NSUF 21-4263: Local thermal properties of fast reactor MOX fuels
This work will be the first application of the thermal conductivity microscope (TCM) to sodium fast reactor (SFR) mixed oxide fuel (MOX). The benefit of using the TCM compared to standard laser flash analysis used on fuel is that the TCM is able to spatially resolve the local thermal conductivity at a resolution in the range of 50-100 micrometers. At high burnup of MOX, extensive migration of fission products towards the fuel to cladding gap occurs, which forms the so-called “Joint Oxide Gaine” or JOG. Using the TCM, the radial distribution of thermal conductivity can be determined and correlated to the elemental composition and underlying microstructure that resulted from a previous RTE (RTE #18-1452). Because the SFR MOX has been irradiated, the TCM is the only facility in the world that can perform these measurements. The scope of the project (1.5 days sample preparation of existing sample at the Irradiated Materials Characterization Laboratory, and 6 days of TCM measurements) is within the scale of an RTE and would provide first-of-its-kind data on the thermal conductivity of irradiated MOX fuel.
Informație Adițională
| Cîmp | Valoare |
|---|---|
| Awarded Institution | Brigham Young University |
| Embargo End Date | 2024-05-09 |
| Facility Tech Lead | Alina Montrose |
| NSUF Call | FY 2021 RTE 1st Call |
| PI | Troy Munro |
| PIE Facilities | Irradiated Materials Characterization Laboratory |
| Project Member | Dr. Troy Munro - Brigham Young University (https://orcid.org/0000-0002-2557-4911) |
| Project Member | Dr. Tsvetoslav Pavlov, Distinguished Postdoctoral Associate - Idaho National Laboratory |
| Project Notes | Awarded on 06/07/2021 |
| Project Type | RTE |
| Publication | Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel performance codes Marat Khafizov, Joshua Ferrigno, Tsvetoslav Pavlov, Narayan Poudel, Daniele Salvato, Chuting Tsai, Troy Munro, Fabiola Cappia Journal of Nuclear Materials 596 2024-04-26 https://doi.org/10.1016/j.jnucmat.2024.155090 |
| RTE Number | 4263 |