|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Computational Materials Science and Engineering for Nuclear Energy
||A Model Coupling Hydrides Formation and Mechanical Behavior of Zircaloy Cladding during Fuel Rod Lifecycle
||Hao Wang, Vikas Tomar
|On-Site Speaker (Planned)
Waterside corrosion of zirconium-alloy (zircaloy) cladding introduces hydrogen precipitates into crystals of zirconium hydride which decrease the ductility of the cladding and may lead to cladding failure. The aim of this work is to provide a viscoplasticity model to describe the mechanical behavior of zirconium hydride rim structure, and coupling it with hydrogen transport. The material parameters are characterized by using Electron Backscatter Diffraction (EBSD) and nanoindentation tests on zircaloy hydride samples. Then the model is validated by Nano Mechanical Raman Spectroscopy measurements during a three point bending test. This model allows us to perform simulation to study the plastic deformation of fuel rod cladding during normal operations, dry storage, and loss of coolant accident (LOCA) scenario. Furthermore, by coupling with the existing hydride formation model in the BISON fuel performance code, hydrogen diffusion induced mechanical property changes and the impact on cladding performance could also be simulated.
||Planned: Supplemental Proceedings volume