CN111519048B - U-shaped uranium leaching device and method - Google Patents

U-shaped uranium leaching device and method Download PDF

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Publication number
CN111519048B
CN111519048B CN202010332291.XA CN202010332291A CN111519048B CN 111519048 B CN111519048 B CN 111519048B CN 202010332291 A CN202010332291 A CN 202010332291A CN 111519048 B CN111519048 B CN 111519048B
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resin
uranium
liquid outlet
inlet
tower
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CN111519048A (en
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程威
郑剑平
阙为民
周根茂
闻振乾
杜志明
李建华
胡柏石
霍建党
孟晋
杨立志
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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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    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0234—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors sulfurated ion as active agent
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/02—Apparatus therefor
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/04—Extraction of metal compounds from ores or concentrates by wet processes by leaching
    • C22B3/06—Extraction of metal compounds from ores or concentrates by wet processes by leaching in inorganic acid solutions, e.g. with acids generated in situ; in inorganic salt solutions other than ammonium salt solutions
    • C22B3/08—Sulfuric acid, other sulfurated acids or salts thereof
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20—Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/22—Treatment or purification of solutions, e.g. obtained by leaching by physical processes, e.g. by filtration, by magnetic means, or by thermal decomposition
    • C22B3/24—Treatment or purification of solutions, e.g. obtained by leaching by physical processes, e.g. by filtration, by magnetic means, or by thermal decomposition by adsorption on solid substances, e.g. by extraction with solid resins
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0265—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Environmental & Geological Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Inorganic Chemistry (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

A U-shaped structure uranium leaching device comprises a U-shaped structure tower body and a resin storage tank, wherein the left end of the U-shaped structure tower body is provided with a lean resin outlet and a leaching agent inlet; the upper part of the right end of the U-shaped structure tower body is connected with a resin storage tank, the resin storage tank is provided with a compressed air inlet, a primary saturated resin inlet and an overflow port, and the right end of the U-shaped structure tower body is provided with a tail liquid outlet.

