|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||Ion Irradiation Damage in Ferritic/Martensitic Steel T91
||Xiang Liu, Yinbin Miao, David Krumwiede, Peter Hosemann, Meimei Li, Marquis A. Kirk, James F. Stubbins
|On-Site Speaker (Planned)
Ferritic/martensitic (F/M) steel T91 is a promising candidate for multiple advanced nuclear systems. In this study, in-situ transmission electron microscopy (TEM) was used to investigate the microstructural evolution of T91 under krypton ion irradiation at elevated temperatures. Ex-situ ion irradiation was also performed on T91 at similar irradiation conditions. Nanoindentation was then used to measure the hardness of irradiated T91. Dislocation network was observed at 300C, whereas localized loop interaction was observed at 400C and 500C. The difference is explained by the <111>-<100> loop transition. Efforts were made to establish the microstructure-property relationship.
||Planned: A print-only volume