| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
N-37: Study of Microstructure, Hydrogen Solubility and Corrosion of Ta-modified Zr-1Nb Alloys for Nuclear Applications |
| Author(s) |
Pedro A. Ferreirós, Estefanía C. Savoy Polack, Liliana A. Lanzani, Paula R. Alonso, Dante P. Quirós, Juan I. Mieza, Eugenia Zelaya, Alexander J. Knowles, Gerardo H. Rubiolo |
| On-Site Speaker (Planned) |
Pedro A. Ferreirós |
| Abstract Scope |
Modified Zr-1Nb alloys with Ta additions is a potential strategy to improve structural alloys for nuclear reactors. The effects of Ta on microstructural stability and resistance to corrosion of Zr–1Nb alloys were systematically investigated and elucidated. The (α+β) microstructure in Zr-1.05Nb, Zr-0.85Nb-0.20Ta and Zr-0.85Nb-0.40Ta (wt.%) alloys were obtained with the following two thermo mechanical processes after a water quenching from βZr: a) annealed at 570 °C for 3840 h and b) a combination of intermediate annealing temperatures and cold rolled steps. Quantitative EDS-TEM analysis together with DSC measurements were used to characterise the changes in phase compositions and the fraction of beta-phase precipitates. Hydrogen solubility was measured in alloys with the first annealed condition. The Ta additions increase the monotectic transformation temperature, improves the steam corrosion at 400 °C and 10 MPa up to 14 days, and decreases slightly the hydrogen solubility. The higher thermal microstructural stability compared to Ta-free Zr-1Nb alloys provide potential advantages for increases in operating temperature or acceleration of precipitation kinetics during thermomechanical processing. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |