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1. EP3843108 - NUCLEAR FUEL URANIUM DIOXIDE PELLETS HAVING IMPROVED FISSION GAS CAPTURING CAPABILITY, AND MANUFACTURING METHOD THEREFOR

Office
European Patent Office
Application Number 19945402
Application Date 30.10.2019
Publication Number 3843108
Publication Date 30.06.2021
Publication Kind A4
IPC
G21C 3/04
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements or their assemblies; Selection of substances for use as reactor fuel elements
02Fuel elements
04Constructional details
G21C 3/62
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements or their assemblies; Selection of substances for use as reactor fuel elements
42Selection of substances for use as reactor fuel
58Solid reactor fuel
62Ceramic fuel
G21C 21/00
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
21Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
CPC
Y02E 30/30
YSECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
30Energy generation of nuclear origin
30Nuclear fission reactors
G21C 3/047
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
02Fuel elements
04Constructional details
045Pellets
047Pellet-clad interaction
G21C 3/623
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
42Selection of substances for use as reactor fuel
58Solid reactor fuel ; Pellets made of fissile material
62Ceramic fuel
623Oxide fuels
G21C 21/00
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
21Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
Y10S 376/901
YSECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
10TECHNICAL SUBJECTS COVERED BY FORMER USPC
STECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
376Induced nuclear reactions: processes, systems, and elements
90Particular material or material shapes for fission reactors
901Fuel
G21C 3/045
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
3Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
02Fuel elements
04Constructional details
045Pellets
Applicants KEPCO NUCLEAR FUEL CO LTD
Inventors LIM KWANG-YOUNG
JUNG TAE-SIK
NA YEON-SU
JOO MIN-JAE
LEE SEUNG-JAE
KIM YOON-HO
Designated States
Title
(DE) KERNBRENNSTOFF-URANDIOXID-PELLETS MIT VERBESSERTER SPALTGASEINFANGFÄHIGKEIT UND HERSTELLUNGSVERFAHREN DAFÜR
(EN) NUCLEAR FUEL URANIUM DIOXIDE PELLETS HAVING IMPROVED FISSION GAS CAPTURING CAPABILITY, AND MANUFACTURING METHOD THEREFOR
(FR) PASTILLES DE DIOXYDE D'URANIUM DE COMBUSTIBLE NUCLÉAIRE AYANT UNE CAPACITÉ DE CAPTURE DE GAZ DE FISSION AMÉLIORÉE ET LEUR PROCÉDÉ DE FABRICATION
Abstract
(EN) The present disclosure relates to a pellet containing an oxide additive to improve a nuclear-fission-gas-adsorption ability of a uranium-dioxide pellet used as nuclear fuel and increase the grain size thereof, and to a method of manufacturing the same. A La2O3-Al2O3-SiO2 sintering additive is added to uranium dioxide so that mass movement is accelerated due to the liquid phase generated during sintering of the uranium-dioxide pellet, which promotes the growth of grains thereof. Further, since less volatilization occurs during sintering due to the low vapor pressure of the liquid phase, efficient additive performance is exhibited, so the liquid phase surrounding the grain boundary effectively adsorbs cesium, which is a nuclear fission gas.
(FR) La présente invention concerne : des pastilles contenant un additif d'oxyde pour améliorer les performances d'adsorption de gaz de fission de pastilles de dioxyde d'uranium utilisées comme combustible nucléaire et, simultanément, favoriser la croissance de taille de grains cristallins des pastilles de dioxyde d'uranium ; et leur procédé de fabrication. L'additif de frittage La2O3-Al2O3-SiO2 est ajouté au dioxyde d'uranium, de sorte qu'une phase liquide générée lors du frittage des pastilles de dioxyde d'uranium accélère un transfert de masse, favorisant ainsi la croissance de grains cristallins, et la faible pression de vapeur de la phase liquide entraîne moins de volatilisation pendant le frittage, par conséquent, l'additif peut manifester une performance efficace, et la phase liquide encerclant les limites de grains cristallins ainsi obtenue peut adsorber efficacement le césium gazeux de fission.