|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||High Temperature Strength Characterization of Alloy 709
||Nicholas Shaber, Harrison Pugesek, Jose Ramirez, Martin Taylor, Robert Stephens, Gabriel Potirniche, Indrajit Charit
|On-Site Speaker (Planned)
Advanced nuclear technologies necessitate advancements in material technologies and characterization. Alloy 709 has shown promising characteristics for nuclear structural applications. Utilizing servo hydraulic test frames, fatigue and creep fatigue crack growth tests are being completed to characterize the mechanical properties and confirm numerical models for Alloy 709. Multiple tests, in conjunction with funding from the DOE-NEUP program, are set to provide the experimental data. Performing these test, analysis of crack growth rates and fracture surfaces are being completed to better understand the properties of Alloy 709. Tests performed on this material show great promise for longer service life in nuclear applications as compared to other materials currently in use.
||Planned: Supplemental Proceedings volume