| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Oxidation Performance of High Uranium Density Fuels for Light Water Reactors |
| Author(s) |
Joshua T. White, Jaime Stull, Scarlett Paisner, Tim Coons, Erofili Kardoulaki, Kenneth McClellan |
| On-Site Speaker (Planned) |
Joshua T. White |
| Abstract Scope |
High uranium density fuels are currently being considered for drop in replacement in the nuclear reactor fleet. This class of fuels, such as UN, provides higher thermal conductivity and improved plant economics relative to native UO2, while also overcoming the neutronic penalties of accident tolerant based alloys. Many of the fundamental mechanisms underlying the oxidation behavior of UN has not been properly investigated in the literature to date. To this end, this work investigates the fundamental corrosion mechanisms in high temperature steam and hydrogen environments to elucidate the governing corrosion mechanisms. Application of inert coatings on UN using electroless deposition will be discussed as a potential method to mitigate washout in these fuels with steam oxidation and microstructural evaluations. Discussion will assess the practical application of coatings in a commercial setting as well as evaluating this as a method to minimizing or preventing oxidation in this class of nuclear fuels. |
| Proceedings Inclusion? |
Undecided |