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
相关论文
共 29 条
[21]   UBER DAS CERURANBLAU UND MISCHKRISTALLE IM SYSTEM CEO2-UO2-U3O8 [J].
RUDORFF, W ;
VALET, G .
ZEITSCHRIFT FUR ANORGANISCHE UND ALLGEMEINE CHEMIE, 1953, 271 (5-6) :257-272
[22]   Sintering of a UO2-PuO2 freeze-granulated powder under reducing conditions [J].
Simeon, Julie ;
Lebreton, Florent ;
Ramond, Laure ;
La Lumia, Florian ;
Clavier, N. ;
Bernard-Granger, Guillaume .
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY, 2020, 40 (15) :5900-5908
[23]   A mechanism for the sintered density decrease of UO2-Gd2O3 pellets under an oxidizing atmosphere [J].
Song, KW ;
Kim, KS ;
Yang, JH ;
Kang, KW ;
Jung, YH .
JOURNAL OF NUCLEAR MATERIALS, 2001, 288 (2-3) :92-99
[24]   In situ X-ray characterization of uranium dioxide during flash sintering [J].
Sprouster, David J. ;
Kardoulaki, Erofili ;
Weidner, Randy ;
Raftery, Alicia M. ;
Elbakhshwan, Mohamed ;
Pokharel, Reeju ;
Reiche, Helmut M. ;
Byler, Darrin D. ;
Ghose, Sanjit K. ;
Dooryhee, Eric ;
McClellan, Kenneth J. ;
Ecker, Lynne E. .
MATERIALIA, 2018, 2 :176-182
[25]  
SURYANARAYANA C, 1998, XRAY DIFFRACTION PRA, P153, DOI DOI 10.1007/978-1-4899-0148-4_6
[26]   Microstructure of carbon blacks determined by X-ray diffraction profile analysis [J].
Ungár, T ;
Gubicza, J ;
Ribárik, G ;
Pantea, C ;
Zerda, TW .
CARBON, 2002, 40 (06) :929-937
[27]   Flash sintering of stoichiometric and hyper-stoichiometric urania [J].
Valdez, J. A. ;
Byler, D. D. ;
Kardoulaki, E. ;
Francis, J. S. C. ;
McClellan, K. J. .
JOURNAL OF NUCLEAR MATERIALS, 2018, 505 :85-93
[28]   THE ELECTRONIC TRANSPORT-PROPERTIES OF UO2 [J].
WINTER, PW .
JOURNAL OF NUCLEAR MATERIALS, 1989, 161 (01) :38-43
[29]   EFFECT OF SINTERING ATMOSPHERE ON THE DENSIFICATION OF UO2-GD2O3 COMPACTS [J].
YUDA, R ;
UNE, K .
JOURNAL OF NUCLEAR MATERIALS, 1991, 178 (2-3) :195-203