About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification Methods for Nuclear Reactor Structural Materials
|
| Presentation Title |
Investigation of Fuel Cladding Chemical Interactions with UO2 and Cladding Materials During Simulated Accident Scenarios |
| Author(s) |
Rebecca Manns, Josephine Libero-Cruzado, Daniel Koury |
| On-Site Speaker (Planned) |
Rebecca Manns |
| Abstract Scope |
As part of a study looking at fuel cladding chemical interaction (FCCI), uranium dioxide (UO2) was placed into diffusion couples alongside cladding materials, Zircaloy-4 and FeCrAl. The diffusion couples were sealed in quartz tubes under vacuum and annealed at temperatures representative of normal and off-normal conditions in a light water reactor. After annealing, the couple was quenched and cut into cross sections. Cross sections were analyzed using an x-ray diffractometer (XRD), and a scanning electron microscope (SEM) equipped with energy dispersive x-ray spectroscopy (EDS). SEM and EDS were used to examine diffusion behavior of the systems and the resulting phases, and XRD was used to examine novel crystallographic phases forming in the diffusion zones. The results of this study provide ex-situ characterization of chemical interactions between UO2 and cladding materials at normal and off-normal temperature conditions. This is critical information to consider when qualifying new nuclear structural materials for certification. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Ceramics, Other, Other |