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CN116354400B - Method for solving nitrogen oxides generated in nitric acid dissolution process of triuranium octoxide product - Google Patents

Method for solving nitrogen oxides generated in nitric acid dissolution process of triuranium octoxide product Download PDF

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Publication number
CN116354400B
CN116354400B CN202111615783.0A CN202111615783A CN116354400B CN 116354400 B CN116354400 B CN 116354400B CN 202111615783 A CN202111615783 A CN 202111615783A CN 116354400 B CN116354400 B CN 116354400B
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nitric acid
nitrogen oxides
product
triuranium octoxide
dissolution process
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CN116354400A (en
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任燕
牛玉清
周志全
赵凤岐
舒祖骏
康绍辉
郑英
张海燕
叶开凯
曹令华
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Beijing Research Institute of Chemical Engineering and Metallurgy of CNNC
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Beijing Research Institute of Chemical Engineering and Metallurgy of CNNC
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    • CCHEMISTRY; METALLURGY
    • C01INORGANIC CHEMISTRY
    • C01GCOMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00Compounds of uranium
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

The invention relates to the field of uranium purification and conversion, in particular to a method for solving the problem of nitrogen oxides generated in the nitric acid dissolution process of a triuranium octoxide product. The method comprises the following steps: adding hydrogen peroxide and triuranium octooxide products into a nitric acid solution according to a proportion, and stirring for dissolution; the mol ratio of the triuranium octoxide product to the hydrogen peroxide is less than or equal to 1; the concentration of nitric acid is not less than 2.6mol/L. The method greatly reduces the generation amount of the nitrogen oxides in the dissolution process, relieves the pollution problem of the nitrogen oxides and improves the economic benefit of the process.

