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Method for preparing UO2

A UO2, molten salt technology, applied in the electrolysis process, electrolysis components, etc., can solve the problems of high fuel consumption, high radiation and so on

Inactive Publication Date: 2020-06-19
HARBIN ENG UNIV
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Problems solved by technology

[0002] Fast breeder reactors (referred to as fast reactors) are one of the preferred reactor types for fourth-generation advanced nuclear energy systems in the world. Fast reactor spent fuel has the characteristics of high burnup, high irradiation, and high plutonium content. Traditional wet reprocessing Technology is difficult to meet the needs of the fast reactor nuclear fuel cycle, and the dry reprocessing technology with molten salt as the medium has the advantages of high temperature resistance, good radiation stability and less radioactive waste, so for spent fuel reprocessing, dry reprocessing Technology with its unique advantages is a key technology choice for the future fast reactor nuclear fuel cycle

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Embodiment

[0049] (1) LiCl-KCl molten salt system and electrolysis device

[0050] The LiCl-KCl eutectic molten salt system (45.8:54.2wt%) was used as the electrolyte. LiCl and KCl were dried and dehydrated before molten salt electrolysis, and LiCl and KCl were dried in a muffle furnace at 200°C for 72 hours, and then mixed in proportion and placed in a muffle furnace at 200°C. Store dry. The molten salt electrolysis experiment adopts a three-electrode system. The working electrodes used in the experiment include tungsten wire (Φ=0.6mm, purity 99.99%) and molybdenum sheet (width×thickness 10mm×1mm, purity 99.99%). The tungsten wire is used to study U 3 o 8 Electrochemical behavior after dissolution, molybdenum flakes were used for electrodeposition experiments. Before use, the working electrode was ground and polished with SiC sandpaper, then soaked in dilute hydrochloric acid, then ultrasonically cleaned with ethanol until it was shiny, and dried for later use. The auxiliary electro...

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Abstract

The invention provides a method for preparing UO2. The method comprises the following steps: firstly, fully and uniformly mixing U3O8 and NH4HF2 powder, and putting the mixed powder at the bottom of acrucible; then, laying LiCl-KCl salt on the mixed powder to cover the mixed powder; carrying out heating to 500 DEG C to melt the salt and keeping the temperature for 3 hours; and after the U3O8 is fully reacted and dissolved, carrying out constant-potential electrolysis by using a potential of -0.8 v (vs Ag / AgCl) with a molybdenum sheet as a cathode, a graphite rod as an anode and Ag / AgCl as a reference electrode so as to prepare UO2, wherein the result of ICP-AES analysis calculation shows that the extraction rate of uranyl ions after electrolysis for 8 hours reaches 98.5%. On one hand, theinvention provides the method for preparing UO2 by purifying uranium oxide through molten salt electrolysis; and on the other hand, HF gas generated in the process of reaction dissolution can be combined with oxygen ions to remove the oxygen ions in the molten salt in the form of water vapor.

Description

technical field [0001] The present invention belongs to the field of nuclear energy development, and relates to a method for dry reprocessing of spent fuel, in particular to a method for preparing UO 2 Methods. Background technique [0002] Fast breeder reactors (referred to as fast reactors) are one of the preferred reactor types for fourth-generation advanced nuclear energy systems in the world. Fast reactor spent fuel has the characteristics of high burnup, high irradiation, and high plutonium content. Traditional wet reprocessing Technology is difficult to meet the needs of the fast reactor nuclear fuel cycle, and the dry reprocessing technology with molten salt as the medium has the advantages of high temperature resistance, good radiation stability and less radioactive waste, so for spent fuel reprocessing, dry reprocessing Technology with its unique advantages is a key technology choice for the future fast reactor nuclear fuel cycle. [0003] Oxide fuel is currently...

Claims

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Application Information

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IPC IPC(8): C25B1/00
CPCC25B1/00
Inventor 韩伟孟洋洋李梅纪文静李文龙陈刘元张迎春
Owner HARBIN ENG UNIV
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