Description

U-shaped uranium leaching device and method
Technical Field
The technology belongs to the technical field of uranium ore in-situ leaching, particularly relates to a technology and a system for leaching primary saturated resin generated by adsorption of leaching liquid obtained by acid leaching, relates to a technology and a system for efficiently leaching primary saturated resin generated by adsorption of leaching liquid obtained by acid leaching by adopting a U-shaped structure, and relates to a U-shaped leaching tower device.
Background
In domestic acid-method uranium leaching mines, sulfuric acid is mainly used as a leaching agent, and uranium mainly exists in an acid leaching solution in the form of uranyl sulfate. In-situ leaching mine and landscape smelting plants, an ion exchange system is generally adopted to recover uranium in a leaching solution, and because the uranium concentration of the in-situ leaching solution is low by an acid method, the ratio of the sulfate ion concentration to the uranyl ion concentration is high, and the two compete for high adsorption strength, the capacity of primary saturated resin generated by an adsorption tower is low, the uranium concentration of qualified liquid generated by direct leaching is low, and the product precipitation is not facilitated.
Aiming at low-capacity saturated resin generated by primary adsorption of acid-method ground leachate, two methods are mainly adopted for treatment at present. Firstly, a saturation re-adsorption process is adopted, U in qualified liquid is adsorbed and eluted through loaded resin, the saturation capacity of the resin is further improved, generated secondary saturated resin is eluted, and the concentration of the qualified liquid can be improved by multiple times; and secondly, adopting an elution extraction process, selectively extracting the uranium in the low-concentration eluted qualified liquid through an organic phase, and then enriching through back extraction.
By adopting a saturated reabsorption process, more than half of the eluted qualified liquid needs to be returned for reabsorption, and the generated saturated reabsorption tail liquid needs to be recycled for adsorption, so that the process is complex; between the adsorption tower and the transformation tower, equipment such as a saturation re-adsorption tower, a recovery adsorption tower, a 3-tower series countercurrent leaching and corresponding resin lifting tanks are needed, the equipment occupies a large area and has large investment, and the operation and the control are difficult.
The leaching extraction process is adopted, the extraction back extraction process is carried out after saturated resin is leached, the uranium in the enriched liquid is enriched and purified again, if the organic phase of the extraction water phase is not completely removed, adverse effects such as resin poisoning and the like can exist when the extraction water phase is mixed into an ion exchange system, and meanwhile, the organic extractant is used as a combustible substance and a non-environment-friendly reagent, and certain safety and environmental protection pressure also exists in storage and operation.
Disclosure of Invention
The invention aims to: by adopting a U-shaped structure leaching technology and a U-shaped structure leaching system, primary saturated resin generated by leaching the leachate in an acid method is adsorbed, the ion exchange process flow of the leachate in an acid method is simplified, the efficient enrichment of uranium in the leachate with low concentration in an acid method is realized, qualified uranium liquid meeting the precipitation requirement of a product is produced, and leached lean resin meeting the transformation requirement is produced.
The technical scheme of the invention is as follows: a U-shaped uranium leaching device comprises a U-shaped tower body and a resin storage tank, wherein the left end of the U-shaped tower body is provided with a lean resin outlet and a leaching agent inlet;
the upper part of the right end of the U-shaped structure tower body is connected with a resin storage tank, the resin storage tank is provided with a compressed air inlet, a primary saturated resin inlet and an overflow port, and the right end of the U-shaped structure tower body is provided with a tail liquid outlet;
and a qualified liquid outlet is arranged at the bottom of the U-shaped structure.
A filter screen is arranged on the tail liquid outlet.
A method for leaching a U-shaped uranium leaching device comprises the following steps:
s1: adding the primary saturated resin into the tower resin from the primary saturated resin inlet, and opening the lean resin outlet;
s2: opening an eluent inlet to add eluent, and opening a tail liquid outlet;
s3: performing countercurrent exchange on the eluent added in the step S2 and the resin added in the step S1 to form a uranium enrichment section, closing a tail liquid outlet and opening a qualified liquid outlet to obtain qualified liquid when the uranium enrichment section is positioned at the qualified liquid outlet;
s4: and when the concentration of the qualified liquid is lower than 30g/L, closing the eluent inlet and the qualified liquid outlet, opening the primary saturated resin inlet, adding the resin into the tower, and opening the lean resin outlet 9 to discharge the lean resin.
Further comprising S5: s2 through S4 are repeated.
In the S1, D231YT is adopted as the tower entering resin.
In S1, the adsorption capacity is 14 mg/mLWR.
In the S2, the eluting agent adopts 1MNN4HCO3+1MH2SO4The linear velocity of the empty tower is 0.5-1.0 m/h.
In the step S3, the qualified liquid is a uranium enrichment section.
In the S4, the tower resin output capacity is <1 mg/mLWR.
The invention has the following remarkable effects:
1) the ion exchange process flow of the acid leaching liquid is simplified. Compared with the leachate treatment process adopted in the domestic acid leaching mountain, the U-shaped structure leaching technology and the U-shaped structure leaching system simplify the process flow, reduce the number of devices and control steps, reduce the redundant resin exchange height, and reduce the fixed asset investment of a newly-built hydrometallurgy plant.
2) Compared with the leaching and extraction process, the method avoids adopting an organic phase, and reduces the safety and environmental protection pressure in the production process of the in-situ leaching hydrometallurgy.
3) The number of devices and control steps are reduced, and automatic control and accurate control are facilitated.
Drawings
FIG. 1 is a schematic diagram of a U-shaped uranium leaching device;
in the figure: a resin storage tank 1, a compressed air inlet 2, a primary saturated resin inlet 3, an overflow port 4, a tail liquid outlet 5, a qualified liquid outlet 6, a filter screen 7, a U-shaped tower body 8, a lean resin outlet 9 and an eluent inlet 10
Detailed Description
A U-shaped uranium leaching device comprises a U-shaped tower body 8 and a resin storage tank 1, wherein the left end of the U-shaped tower body 8 is provided with a lean resin outlet 9 and a leaching agent inlet 10;
the upper part of the right end of the U-shaped structure tower body 8 is connected with a resin storage tank 1, the resin storage tank 1 is provided with a compressed air inlet 2, a primary saturated resin inlet 3 and an overflow port 4, the right end of the U-shaped structure is provided with a tail liquid outlet 5, and the tail liquid outlet 5 is provided with a filter screen 7;
a qualified liquid outlet 6 is arranged at the bottom of the U-shaped structure;
a U-shaped structure uranium leaching method comprises the following steps:
s1: the resin entering the tower is added from a primary saturated resin inlet 3, D231YT is adopted as the resin entering the tower, the adsorption capacity is 14mg/mLWR, and a lean resin outlet 9 is opened.
S2: opening eluent inlet 10, adding eluent with 1MNN4HCO3+1MH2SO4The linear velocity of the empty tower is 0.5-1.0 m/h, and a tail liquid outlet 5 is opened.
S3: and (3) performing countercurrent exchange on the eluent added in the S2 and the resin added in the S1 to form a uranium enrichment section, closing the tail liquid outlet 5 and opening the qualified liquid outlet 6 when the uranium enrichment section is positioned at the position of the qualified liquid outlet 6, and discharging qualified liquid, namely the uranium enrichment section.
S4: when the concentration of the qualified liquid is lower than 30g/L, closing the eluent inlet 10 and the qualified liquid outlet 6, opening the primary saturated resin inlet 3, adding the resin into the tower, opening the lean resin outlet 9, discharging the lean resin, wherein the capacity of the resin discharged from the tower is less than 1 mg/mLWR.
S5: s2 through S4 are repeated.

