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Method suitable for continuously removing iodine in spent fuel dissolving liquid

A technology for dissolving liquid and spent fuel, used in reactor fuel elements, climate sustainability, nuclear power generation, etc., can solve problems such as the impact of kerosene reuse, entering solvent and water-phase waste liquid, etc., to reduce generation and increase use. Longevity, effect of solving pollution problems

Active Publication Date: 2020-12-04
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

During the spent fuel reprocessing process, most of the iodine will enter the tail gas produced by dissolution, and a small part will remain in the solution. Part of the iodine in the solution will enter the extraction process unit later, but some will enter the solvent and the aqueous phase waste liquid, and then spread to each process of the post-treatment process, which has a serious impact on the post-treatment process and the reuse of kerosene

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0022] A method suitable for continuously removing iodine from a spent fuel solution (where the uranium concentration is 250g / L and the iodine content is 400mg / L). After the spent fuel is oxidized and dissolved with nitric acid in a dissolution tank and filtered, the obtained spent The solution and the removal gas flow into the removal device simultaneously from the two inlets at the bottom of the column device. As a purge gas, nitrogen oxides react with nitric acid in the spent fuel solution to generate nitrous acid; iodide ions and iodate ions in the spent fuel solution undergo redox reactions with nitrous acid to generate molecular iodine, and then the iodine molecules are released by blowing air. The radioactive iodine in the spent fuel solution can be continuously removed by carrying it out.

[0023] Wherein the expelled gas is nitrogen oxide, and the volume ratio of each component under standard conditions is 10% of nitrogen monoxide, 40% of nitrogen dioxide, 20% of dini...

Embodiment 2

[0028] A method suitable for continuously removing iodine from a spent fuel solution (where the uranium concentration is 250g / L and the iodine content is 400mg / L). After the spent fuel is oxidized and dissolved with nitric acid in a dissolution tank and filtered, the obtained spent The solution and the removal gas flow into the removal device simultaneously from the two inlets at the bottom of the column device. As a purge gas, nitrogen oxides react with nitric acid in the spent fuel solution to generate nitrous acid; iodide ions and iodate ions in the spent fuel solution undergo redox reactions with nitrous acid to generate molecular iodine, and then the iodine molecules are released by blowing air. The radioactive iodine in the spent fuel solution can be continuously removed by carrying it out.

[0029] Wherein the expelled gas is nitrogen oxides, and the volume ratio of each component in a standard state is 50% of nitrogen dioxide, 10% of dinitrogen trioxide, and the rest i...

Embodiment 3

[0034] A method suitable for continuously removing iodine from a spent fuel solution (where the uranium concentration is 250g / L and the iodine content is 400mg / L). After the spent fuel is oxidized and dissolved with nitric acid in a dissolution tank and filtered, the obtained spent The solution and the removal gas flow into the removal device simultaneously from the two inlets at the bottom of the column device. As a purge gas, nitrogen oxides react with nitric acid in the spent fuel solution to generate nitrous acid; iodide ions and iodate ions in the spent fuel solution undergo redox reactions with nitrous acid to generate molecular iodine, and then the iodine molecules are released by blowing air. The radioactive iodine in the spent fuel solution can be continuously removed by carrying it out.

[0035] Wherein the expelled gas is nitrogen oxide, and the volume ratio of each component under the standard state is 20% of nitrogen monoxide, 50% of nitrogen dioxide, 10% of dinit...

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PUM

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Abstract

The invention belongs to the technical field of spent fuel post-treatment processes, and discloses a method for efficiently and continuously removing iodine in spent fuel post-treatment dissolving liquid. According to the method, oxynitride is used as expelling gas, iodine ions and iodate ions in the spent fuel dissolving solution are subjected to a chemical reaction through the expelling gas to generate molecular iodine, and then air is blown in to carry iodine molecules out, so that radioactive iodine in the spent fuel dissolving liquid can be continuously expelled. According to the method,the pollution of iodine to a post-treatment process can be avoided, the generation of organic iodine is reduced, the service life of the diluent is prolonged, iodine in the spent fuel element dissolving liquid is continuously expelled, and the expelling rate is as high as 95% or above.

Description

technical field [0001] The disclosure belongs to the technical field of spent fuel reprocessing technology, and in particular relates to a method for efficiently and continuously removing iodine from a spent fuel reprocessing solution. Background technique [0002] Iodine is one of the main fission products in spent fuel elements of power reactors, among which the long-lived 129 I has a half-life of up to 1.57×10 7 year. During the spent fuel reprocessing process, most of the iodine will enter the tail gas produced by dissolution, and a small part will remain in the solution. Part of the iodine in the solution will enter the extraction process unit later, but some will enter the solvent And the aqueous waste liquid, and then spread to each process of the post-treatment process, which has a serious impact on the post-treatment process and the reuse of kerosene. Therefore, it is necessary to take measures to drive iodine-129 out before the post-processing solvent extraction...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C19/50G21F9/00G21F9/06
CPCG21C19/50G21F9/001G21F9/06Y02E30/30Y02W30/50
Inventor 丛海峰肖松涛刘协春兰天李宝军
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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