|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Modeling High-Temperature Corrosion of Zirconium Alloys Using the Extended Finite Element Method
||Wen Jiang, Benjamin Spencer, Adrien Couet
|On-Site Speaker (Planned)
The oxidation process of zirconium-alloy cladding is fundamental in light-water reactor fuel performance. The resultant oxidation layer on the cladding’s outer surface can affect the cladding’s thermal and mechanical properties. In current nuclear fuel performance codes, oxidation modeling is limited by the lack of coupling with mechanics, thus impeding a proper description of high-temperature oxidation’s impact on mechanical properties. This limitation is mostly due to the key numerical challenge inherent in tracking the location of the oxidation front over time. A recent development in the extended finite element method (X-FEM) in the nuclear fuel performance code BISON enables precision tracking of interfaces at relatively low computation cost. The ability to couple X-FEM with the mechanics in BISON is a first-of-a-kind achievement in oxidation modeling and would enable more comprehensive simulations of fuel rod behavior during LOCAs.
||Modeling and Simulation, Computational Materials Science & Engineering, Nuclear Materials