|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Chemical and Microstructural Analysis of Irradiated Mixed Oxide Fuels
||Riley Parrish, Jason Harp, Assel Aitkaliyeva
|On-Site Speaker (Planned)
Mixed oxide (MOX) fuels offer excellent high temperature and chemical stability during irradiation, while the incorporation of several atomic percent Pu to base UO2 fuel can be used to eliminate Pu from long-term storage. This presentation will discuss the microstructural and chemical characteristics of annular MOX fuel pellets irradiated in fast flux test facility (FFTF) to various burnup levels. Transmission electron microscopy (TEM) is used to examine specimens sampled radially from the fuel pellet using focused ion beam (FIB) lift-out techniques. Bright field imaging is used to conduct phase identification, observe dislocations, precipitate size and morphology, and energy dispersive X-ray spectroscopy (EDS) is used to map the local chemical species.
This work was supported by the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07- 051D14517 as part of a Fuel Cycle Research and Development (FCRD) program and Nuclear Science User Facilities (NSUF).
||Planned: Supplemental Proceedings volume