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.

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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

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article

Flash sintering of UO2 pellets for nuclear fuel and wasteform applications

David Pearmain, S. Bostanchi, T. Abram, N. Barron et al.
2 citations
Journal of the European Ceramic Society
Nuclear Materials and Properties
0.23
article

Flash sintering of UO2 pellets for nuclear fuel and wasteform applications

David Pearmain, S. Bostanchi, T. Abram, N. Barron, R. W. Harrison, Jennifer Buckley, D.T. Goddard, J.G. Morgan
article en
2 citations

Abstract

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.

Journal of the European Ceramic SocietyVol. 45(3)
National Nuclear Laboratory (GB), University of Manchester (GB), Lucideon (United Kingdom) (GB)
Nuclear Decommissioning Authority, Department for Business, Energy and Industrial Strategy, UK Government, Engineering and Physical Sciences Research Council
Openalex Percentile: Top 50%
Nuclear Materials and Properties
0.23
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Flash sintering of UO2 pellets for nuclear fuel and wasteform applications — David Pearmain, S. Bostanchi, et al. · Journal of the European Ceramic Society (2024) | TGRS Research Map | TGRS