About this Abstract |
Meeting |
2024 TMS Annual Meeting & Exhibition
|
Symposium
|
2024 Technical Division Student Poster Contest
|
Presentation Title |
SPG-69: Investigation of Fuel Chemical Cladding Interactions with UO2 and UN using Diffusion Couples |
Author(s) |
Rebecca Manns, Josie Libero, Daniel Koury |
On-Site Speaker (Planned) |
Rebecca Manns |
Abstract Scope |
As part of a study looking at fuel chemical cladding interactions (FCCIs), uranium dioxide (UO2) and uranium nitride (UN) pellets were placed into diffusion couples alongside cladding materials of interest, such as HT9 and zircaloy. The diffusion couples were sealed in quartz tubing under vacuum, annealed at various temperatures, quenched, and then cut into cross sections. Cross sections were prepared using standard metallographic practices and were analyzed using a scanning electron microscope (SEM) equipped with energy dispersive x-ray spectroscopy (EDS). SEM and EDS were used to examine the concentration profiles of the diffusion zones, the resulting phases, and the general diffusion behavior of the systems. The activation energies, integrated diffusion coefficients, and interdiffusion coefficients were calculated. The results of this study provide critical information about the fuel chemical cladding interactions and offer a comparison between UO2, a well-established fuel, and UN, a candidate fuel. |
Proceedings Inclusion? |
Undecided |
Keywords |
Nuclear Materials, Characterization, Other |