| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components IV
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| Presentation Title |
Mechanical Anisotropy of Textured Nb-Modified Zircaloy-4 Cladding Tubes |
| Author(s) |
Mahmoud Y. Hawary, K.L. Murty |
| On-Site Speaker (Planned) |
Mahmoud Y. Hawary |
| Abstract Scope |
Zircaloys, long used as fuel cladding materials, have undergone various modifications to improve in-reactor performance. One such modification is the addition of Nb to Zircaloy-4, aimed at enhancing corrosion resistance while maintaining good irradiation integrity. This study explores the mechanical anisotropy of the Nb-modified Zircaloy-4 tubes through biaxial creep behavior. Axial and hoop creep strains were measured using internally pressurized tubes superimposed with an axial load at different hoop-to-axial stress ratios. Anisotropy parameters were derived using the modified Hill criterion for anisotropic materials. Creep loci at constant energy dissipation were constructed to compare axial and hoop creep strengths. Crystallographic texture and Crystalline Orientation Distribution Functions (CODF) were assessed using Electron Backscatter Diffraction (EBSD). The results provide insight into the effects of Nb modification on Zircaloy-4, particularly in terms of mechanical anisotropy under various stress conditions. This work is supported and funded by the US NSF grant CMMI1727237. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Mechanical Properties |