| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramic Materials for Nuclear Energy Research and Applications
|
| Presentation Title |
Zirconia-coated Uranic Fuel Particles Processing and In Situ Sintering Characterisation |
| Author(s) |
Phylis Makurunje, Gareth Stephens, Simon C. Middleburgh |
| On-Site Speaker (Planned) |
Phylis Makurunje |
| Abstract Scope |
Gel casting was studied as an encapsulation-aiding process for the manufacture of uranic coated fuel particles (CFP) for gas and light water reactors. Encapsulation involved the envelopment of colloidal droplets within a zirconium oxynitrate precursor solution during gel casting. The enveloping zirconium oxynitrate precursor phase was to result in a zirconium oxide coating on uranium dioxide kernels. The surfactants-conditioned uranium dioxide colloid was modified by an alginate cross-linking matrix prior to encapsulation, to facilitate solidification by ion exchange when contacted with calcium chloride. Pourbaix diagrams were employed to analyse zirconium oxynitrate solution stability with varying pH and complemented by experimental zeta potential studies. The kernels' sintering behaviour and thermal expansion were analysed by an optical dilatometer system up to 1600 °C in argon and characterised by XRD, Raman spectroscopy and SEM. Encapsulated wet granulation is a promising method for manufacturing coated fuel particles. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Surface Modification and Coatings, Ceramics, Shaping and Forming |