| 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 |
Cr-doped UO2 Studied Using XAS and Neutron Scattering |
| Author(s) |
Arjen van Veelen, Adrien J. Terricabras, Scarlett Widgeon Paisner, Tarik A. Saleh, Joshua T. White |
| On-Site Speaker (Planned) |
Arjen van Veelen |
| Abstract Scope |
Uranium dioxide (UO2) fuel powers commercial light water reactors. Dopants enhances fuel performance and stability by increasing microstructure, in particular grain size, improving both creep and fission gas release behavior. Cr dopants has been recognized to enhance grain growth, which increases grains from ~15 (± 2 µm) to 28-41 (± 4 µm) through the incorporation of defects and liquid secondary phases. Understanding the structure and formation of defects are important for the development of fission gas models and Centipede code development. The structure of these defects has currently not been measured in great detail. We used X-ray Absorption Spectroscopy and X-ray and Neutron Diffraction to study the defect structures of Cr-doped and un-doped UO2. Our results suggest that Cr dissolution into UO2 is strongly dependent on concentration, temperature and oxygen potential during sintering. We will discuss the Cr-doping effects on the UO2 defect chemistry in relation to fission gas modeling. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Other |