| About this Abstract |
| Meeting |
MS&T22: Materials Science & Technology
|
| Symposium
|
Advanced Characterization of Materials for Nuclear, Radiation, and Extreme Environments III
|
| Presentation Title |
Advanced In-situ and Post-Irradiation-Examination Thermal Conductivity Measurements of Nuclear Fuels and Materials |
| Author(s) |
Zilong Hua, Amey Khanolkar, Cody Dennett, Robert Schley, Austin Fleming, Colby Jensen, Marat Khafizov, David Hurley |
| On-Site Speaker (Planned) |
Zilong Hua |
| Abstract Scope |
Thermal conductivity of nuclear fuels is directly related to reactor safety and efficiency. In this talk, unique advanced capabilities residing at Idaho National Laboratory (INL) that can characterize thermal conductivity and diffusivity of nuclear fuels and materials on microscopic and mesoscopic length scales are presented with the latest experimental results. Using laser-based approaches such as thermoreflectance and photothermal radiometry, thermal transport measurements can be performed as a part of Post-Irradiation Examination (PIE) or in situ. It provides novel insights of fundamental mechanisms of microscale heat conduction involving microstructural defect generation and evolution of nuclear fuels, which will benefit advanced fuel performance codes and aid in the development of high thermal conductivity fuels. |