| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
|
| 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, 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 severe 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 of these binary systems at 6 temperatures, including both hcp and bcc phases, were measured using high-throughput diffusion multiples. These diffusion coefficients will help establish a reliable and comprehensive diffusion coefficient (atomic mobility) 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, High-Temperature Materials |