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Method for treating uranium purified radioactive waste water

A radioactive waste water and waste water technology, applied in radioactive purification, nuclear engineering, etc., can solve the problems of secondary pollution and incomplete treatment effect, and achieve the effect of reducing treatment cost, improving treatment efficiency, safety and reliability, and reducing labor cost

Active Publication Date: 2018-06-19
BEIJING HANGTIAN XINFENG MECHANICAL EQUIP +1
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  • Abstract
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  • Application Information

AI Technical Summary

Problems solved by technology

[0004] The technical problem of the present invention is to overcome the problems of incomplete treatment effect and secondary pollution in the existing radioactive wastewater treatment system

Method used

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  • Method for treating uranium purified radioactive waste water

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Embodiment Construction

[0035] The radioactive waste water enters the pretreatment reactor, and the ozone gas is injected into the reactor for 10-60 minutes to generate a light yellow precipitate, and the uranium precipitate is recovered by plate and frame pressure filtration. The liquid enters the pretreatment reactor, and an excess of 20% barium carbonate ore powder is added according to the stoichiometric ratio, and heated and stirred for reaction. Filter out the debris through a plate and frame filter. The liquid enters the MVR evaporator and the three-effect evaporator for evaporation and concentration, and the steam enters the steam condensing device, and barium nitrate crystals are produced in the concentrated liquid. The concentrated solution is separated by sedimentation to separate the barium nitrate semi-finished product. The liquid enters the metathesis reaction kettle I, adding industrial barium carbonate powder, heating and stirring to undergo a metathesis reaction, and the reaction ge...

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Abstract

The invention relates to a method for treating radioactive waste water, in particular to a comprehensive method for treating uranium purified radioactive waste water. The method is the standard-achieving discharge processing of high-salt radioactive waste water containing uranium ions generated in the production process of uranium purifying, and the method is particularly suitable for the waste water discharged in the uranium purifying production process of nitric acid dissolving, organic solvent extracting and ammonium carbonate refining. According to the method, the uranium ions are thoroughly condensed and filtered based on special ingredients of witherite and the three-stage purifying technology process, wherein a large number of uranium ions are removed by neutralization and condensation through the witherite in an acid environment in the first stage of purifying, the uranium ions can be condensed under the actions of flocculent settling, ion absorption and like by adding the witherite or industrial barium carbonate in a neutralized environment in the second stage, and at the moment radioactive elements such as the uranium ions and the like are thoroughly removed by adding alkaline sodium carbonate to ensure that the solution is under an alkaline environment in the third stage.

Description

technical field [0001] The invention relates to a treatment method for radioactive waste water, in particular to a comprehensive treatment method for uranium-purified radioactive waste water. It is a standard discharge treatment of high-salt radioactive wastewater containing uranium ions produced in the uranium purification production process. It is especially suitable for the wastewater discharged from the uranium purification production process of nitric acid dissolution, organic solvent extraction and ammonium carbonate refining. This method is also suitable for treatment Other uranium-containing radioactive wastewater produced in the nitric acid hydrometallurgy process. Background technique [0002] Uranium purification is an extremely critical production link in the extraction process of nuclear raw materials, but the process will generate a large amount of uranium-containing wastewater. Taking a production facility with an annual output of 1,000 tons of metal uranium a...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/06G21F9/08
CPCG21F9/06G21F9/08
Inventor 边柳寻豪杰
Owner BEIJING HANGTIAN XINFENG MECHANICAL EQUIP
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