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A kind of reaction medium of uranium-containing low-temperature molten salt system, preparation method and application of the system

A technology of low-temperature molten salt and reaction medium, which is applied in the direction of reactor fuel materials, greenhouse gas reduction, nuclear power generation, etc., can solve the problems of electrolytic cell short circuit, large-scale continuous production, etc., and achieve simple process, solve electrolytic cell short circuit, and good The effect of environmental friendliness

Active Publication Date: 2019-11-12
MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0006] The purpose of the present invention is to: in the current dry reprocessing of spent fuel, LiCl-KCl-UCl in the temperature range of 400-500°C is usually used 3 Molten salt system, molten salt electrolytic refining of uranium to produce dendritic metal uranium with a loose structure is likely to cause a short circuit in the electrolytic cell and cannot be produced continuously on a large scale. A low-temperature molten salt system containing uranium, its preparation method and application are provided

Method used

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  • A kind of reaction medium of uranium-containing low-temperature molten salt system, preparation method and application of the system
  • A kind of reaction medium of uranium-containing low-temperature molten salt system, preparation method and application of the system
  • A kind of reaction medium of uranium-containing low-temperature molten salt system, preparation method and application of the system

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Experimental program
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Effect test

Embodiment 1

[0053] In a low-humidity hypoxic glove box, mix the components evenly according to the molar ratio LiBr: KBr: CsBr = 0.561: 0.189: 0.250, then weigh 300 g of dried LiBr, KBr and CsBr mixed salts and 6 g of ZnBr 2 , after stirring evenly, put it into an alumina crucible. In the heating furnace in the glove box, the crucible is heated to 400 °C with the heating furnace at a heating rate of 3 °C / min. During this period, 5g of high-purity dendritic metal uranium was dried and stored. When the temperature of the molten salt in the crucible reaches 240°C, the above metal uranium is added at one time. At this time, a violent substitution reaction can be observed in the crucible.

[0054] When the reaction reached 12 hours, a cold alumina rod was quickly inserted into the molten salt and then taken out. At this time, the molten salt sample adhered to the surface of the alumina rod was used for ICP-AES analysis. The analysis results showed that the content of zinc element in the mol...

Embodiment 2

[0059] In a low-humidity and low-oxygen glove box, according to the molar ratio LiBr: KBr: CsBr = 0.561: 0.189: 0.250, mix the components evenly, and then weigh 300 g of the dried LiBr, KBr and CsBr mixed salt and 10 g of ZnBr 2 , after stirring evenly, put it into an alumina crucible. In the heating furnace in the glove box, the crucible was heated to 450 °C with the heating furnace at a heating rate of 3 °C / min. During this period, 8g of high-purity dendritic metal uranium was dried and preserved. When the temperature of the molten salt in the crucible reaches 240°C, the above metal uranium is added at one time. At this time, a violent substitution reaction can be observed in the crucible.

[0060] Then, use a cold alumina rod to quickly put it into the molten salt and then take it out. At this time, the molten salt sample adhered to the surface of the alumina rod is used for ICP-AES analysis. The analysis results show that the mass fraction of zinc element in the molten ...

Embodiment 3

[0063] In the electrolytic furnace, with the UBr prepared according to the example 1 method 3 LiBr-KBr-CsBr-UBr with a mass fraction of 2.7% 3 The bromide molten salt system is the electrolyte, the cathode uses a tungsten rod with a diameter of 2mm and a length of 40mm immersed in the molten salt, and the anode uses a metal uranium rod with a diameter of 9mm and a length of 100mm for electrolytic refining; among them, the cell voltage is 0.7V, and the electrolysis temperature is 350 ℃, the electrolysis time is 48 hours. High-purity metal uranium is deposited on the cathode, and the metal uranium presents a nodular shape.

[0064] Analysis result shows: the metallic uranium purity that present embodiment prepares exceeds 99.995%, and uranium sample is as image 3 As shown, the XRD pattern of the uranium sample is as Figure 4 Shown, impurity element content analysis is shown in Table 1. image 3 In the figure, the top is the silver-white metallic uranium after the molten sa...

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Abstract

The invention discloses a uranium-bearing low-temperature molten salt system, a preparation method thereof and an application of the system to the field of electrolytic preparation of metallic uranium, and aims to solve the problems that in current spent fuel dry reprocessing, an LiCl-KCl-UCl3 molten salt system within the temperature range of 400-500 DEG C is usually adopted, uranium is refined by molten salt electrolysis to generate structurally loose dendritic metallic uranium, short circuit of an electrolytic tank is easily caused, and large-scale continuous production cannot be realized.The metallic uranium electrolytically prepared by the uranium-bearing low-temperature molten salt system is high in purity and compact in structure and in the shape of a nodule (but the metallic uranium prepared by the LiCl-KCl-UCl3 molten salt system is structurally loose and dendritic and has essential difference from the metallic uranium electrolytically prepared by the uranium-bearing low-temperature molten salt system), and the electrolytic refining process is safe and controllable, can be applied to development of industrial spent fuel dry reprocessing technology to meet the requirementsof Chinese industrial continuous production of high-purity metallic uranium, and has a good application prospect. Further, the uranium-bearing low-temperature molten salt system is simple in production process, low in equipment and experimental condition requirement, low in energy consumption and pollution, has a good application prospect and is worthy of large-scale popularization and application.

Description

technical field [0001] The invention relates to the field of chemical industry, especially the field of nuclear chemical industry, especially the field of preparation and recovery of metal uranium, specifically a uranium-containing low-temperature molten salt system, its preparation method and application. The present invention proposes a uranium-containing low-temperature molten salt system based on a low-temperature bromide molten salt system, and prepares a uranium-containing low-temperature molten salt system in situ through a redox reaction, and prepares a non-dendritic structure with a tight structure based on the molten salt system. High-purity solid uranium metal is of great significance for the development of spent fuel dry reprocessing technology and the preparation of high-purity metal uranium. Background technique [0002] In the spent fuel dry reprocessing technology, the recovery of uranium by molten salt electrolytic refining is one of the core processes; curr...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C22B60/02G21C3/54
CPCC22B60/0213G21C3/54Y02E30/30
Inventor 唐浩贾建平
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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