| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
Microstructural and Mechanical Properties of Hot Deformation Behavior of Zr-4 Alloy
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| Author(s) |
Gaurav Singh, Raviraj Verma, Vishnu Narayanan KI, Umesh Kumar Arora, R Jayaganthan |
| On-Site Speaker (Planned) |
Gaurav Singh |
| Abstract Scope |
Zirconium alloy shows a good combination of strength and ductility, low neutron absorption cross-section, and excellent corrosion and oxidation resistance. The hot deformation behaviour of Zr-4 was studied in the temperatures (650oC and 750oC) with strain rates (0.01 and 1 s-1). It was observed that the flow stress of Zr alloy is high at a high strain rate (1 s-1) and low temperature (650oC). The true stress-strain curve of the alloy has shown the serrated oscillation characteristics. Electron backscattered diffraction (EBSD) was used to characterize y evolution of microstructural and texture features in hot deformed samples. Microhardness of measurements were performed in hot deformed samples was measured and it was correlated with the microstructural characteristics such as grain size and texture. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Other |