| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications
|
| Presentation Title |
Uranium Nitride Advanced Fuel: An Evaluation of the Oxidation Resistance of Coated and Doped Grains |
| Author(s) |
Yulia Mishchenko, Denise Adorno Lopes, Kyle Johnson, Janne Wallenius |
| On-Site Speaker (Planned) |
Yulia Mishchenko |
| Abstract Scope |
Uranium nitride is a high-density fissile fuel under consideration as a promising fuel for light water reactor (LWR) systems. However, its resistance to corrosion in contact with steam and air is significantly inferior to UO2 fuel and therefore must be improved. In this study, the oxidation behaviour of the composite UN-AlN, UN-CrN and UN-AlN-CrN pellets was investigated and compared with the pure UN and UO2 pellets. These dopants were selected based on ab-initio modelling calculations.
UN powders were mixed with various amounts of AlN and CrN powders and sintered into pellets of high density using the SPS method. The pellets were sectioned into small cubes and were subjected to a thermal transient up to 800°C under inert, air and steam atmospheres in an STA-EGA (TGA-DSC-Gas-MS) system. The work performed here are intended to provide the basis for future improvement in water tolerance of advanced UN fuels for LWR applications. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Composites, Ceramics |