Description

Method for solving nitrogen oxides generated in nitric acid dissolution process of triuranium octoxide product
Technical Field
The invention relates to the field of uranium purification and conversion, in particular to a method for solving the problem of nitrogen oxides generated in the nitric acid dissolution process of a triuranium octoxide product.
Background
Triuranium octoxide (i.e., U 3O8) is the predominant uranium concentrate product. In the nitric acid dissolution process of the uranium purification conversion flow, the U 3O8 product has the problem of generating a large amount of nitrogen oxide harmful gas, which is not beneficial to the environmental protection economy of the working procedure.
Uranium in the U 3O8 material has low-valence +4-valence uranium and high-valence +6-valence uranium, and the nitric acid dissolution process of the uranium not only needs acidolysis, but also needs oxidation. When nitric acid is oxidized with the reducing substance +4 uranium, the reduced product is also poor depending on the concentration of nitric acid. Typically, concentrated nitric acid reacts with reducing substances to reduce to nitrogen dioxide and dilute nitric acid reacts with reducing substances to reduce to nitric oxide. When U 3O8 and nitric acid are dissolved in the same way, the following reaction occurs:
U 3O8+8HNO3 (rich) →3UO 2(NO3)2+2NO2↑+4H2 O
3U 3O8+20HNO3 (lean) to 9UO 2(NO3)2+2NO↑+10H2 O
The nitrogen oxides have different degrees of harm to human bodies and the environment, bring great environmental protection pressure to enterprises, need to be collected and treated by adopting a collecting device, and increase the production and operation costs.
Disclosure of Invention
The invention aims to solve the technical problems that: the method solves the problem of nitrogen oxide generation in the nitric acid dissolution process of the triuranium octoxide product, greatly reduces the generation amount of the nitrogen oxide in the dissolution process, relieves the pollution problem of the nitrogen oxide, and improves the economic benefit of the process.
The invention provides a method for solving the problem of generating nitrogen oxides in the nitric acid dissolution process of a triuranium octoxide product, which comprises the following steps:
adding hydrogen peroxide and triuranium octooxide products into a nitric acid solution according to a proportion, and stirring for dissolution;
the mol ratio of the triuranium octoxide product to the hydrogen peroxide is less than or equal to 1;
The concentration of nitric acid is not less than 2.6mol/L.
Preferably, the method specifically comprises the following steps:
Heating a nitric acid solution, adding hydrogen peroxide, uniformly mixing, and adding a triuranium octoxide product.
Preferably, the temperature of the heating is not higher than 60 ℃.
Preferably, the stirring is carried out for a period of time not less than 15 minutes.
Preferably, the concentration of the nitric acid solution is 3-6 mol/L.
Preferably, the uranium content of the triuranium octoxide product is 84.8%.
Compared with the prior art, the method for solving the problem that the U 3O8 generates nitrogen oxide gas in the nitric acid dissolution process solves the problem that the nitric acid dissolution process generates nitrogen oxide in the nitric acid dissolution process, reduces equipment investment and absorbs wastewater. The acid consumption of nitric acid dissolution is reduced, and the economic benefit is improved. The technology has the characteristics of economy, simplicity and practicability.
Detailed Description
For a further understanding of the present invention, embodiments of the invention are described below in conjunction with the examples, but it should be understood that these descriptions are merely intended to illustrate further features and advantages of the invention, and are not limiting of the invention.
The embodiment of the invention discloses a method for solving the problem of generating nitrogen oxides in the nitric acid dissolution process of a triuranium octoxide product, which comprises the following steps:
adding hydrogen peroxide and triuranium octooxide products into a nitric acid solution according to a proportion, and stirring for dissolution;
the mol ratio of the triuranium octoxide product to the hydrogen peroxide is less than or equal to 1;
The nitric acid concentration is not less than 2.6mol/L, preferably 3 to 6mol/L.
Preferably, the method specifically comprises the following steps:
Heating a nitric acid solution, adding hydrogen peroxide, uniformly mixing, and adding a triuranium octoxide product.
The temperature of the heating is not higher than 60 ℃.
The stirring and dissolving time is not less than 15 minutes.
The uranium content of the triuranium octoxide product is 84.8%.
The invention solves the problems of nitrogen oxide gas generation in the nitric acid dissolution process of 1) U 3O8, reduces equipment investment and wastewater absorption.
Uranium in the U 3O8 material has low-valence +4-valence uranium and high-valence +6-valence uranium, and the nitric acid dissolution process of the uranium not only needs acidolysis, but also needs oxidation. When nitric acid and reducing substances are subjected to oxidation reaction, the nitric acid is reduced into nitrogen oxides such as nitrogen dioxide, nitric oxide and the like, and the nitrogen oxides are additionally collected and treated by adopting a collecting device.
O 2 2- in the H 2O2 reagent belongs to a strong oxidant, and O 2 2- in the H 2O2 reagent and +4 uranium in the U 3O8 material are subjected to oxidation-reduction reaction by a method of adding the H 2O2 reagent in proportion, so that the following reaction occurs:
U3O8+H2O2+6HNO3→3UO2(NO3)2+4H2O
The method avoids that nitric acid is reduced into nitrogen oxides, can effectively solve the problem that U 3O8 generates nitrogen oxides in the nitric acid dissolution process, omits the investment of a nitrogen oxide absorption device, and reduces the generation of absorption wastewater.
2) The acid consumption of nitric acid dissolution is reduced, and the economic benefit is improved.
The nitric acid dissolution process of the U 3O8 material not only needs acidolysis, but also needs oxidation. According to the invention, through a method of adding the H 2O2 reagent in proportion, O 2 2- in the H 2O2 reagent and +4 uranium in the U 3O8 material are subjected to oxidation-reduction reaction, so that the consumption of nitric acid for the +4 uranium oxidation reaction in the dissolving process of the U 3O8 material is reduced.
In order to further understand the present invention, the method for solving the problem of generating nitrogen oxides in the nitric acid dissolution process of the triuranium octoxide product provided by the present invention is described in detail below with reference to examples, and the scope of protection of the present invention is not limited by the following examples.
Example 1
100Ml of nitric acid solution with the concentration of 6moL/L is adopted, the uranium content is calculated according to the concentration of 300g/L, the molar ratio of U 3O8 to H 2O2 is 1:1, the uranium content of U 3O8 is 84.8%, namely 35.4g of U 3O8 and 4.8g of H 2O2 reagent with the content of 30% are required to be added into 100moL of nitric acid solution. The nitric acid solution was warmed to 60 ℃ using a water bath thermostatic stirrer. And then adding the H 2O2 reagent into a nitric acid solution in advance, uniformly mixing, adding the U 3O8 product, stirring and dissolving for 15min, collecting and analyzing gas in the dissolving process, filtering the solution after dissolving, drying and weighing insoluble slag, calculating to obtain the dissolution rate of the uranium product of 98.01%, and measuring that the generation amount of nitrogen oxides in the dissolving process is reduced by more than 99% compared with the mode of dissolving the U 3O8 product without adding the H 2O2 reagent.
Example 2
100Ml of nitric acid solution with the concentration of 6moL/L is adopted, the uranium content is calculated according to the concentration of 300g/L, the molar ratio of U 3O8 to H 2O2 is 1:1.1, the uranium content of U 3O8 is 84.8%, namely 35.4g of U 3O8 and 5.2g of H 2O2 reagent with the content of 30% are required to be added into 100moL of nitric acid solution. The nitric acid solution was warmed to 60 ℃ using a water bath thermostatic stirrer. And adding the H 2O2 reagent into a nitric acid solution in advance, uniformly mixing, adding the U 3O8 product, stirring and dissolving for 15min, collecting and analyzing gas in the dissolving process, filtering the solution after dissolving, drying and weighing insoluble slag, calculating to obtain the dissolution rate of the uranium product as 97.98%, measuring the generation amount of nitrogen oxides in the dissolving process, and analyzing the result to show that the U 3O8 product hardly generates nitrogen oxides in the dissolving process.
Example 3
100Ml of solution with the nitric acid concentration of 3moL/L is adopted, the uranium content is calculated according to the concentration of 300g/L, the molar ratio of U 3O8 to H 2O2 is 1:1, the uranium content of U 3O8 is 84.8%, namely 35.4g of U 3O8 and 4.8g of H 2O2 reagent with the content of 30% are required to be added into 100moL of nitric acid solution. The nitric acid solution was warmed to 60 ℃ using a water bath thermostatic stirrer. And then adding the H 2O2 reagent into a nitric acid solution in advance, uniformly mixing, adding the U 3O8 product, stirring and dissolving for 30min, collecting and analyzing gas in the dissolving process, filtering the solution after dissolving, drying and weighing insoluble slag, calculating to obtain the dissolution rate of the uranium product as 96.83%, and measuring that the production amount of nitrogen oxides in the dissolving process is reduced by 99% compared with the mode of dissolving the U 3O8 product without adding the H 2O2 reagent.
Example 4
100Ml of nitric acid solution with the concentration of 3moL/L is adopted, the uranium content is calculated according to the concentration of 300g/L, the molar ratio of U 3O8 to H 2O2 is 1:1.1, the uranium content of U 3O8 is 84.8%, namely 35.4g of U 3O8 and 5.2g of H 2O2 reagent with the content of 30% are required to be added into 100moL of nitric acid solution. The nitric acid solution was warmed to 50 ℃ using a water bath thermostatic stirrer. And adding the H 2O2 reagent into a nitric acid solution in advance, uniformly mixing, adding the U 3O8 product, stirring and dissolving for 60min, collecting and analyzing gas in the dissolving process, filtering the solution after dissolving, drying and weighing insoluble slag, calculating to obtain the dissolution rate of the uranium product of 96.78%, measuring the generation amount of nitrogen oxides in the dissolving process, and analyzing the result to show that the U 3O8 product hardly generates nitrogen oxides in the dissolving process.
Example 5
100Ml of nitric acid solution with the concentration of 2.6moL/L is adopted, the uranium content is calculated according to the concentration of 300g/L, the molar ratio of U 3O8 to H 2O2 is 1:1.1, the uranium content of U 3O8 is 84.8%, namely 35.4g of U 3O8 and 5.2g of H 2O2 reagent with the content of 30% are required to be added into 100moL of nitric acid solution. The nitric acid solution was warmed to 60 ℃ using a water bath thermostatic stirrer. And adding the H 2O2 reagent into a nitric acid solution in advance, uniformly mixing, adding the U 3O8 product, stirring and dissolving for 60min, collecting and analyzing gas in the dissolving process, filtering the solution after dissolving, drying and weighing insoluble slag, calculating to obtain the dissolution rate of the uranium product of 96.13%, measuring the generation amount of nitrogen oxides in the dissolving process, and analyzing the result to show that the U 3O8 product hardly generates nitrogen oxides in the dissolving process.
The above description of the embodiments is only for aiding in the understanding of the method of the present invention and its core ideas. It should be noted that it will be apparent to those skilled in the art that various modifications and adaptations of the invention can be made without departing from the principles of the invention and these modifications and adaptations are intended to be within the scope of the invention as defined in the following claims.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.

