|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Irradiation Effects on Fe-9%Cr Grain Boundary Strength Measured via In-situ TEM Testing
||Jennifer Watkins, Brian J Jaques, Allyssa Bateman, Yaqiao Wu, Indrajit Charit, Janelle P Wharry, Kayla Yano, Wen Jiang, Chao Jiang
|On-Site Speaker (Planned)
Iron-chromium based ferritic/martensitic alloys, such as Fe-9%Cr ODS, are of interest in nuclear technology applications such as structural materials for advanced nuclear reactors. This work focuses on in-situ TEM testing of single grain boundaries with known misorientation angles, before and after proton irradiation. A novel, in-situ TEM technique was used to investigate irradiation effects on the mechanical behavior of grain boundaries of Fe-9%Cr. Electron backscatter diffraction (EBSD) was used to evaluate grain size and orientation for input into finite element analysis (FEA) models for code development and validation. A focused ion beam (FIB) was used to fabricate and optimize various design geometries of sub-micrometer cantilevers and tensile specimens. An innovative “push-to-pull” device was used for tensile testing to simplify the stress state experienced at the grain boundaries. Quantitative stress-strain data and qualitative visualization of the grain boundary behavior was gained using transmission electron microscopy (TEM) coupled with a Hysitron picoindenter.
||Planned: Supplemental Proceedings volume