Apparatus and method for directly preparing UO2 by molten salt electrolysis of U3O8

A molten salt electrolysis, UO2 technology, applied in the field of nuclear energy, can solve the problems of high fuel consumption, high radiation, high plutonium content, etc., and achieve the effects of reducing emissions, low cost and simple operation

Active Publication Date: 2020-05-15
HARBIN ENG UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0002] Nuclear energy is an economical, safe, reliable and clean energy, which has attracted more and more attention from the society, and the nuclear fuel cycle is the core issue restricting the development of nuclear energy, especially the current fast breeder reactor (referred to as fast reactor) has been established It is one of the preferred reactor types for the fourth-generation advanced nuclear energy system in the world, and the fast reactor spent fuel has the characteri

Method used

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  • Apparatus and method for directly preparing UO2 by molten salt electrolysis of U3O8
  • Apparatus and method for directly preparing UO2 by molten salt electrolysis of U3O8
  • Apparatus and method for directly preparing UO2 by molten salt electrolysis of U3O8

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Embodiment

[0042] (1) Experimental device

[0043] The experimental device adopted in the embodiment is as figure 1 (a) and figure 1 As shown in (b), the 0.3gU 3 o 8 The powder is loaded in the anode glass sleeve (such as figure 1 (b) shown). The electrolyte used was LiCl-KCl eutectic molten salt, and the LiCl-KCl eutectic salt was dried in a vacuum muffle furnace at 200°C for 72 hours before use, in order to remove the moisture absorbed by the LiCl-KCl eutectic salt. The cathode used is Mo cathode, which is ground and polished with SiC sandpaper before use, then soaked in dilute hydrochloric acid for a few minutes, then cleaned with ethanol until it is shiny, and dried for later use. figure 1 (a) Electrolysis of U for chloride molten salt system 3 o 8 Preparation of UO 2 Device diagram, ①-graphite rod, ②-quartz glass tube with closed bottom and holes on both sides, ③-U 3 o 8 Powder, ④-chloride molten salt, ⑤-molybdenum sheet, ⑥-electrolytic cell crucible, ⑦-corundum sleeve, ⑧-...

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Abstract

The invention provides an apparatus and a method for preparing UO2 through molten salt electrolysis of U3O8. The apparatus comprises an electrolytic tank crucible, chloride molten salt, an inert cathode and an anode device, the inert cathode and the anode device are inserted into the chloride molten salt, and the inert cathode comprises a molybdenum sheet or a tungsten sheet and a corundum sleevewrapping the molybdenum sheet or the tungsten sheet; and the anode device is formed by putting a graphite rod in a quartz glass tube with a closed bottom and with holes formed in the two sides, immersing the small holes in the two sides of the quartz glass tube in the chloride molten salt and sealing the top end of the quartz glass tube. Cl2 generated by electrolysis is applied to dissolution of U3O8 in a chloride molten salt system, so emission of Cl2 can be reduced, and repeated utilization of resources is achieved; and the problem of dissolution of U3O8 in the chloride molten salt can be solved. The process is carried out in an atmospheric environment, other auxiliary dissolving reagents are not introduced, other precipitates are not formed, and the whole process is simple to operate and low in cost.

Description

technical field [0001] The invention relates to a device and method for preparing UO2, in particular to a device and method for directly preparing UO2 by electrolyzing U3O8 with molten salt, belonging to the field of nuclear energy, and in particular to a method for dry reprocessing of spent fuel. Background technique [0002] Nuclear energy is an economical, safe, reliable and clean energy, which has attracted more and more attention from the society, and the nuclear fuel cycle is the core issue restricting the development of nuclear energy, especially the current fast breeder reactor (referred to as fast reactor) has been established It is one of the preferred reactor types for the fourth-generation advanced nuclear energy system in the world, and the fast reactor spent fuel has the characteristics of high burnup, high irradiation, and high plutonium content, and the traditional wet reprocessing technology is difficult to meet the needs of the fast reactor nuclear fuel cycl...

Claims

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Application Information

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IPC IPC(8): C25B1/00C25B1/26C25B9/00
CPCC25B1/00C25B1/26C25B9/00
Inventor 韩伟孟洋洋李梅纪文静李文龙陈刘元管艳东
Owner HARBIN ENG UNIV
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