NSUF 23-4777: Elucidating Dislocation Loop Formation in Hot-extruded U-10Zr Alloy Under Irradiation
U-10Zr is currently being considered as fuel for several nuclear reactors under design. Among the various fabrication methods, hot extrusion has gained popularity. However, concerns have emerged regarding the anisotropic growth resulting from irradiation effects. The current understanding of this issue remains insufficient due to its complexity and limited investigations. As a result, there is a need to advance knowledge in this field. The proposed research aims to employ in situ transmission electron microscopy (TEM) with ion irradiation at elevated temperatures to investigate the formation of dislocation loops and changes in density as the radiation dose escalates. The research timeline involves 1 day of SEM-EBSD, 4 days of FIB liftout, and 5 days of TEM work. The expected outcomes will provide insights into the density of dislocation loops on specific crystallographic planes within different phases, as a function of dose. The results will shed light on mechanistic models and estimation of anisotropic growth under irradiation, leading to a better understanding in the field of metal fuel irradiation behavior.
Additional Info
| Field | Value |
|---|---|
| Abstract | U-10Zr is currently being considered as fuel for several nuclear reactors under design. Among the various fabrication methods, hot extrusion has gained popularity. However, concerns have emerged regarding the anisotropic growth resulting from irradiation effects. The current understanding of this issue remains insufficient due to its complexity and limited investigations. As a result, there is a need to advance knowledge in this field. The proposed research aims to employ in situ transmission electron microscopy (TEM) with ion irradiation at elevated temperatures to investigate the formation of dislocation loops and changes in density as the radiation dose escalates. The research timeline involves 1 day of SEM-EBSD, 4 days of FIB liftout, and 5 days of TEM work. The expected outcomes will provide insights into the density of dislocation loops on specific crystallographic planes within different phases, as a function of dose. The results will shed light on mechanistic models and estimation of anisotropic growth under irradiation, leading to a better understanding in the field of metal fuel irradiation behavior. |
| Award Announced Date | 2023-09-14T13:39:09.193 |
| Awarded Institution | None |
| Facility | None |
| Facility Tech Lead | Kevin Field |
| Irradiation Facility | None |
| PI | Yi Xie |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | None |