Flash sintering of UO2 pellets for nuclear fuel and wasteform applications

被引:0
|
作者
Harrison, R. W. [1 ]
Morgan, J. [1 ]
Buckley, J. [1 ]
Bostanchi, S. [2 ]
Pearmain, D. [2 ]
Abram, T. [1 ]
Goddard, D. [3 ]
Barron, N. [4 ]
机构
[1] Univ Manchester, Nucl Fuel Ctr Excellence, Dept Mech Aerosp & Civil Engn, Manchester M13 9PL, England
[2] Lucideon Ltd, Queens Rd, Stoke On Trent ST4 7LQ, England
[3] Preston Lab, Natl Nucl Lab, Springfields, Preston PR4 0XJ, England
[4] Cent Lab, Natl Nucl Lab, Seascale, Sellafield CA20 1PG, England
基金
英国工程与自然科学研究理事会;
关键词
Nuclear fuel; Nuclear waste; Flash sintering; Field assisted sintering; MOx; ELECTRICAL PROPERTIES; URANIUM-DIOXIDE; MECHANISM; PHASE; THO2;
D O I
10.1016/j.jeurceramsoc.2024.116993
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Flash sintering (FS) has been shown to enhance the sintering kinetics in UO2. Using a bespoke AC-FS furnace, high density UO2 pellets, >95 % theoretical density (TD) have been produced followed by scale up and Gd2O3 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 UO2 samples to >95 % TD and grain size to similar to 4 mu m, close to conventional sintering (CS). The optimised FS program reduced sintering temperature and cycle time by similar to 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% Gd2O3 addition, a similar to 92 %TD pellet with similar to 2 mu m grain size was obtainable, highlighting further optimisation is required for mixed oxide (MOx) materials.
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页数:14
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