| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification of Nuclear Materials Integrating Experiments, Modeling, and Theories
|
| Presentation Title |
Thermal Dependence of Mechanical Anisotropy In Zircaloy-4 Cladding |
| Author(s) |
Malachi Nelson, Shmuel Samuha, Peter Hosemann, David Kamerman |
| On-Site Speaker (Planned) |
Malachi Nelson |
| Abstract Scope |
Zircaloy-4 (Zr-4) has been extensively employed in nuclear reactors as fuel cladding and core structural applications. Due to its hexagonal close-packed structure and limited slip systems, Zr-4 develops a preferred crystallographic orientation (texture) during thermomechanical fabrication processes. The resulting anisotropic mechanical properties influence in-service behavior, and material testing techniques used to measure material properties for modeling or qualification benefit from this consideration. Several studies help explain anisotropy from differing stress states, but there is little understanding of why anisotropy changes with temperature in this material. In this research, the anisotropic hardening behavior is investigated under uniaxial and biaxial stress conditions at temperatures from room temperature to 525 °C. In conjunction with electron crystallography characterizations, visco-plastic self-consistent modeling is used to quantitively correlate the thermally activated plastic deformation behavior to mechanical anisotropy and texture. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Computational Materials Science & Engineering |