Method for preparing initial molten salt system in molten salt electrolysis dry after-treatment process

A molten salt electrolysis and molten salt technology, applied in the field of nuclear fuel cycle dry reprocessing, can solve the problems of increasing radioactive material operating procedures, current empty consumption, incomplete discharge of tetravalent uranium, etc., to reduce the amount and disposal costs, and save Production cost and the effect of shortening the operation process

Active Publication Date: 2015-04-29
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This method of directly adding uranium chloride requires an additional production line for uranium chloride, which increases the operating procedures for radioactive substances; in addition, the uranium chloride prepared on the production line is usually a mixture of uranium trichloride and uranium tetrachloride, the latter's The introduction will easily lead to incomplete discharge of tetravalent uranium in the cathode, resulting in empty current consumption

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0034] A method for preparing an initial molten salt system during molten salt electrolytic dry post-treatment, the method comprising the following steps:

[0035] (1) Add 300 g of LiCl-KCl eutectic molten salt and 50 g of spent fuel into the electrolytic cell, wherein the spent fuel is immersed in a porous platinum-coated titanium basket and suspended in the lower part of the LiCl-KCl eutectic molten salt;

[0036] (2) Heating the LiCl-KCl eutectic molten salt to 450°C to melt it, and keeping it in a molten state at constant temperature;

[0037] (3) Pass HCl gas into the electrolyzer described in step (1) through the nickel-based alloy pipeline, and react with the uranium in the spent fuel to generate UCl 3 , the gas flow rate is 0.1L / min;

[0038] (4) Purge argon into the electrolytic cell described in step (1) through the nickel-based alloy pipeline to get rid of the HCl gas remaining in the pipeline and molten salt, and obtain the initial molten salt required for post-tr...

Embodiment 2

[0042] The method and steps used in Example 1 are the same, except that the heating temperature of the eutectic molten salt is 500° C., the flow rate of HCl gas used is 1.0 L / min, and the pipes for HCl gas and argon are corundum tubes.

[0043] The result of this method shows that metal uranium reacts with HCl faster and more thoroughly, and the utilization rate of hydrogen chloride is 95%.

Embodiment 3

[0045] The method and steps used in Example 1 are the same, except that the heating temperature of the eutectic molten salt is 550 ° C. The chlorinated gas used is Cl 2 , the gas flow rate is 0.5L / min.

[0046] The results of this method show that metal uranium and Cl 2 The reaction is faster and more thorough, and the utilization rate of hydrogen chloride is 97%.

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PUM

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Abstract

The invention belongs to the technical field of nuclear fuel cycle dry after-treatment and discloses a method for preparing an initial molten salt system in a molten salt electrolysis dry after-treatment process. The method comprises the following steps: introducing chlorination gases into LiCl-KCl eutectic molten salt and spent fuel positioned in an electrolytic cell so as to introduce uranium ion into the molten salt, thereby obtaining the initial molten salt system needed by molten salt electrolysis dry after-treatment. The method has the advantages that the chlorination rate of the chlorination gases is high, the uranium ion can be introduced into the electrolytic cell in situ, and an extra uranium chloride production line does not need to be established.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel cycle dry post-processing, and in particular relates to a method for preparing an initial molten salt system in the dry post-processing process of molten salt electrolysis. Background technique [0002] Dry reprocessing is the key link to realize the closed fuel cycle of fourth-generation reactors. The molten salt electrochemical separation technology is currently the most in-depth research in the world and the most promising dry reprocessing technology. Molten salt electrolytic dry post-treatment uses the difference in redox potential of uranium, plutonium and split element ions in the molten salt system to separate uranium and plutonium from split elements, usually using LiCl-KCl eutectic molten salt as a solvent. In order to start the electrolysis reaction, alleviate the polarization phenomenon of the electrode reaction in the initial stage of electrolysis, and improve the purity of uraniu...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C25C3/34
CPCC25C3/34
Inventor 林如山何辉唐洪彬叶国安
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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