Flash sintering of UO2 pellets for nuclear fuel and wasteform applications
Flash sintering (FS) has been shown to enhance the sintering kinetics in UO 2 . Using a bespoke AC-FS furnace, high density UO 2 pellets, >95 % theoretical density (TD) have been produced followed by scale up and Gd 2 O 3 doping trials. Increasing furnace temperature during FS increases pellet density to a plateau, however, increasing hold time and maximum current both increased the density of UO 2 samples to >95 % TD and grain size to ∼4 µm, close to conventional sintering (CS). The optimised FS program reduced sintering temperature and cycle time by ∼50 % compared to CS. Scale up trials showed >96 %TD pellets could be achieved for 11.3 and 14.125 mm diameter green bodies, demonstrating typical fuel pellet diameters are feasible with FS. Gd doping experiments showed with 1 wt% Gd 2 O 3 addition, a ∼92 %TD pellet with ∼2 µm grain size was obtainable, highlighting further optimisation is required for mixed oxide (MOx) materials.
Authors
- David Pearmain
- S. Bostanchi
- T. Abram (ORCID: https://orcid.org/0000-0001-6713-9849)
- N. Barron
- R. W. Harrison (ORCID: https://orcid.org/0000-0003-1186-6056)
- Jennifer Buckley (ORCID: https://orcid.org/0000-0003-1358-2313)
- D.T. Goddard
- J.G. Morgan
Institutions
- National Nuclear Laboratory (GB)
- University of Manchester (GB)
- Lucideon (United Kingdom) (GB)
Publication Details
- Journal
- Journal of the European Ceramic Society
- Published
- 2024-10-18
- DOI
- https://doi.org/10.1016/j.jeurceramsoc.2024.116993
- Citations
- 2
- Primary Topic
- Nuclear Materials and Properties
- Type
- article
- Field-Weighted Citation Impact
- 0.23
Funders
- Nuclear Decommissioning Authority
- Department for Business, Energy and Industrial Strategy, UK Government
- Engineering and Physical Sciences Research Council