| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-based Composites for Nuclear Fission Applications
|
| Presentation Title |
Radially Resolved Thermo-physical Modelling in High Burnup Oxide Nuclear Fuel |
| Author(s) |
Joshua Ferrigno, Pierre-Clement Simon, Marat Khafizov |
| On-Site Speaker (Planned) |
Joshua Ferrigno |
| Abstract Scope |
Localized trends affecting the thermo-physical properties of nuclear fuel have only recently been elucidated owing to novel experimental methods which are far more discretized than previously. Radial measurement of porosity, elemental composition, and thermal conductivity of mixed oxide nuclear fuel pellets at various burnups (6%-19% FIMA) have been similarly measured. Here we develop a BISON model with which we model the oxide system measured in post irradiation examination (PIE) to derive the radial quantities as seen in measurement. Within this model, the various thermal conductivity models are deliberated, and modifications are made to ensure that the extracted thermal conductivity of MOX fuel can be corroborated with measurements. Due to large thermal variations across the annular fuel pellet, many significant microstructural alterations occur across short distances which greatly impact thermal conductivity. This work provides a pathway for improving localized thermal conductivity correlations, and thermo-physical processes in fuel performance codes. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, |