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Preparation method of uranium nitride composite uranium silicide fuel pellet

A technology of fuel pellets and uranium nitride, which is applied in the field of preparation of uranium nitride composite fuel pellets, can solve the problems of unclear description of the preparation process and composite fuels that have not been reported.

Inactive Publication Date: 2021-06-22
CHINA NUCLEAR BAOTOU GUANGHUA CHEM IND
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Problems solved by technology

[0002] At present, the process preparation method widely used in foreign countries is to use U 3 Si 2 After mixing with UN, UN-U is prepared by liquid phase sintering and spark plasma sintering process 3 Si 2 Composite fuel, but the description of the preparation process is not clear, and domestic research on the composite fuel has not been reported

Method used

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Embodiment

[0021] High-purity graphite is selected as the mold used for smelting, and a layer of refractory oxide slurry coating is applied to the inner wall by electrostatic spraying. The slurry is made of ZrO 2 (whereby adding 10-20wt% of Y 2 o 3 )composition;

[0022] Clean the oxide layer on the surface of the refined uranium ingot with nitric acid, soak it in alcohol to remove the residual dirt on the surface, wipe and dry it, put the uranium ingot on the high-purity silicon ingot, and put it into a high-purity graphite crucible, in which the silicon The mass of the ingot accounts for 5% to 11% of the total mass;

[0023] Put the above-mentioned mold with materials into a high-frequency induction melting furnace as a whole, fill it with Ar gas as a protective gas, set the melting temperature at 1500-1800°C, and realize the uniformity of the materials by continuously stirring the molten materials during the melting process After fully degassing, the molten material is poured in th...

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Abstract

The invention belongs to the technical field of preparation of uranium nitride composite fuel pellets, and particularly relates to a preparation method of a uranium nitride composite uranium silicide fuel pellet. The preparation method comprises the steps of preparing a U3Si2 ingot through vacuum induction melting of metal uranium and monatomic silicon, and crushing and ball-milling to obtain U3Si2 powder; carrying out cyclic hydrogenation dehydrogenation on metal uranium to prepare metal uranium powder, and conducting nitridation to obtain a uranium nitrogen compound; pre-pressing the uranium nitrogen compound in a graphite mold, carrying out high-temperature denitrification on the uranium nitrogen compound together with the mold in a tungsten-molybdenum sintering furnace to obtain a blocky UN material, and carrying out crushing and ball milling to prepare UN powder which can stably exist at room temperature; carrying out dry three-dimensional mixing or wet ball milling mixing with ethyl alcohol as a medium on the UN powder and 10-80 wt% of U3Si2 powder, obtaining UN-U3Si2 mixed powder, and preparing the UN-U3Si2 composite fuel pellet through pressureless sintering or hot pressing sintering. The pellet has higher uranium density, higher heat conductivity coefficient and certain steam oxidation resistance, and the overall capacity of a system for bearing serious accident conditions is enhanced.

Description

technical field [0001] The invention belongs to the technical field of preparing uranium nitride composite fuel pellets, and in particular relates to a preparation method of uranium nitride composite uranium-three-silicon-two fuel pellets. Background technique [0002] At present, the process preparation method widely used in foreign countries is to use U 3 Si 2 After mixing with UN, UN-U is prepared by liquid phase sintering and spark plasma sintering process 3 Si 2 Composite fuel, but the description of the preparation process is not clear, and domestic research on the composite fuel has not been reported. Contents of the invention [0003] The purpose of the present invention is to provide a method for preparing uranium nitride composite uranium-silicon-difuel pellets, the prepared UN-U 3 Si 2 Composite Fuel vs Conventional UO 2 Compared with fuel pellets, it has higher uranium density, higher thermal conductivity and certain resistance to steam oxidation, which e...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C21/02G21C21/16
CPCG21C21/02G21C21/16Y02E30/30
Inventor 李宗书杜江平何勇刘文涛郝若彤乔伟隋政孟莹
Owner CHINA NUCLEAR BAOTOU GUANGHUA CHEM IND
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