temperatures. The grain boundary sink efficiency is discussed based on denuded zone formation. The results are compared with other BCC materials. At the large scale, nanoindentation tests are performed. The multiscale studies are then correlated. Conclusions regarding the advantages and possible disadvantages of using pure nanocrystalline tungsten materials are presented.
||Planned: Supplemental Proceedings volume