| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
|
| Presentation Title |
Influence of Temperature on Slip Properties and Strain Rate Sensitivity in Zircaloy-4 by Micro-cantilever Tests |
| Author(s) |
Jicheng Gong, Ed Darnbrough, Angus J Wilkinson |
| On-Site Speaker (Planned) |
Jicheng Gong |
| Abstract Scope |
Zirconium is a fuel cladding material. Its micromechanical behaviour plays an important role in the mechanical integration of nuclear fission reactors. Alpha zirconium has the hexagonal crystal structure with three dominant slip systems: <a> prismatic, <a> basal and <c+a> slips. Single crystal micro-cantilevers were machined in Zircoloy-4 alloy at the orientations that can trigger each slip system, respectively. The testing pieces were deflected by an insitu pico-indenter in SEM to extract the slip properties of α-Zr from the ambient temperature to 300 ˚C. Strain rate jumps were introduced in micro-cantilever bending tests to assess the strain rate sensitivity (SRS) of each slip system as a function of temperature. The results showed SRSs of both <a> prismatic and <a> basal slips are ~0.045 which is significantly higher than that (0.01) of <c+a> slips at 150 ˚C. However, such anisotropy in SRSs becomes moderate at the room temperature and 300 ˚C. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Characterization |