| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Thermodynamics and Kinetics of Alloys II
|
| Presentation Title |
First-principles-based Thermodynamic Database the Cr-Zr-X System Towards Design of Layered Accident Tolerant Nuclear Fuels |
| Author(s) |
Theresa Davey, Ying Chen |
| On-Site Speaker (Planned) |
Theresa Davey |
| Abstract Scope |
To improve the safety and lifetime of boiling water-type nuclear fission reactors, new accident tolerant fuels are under development where a Cr-alloy coating is applied to the conventional Zr-alloy nuclear fuel cladding. At the current stage of experimental development, pure Cr is applied to the surface of the Zr-alloy, but this work aims to determine potential alloying elements that can improve the properties of the alloys, ensure good adhesion of the Cr-based coating to the Zr-alloy, and to suppress formation of undesirable brittle intermetallic phases forming between the layers. First-principles calculations were used to investigate each of the layers in this fuel cladding system under various doping conditions with light elements, all 3d and selected 4d and 5d transition metals, and some other elements of interest. This data was used to build a Cr-Zr-X thermodynamic database that can be used for preliminary design of this layered nuclear fuel. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Modeling and Simulation, |