About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Qualification Methods for Nuclear Reactor Structural Materials
|
| Presentation Title |
Biaxial Creep Anisotropy in Nb-Modified Zircaloys: Role of Microstructure and Texture |
| Author(s) |
Mahmoud Y. Hawary, K.L. Murty |
| On-Site Speaker (Planned) |
Mahmoud Y. Hawary |
| Abstract Scope |
This study examines the biaxial creep behavior of Nb-containing zirconium alloys, ZIRLOŽ and HANA-4, developed for nuclear fuel cladding in light water reactors. Testing was conducted on thin-walled tubes in both cold-worked stress-relieved (CWSR) and recrystallized (Rx) conditions under varied hoop-to-axial stress ratios (0–2), using internal pressurization and axial loading. Anisotropy parameters (R, P) and formability (B) were determined using the modified Hill criterion. Crystallographic orientation distribution functions (CODFs) from EBSD were used to quantify texture and correlate it with creep anisotropy. EBSD also provided insights into grain morphology and aspect ratios, highlighting microstructural influences on deformation behavior. Creep loci were constructed at constant energy dissipation to assess deviations from isotropy. Temperature and stress effects on deformation were also evaluated. This work highlights the critical role of microstructure and texture in governing anisotropic creep in advanced Zircaloys, supporting the development of more resilient nuclear fuel cladding materials. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, |