| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Advanced Characterization and Modeling of Nuclear Fuels: Microstructure, Thermo-physical Properties
|
| Presentation Title |
Diffusion Coefficients of Zr- and Cr-based Binary Systems for Simulation of Cr-coated Zircaloy Nuclear Fuel Cladding |
| Author(s) |
Ella Kartika Pek, Wei Zhong, Alexander Butler, Ji-Cheng Zhao |
| On-Site Speaker (Planned) |
Ella Kartika Pek |
| Abstract Scope |
Chromium-coated Zircaloy is one of the accident-tolerant fuel (ATF) claddings. A thin Mo, Nb, or Ta interlayer may be placed between Cr and Zircaloy to serve as a diffusion barrier to reduce reaction between Cr and Zircaloy under accident conditions. Diffusion coefficients of Zr-(Cr, Mo, Nb, Ta), Zircaloy-Cr, and Cr-(Mo, Nb Ta) binary systems are essential for accurate prediction of the ATF lifetime. Diffusion coefficients consisting of these binary systems are being made and will be annealed at 6 temperatures. This allows us to obtain diffusion coefficients in order to establish a reliable and comprehensive diffusion coefficient database for the 8 binary systems, to fill a knowledge gap in diffusion data for the Cr-coated Zircaloy ATF. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Other |