Claims (5)

1. The method for solving the problem of generating nitrogen oxides in the nitric acid dissolution process of the triuranium octoxide product is characterized by comprising the following steps of:
heating a nitric acid solution, adding hydrogen peroxide, uniformly mixing, adding a triuranium octoxide product, and stirring for dissolution;
the mol ratio of the triuranium octoxide product to the hydrogen peroxide is less than or equal to 1;
the concentration of the nitric acid solution is not less than 2.6mol/L.
2. The method for solving the problem of nitrogen oxide generated in the nitric acid dissolution process of a triuranium octoxide product according to claim 1, characterized in that the temperature of the heating is not higher than 60 ℃.
3. The method for solving the problem of nitrogen oxide generation in the nitric acid dissolution process of a triuranium octoxide product according to claim 1, wherein the stirring dissolution time is not less than 15 minutes.
4. The method for solving the problem of nitrogen oxide generation in the nitric acid dissolution process of a triuranium octoxide product according to claim 1, wherein the concentration of the nitric acid solution is 3-6 mol/L.
5. The method for solving the problem of nitrogen oxides generated in the nitric acid dissolution process of a triuranium octoxide product according to claim 1, wherein the uranium content of the triuranium octoxide product is 84.8%.
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Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113772733A (en) * 2021-09-13 2021-12-10 中国科学院上海应用物理研究所 Water phase preparation method of anhydrous uranyl chloride

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JPH0717716A (en) * 1993-06-30 1995-01-20 Mitsubishi Materials Corp Production of uranyl fluoride
CN104597174A (en) * 2013-11-04 2015-05-06 青岛齐力铸钢有限公司 Isotope dilution mass spectrometry method for determining content of uranium in uranium niobium alloy
CN103866122B (en) * 2014-01-06 2015-11-04 东华理工大学 A method for microbial leaching of uranium and molybdenum ore and enrichment and separation of uranium and molybdenum
FR3017611B1 (en) * 2014-02-19 2016-03-18 Areva Nc PROCESS FOR ACTIVATION OF U3O8 FOR CONVERSION TO UO4 HYDRATE.
CN110921710B (en) * 2019-11-25 2022-05-03 南华大学 Preparation and application of uranium oxide with photocatalytic ciprofloxacin degradation activity

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113772733A (en) * 2021-09-13 2021-12-10 中国科学院上海应用物理研究所 Water phase preparation method of anhydrous uranyl chloride

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