|About this Abstract
||2023 TMS Annual Meeting & Exhibition
||Microstructural, Mechanical and Chemical Behavior of Solid Nuclear Fuel and Fuel-cladding Interface
||Advanced Characterization of Fuel-cladding Chemical Interaction in HT9 clad U-Mo-Ti-Zr Metallic Fuel Irradiated in Advanced Test Reactor
||Yachun Wang, Jatuporn Burns, Mukesh N Bachhav, Tiankai Yao, Luca Capriotti
|On-Site Speaker (Planned)
Abstract: Fuel cladding chemical interaction (FCCI) is recognized as an important fuel performance factor to support high burnup metallic fuel. Idaho National Laboratory’s and Department of Energy Advanced Fuel Campaign program experience on U-Zr fuel R&D focus on developing a mechanistic understanding of FCCI behavior and advanced fuel designs to mitigate and control FCCI. This study leveraged the state-of-the-art materials characterization methods, such as scanning electron microscopy (SEM), transmission electron microscopy (TEM), and atom probe tomography (APT), to better characterize the FCCI region formed in HT9 cladding by interaction with U-5Mo-4.3Ti-0.7Zr (wt.%) fuel during irradiation in the Advanced Test Reactor (ATR) to 2.2 % FIMA at peak inner cladding temperature (PICT) up to 650°C. Results are discussed in terms of the characteristics of FCCI and the effects from fuel composition and irradiation conditions on FCCI.
||Characterization, Nuclear Materials, Other