| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Thermodynamics and Kinetics of Alloys III
|
| Presentation Title |
Alloy Design for Cr-alloy Coated Zr-alloy Cladding of Nuclear Fuel |
| Author(s) |
Ying Chen, Theresa Davey , Bo Li, Hiroaki Abe |
| On-Site Speaker (Planned) |
Ying Chen |
| Abstract Scope |
For realizing the accident-tolerant fuels in nuclear fission reactors, a Cr-alloy coated Zr-alloy cladding system is under development where a dilute Cr-alloy layer may be applied to the conventional Zr-alloy cladding on the nuclear fuel. This work aims to find candidate alloying elements that can improve the properties of the coating alloy, ensure good adhesion of the coating layer to the Zr-alloy, and to suppress formation of undesirable brittle intermetallic phases (Laves phase) forming in the interface of Cr-Zr. First-principles calculations have been applied to investigate the stability and elements diffusion trend under various doping conditions with all 3d and selected 4d and 5d transition metal elements, then proposed that Al as alloying element in a Cr-rich solid solution, and Zn, Sn and Mg taking role of suppressing the formation of the Laves phase at the Cr-Zr interface. Based on the computational prediction, the relevant experimental validations were conducted. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Modeling and Simulation, Computational Materials Science & Engineering |