Claims (8)

1. The utility model provides a U type structure uranium leaching device which characterized in that: comprises a U-shaped structure tower body (8) and a resin storage tank (1), wherein the left end of the U-shaped structure tower body (8) is provided with a poor resin outlet (9) and an eluent inlet (10);
the upper part of the right end of the U-shaped structure tower body (8) is connected with a resin storage tank (1), the resin storage tank (1) is provided with a compressed air inlet (2), a primary saturated resin inlet (3) and an overflow port (4), and the right end of the U-shaped structure is provided with a tail liquid outlet (5);
a qualified liquid outlet (6) is arranged at the bottom of the U-shaped structure;
a filter screen (7) is arranged on the tail liquid outlet (5).
2. A uranium leaching method applying the U-shaped uranium leaching device according to claim 1, wherein the U-shaped uranium leaching device is characterized in that: the method comprises the following steps:
s1: adding the primary saturated resin into the tower resin from the primary saturated resin inlet (3), and opening the lean resin outlet (9);
s2: opening an eluent inlet (10), adding eluent, and opening a tail liquid outlet (5);
s3: the eluent added in the S2 and the resin added in the S1 perform countercurrent exchange to form a uranium enrichment section, when the uranium enrichment section is positioned at the qualified liquid outlet (6), the tail liquid outlet (5) is closed, and the qualified liquid outlet (6) is opened to obtain qualified liquid;
s4: when the concentration of the qualified liquid is lower than 30g/L, closing the eluent inlet (10) and the qualified liquid outlet (6), opening the primary saturated resin inlet (3), adding the tower resin, and opening the lean resin outlet (9) to discharge the lean resin.
3. A uranium leaching method according to claim 2, wherein: further comprising S5: s2 through S4 are repeated.
4. A uranium leaching method according to claim 2, wherein: in the S1, D231YT is adopted as the tower entering resin.
5. A uranium leaching method according to claim 4, wherein: in S1, the adsorption capacity is 14 mg/mLWR.
6. A uranium leaching method according to claim 4, wherein: in the step S2, 1M NN is adopted as eluent4HCO3+1M H2SO4The linear velocity of the empty tower is 0.5-1.0 m/h.
7. A uranium leaching method according to claim 4, wherein: in the step S3, the qualified liquid is a uranium enrichment section.
8. A uranium leaching method according to claim 4, wherein: in the S4, the tower resin output capacity is <1 mg/mLWR.
CN202010332291.XA 2020-04-24 2020-04-24 U-shaped uranium leaching device and method Active CN111519048B (en)

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Publication number Priority date Publication date Assignee Title
CN112143886A (en) * 2020-09-10 2020-12-29 核工业北京化工冶金研究院 W-shaped fixed bed leaching device and method
CN114192195A (en) * 2021-12-09 2022-03-18 中核内蒙古矿业有限公司 Elution device for uranium extraction by ion exchange method and elution method of ion exchange resin

Citations (4)

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Publication number Priority date Publication date Assignee Title
CN2064265U (en) * 1989-07-28 1990-10-24 济南市长清张夏水暖器材厂 U-shaped combined ion-exchanger
CN2085368U (en) * 1991-01-26 1991-09-25 董延年 U type co- and counter-current ion-exchanger
CN206631600U (en) * 2017-03-06 2017-11-14 武汉轻工大学 A kind of U-shaped ion exchange column
CN210150770U (en) * 2019-06-28 2020-03-17 济南巨力热能科技有限公司 U-shaped counter-current regeneration ion exchanger

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GB813269A (en) * 1955-01-04 1959-05-13 Commw Scient Ind Res Org Improvements in and relating to the extraction of uranium
CN2039998U (en) * 1988-12-17 1989-06-28 孙荣清 Tube type ion-exchanger
CN205774727U (en) * 2016-06-02 2016-12-07 中核第四研究设计工程有限公司 A kind of movable fixed-bed eluting column
CN107460314B (en) * 2016-06-02 2019-09-17 中核第四研究设计工程有限公司 Packed moving bed ion exchange eluting column
CN110624275A (en) * 2018-06-25 2019-12-31 中核第四研究设计工程有限公司 Uranium ore hydrometallurgy leakage-proof environment-friendly type dense moving bed adsorption tower and use method

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN2064265U (en) * 1989-07-28 1990-10-24 济南市长清张夏水暖器材厂 U-shaped combined ion-exchanger
CN2085368U (en) * 1991-01-26 1991-09-25 董延年 U type co- and counter-current ion-exchanger
CN206631600U (en) * 2017-03-06 2017-11-14 武汉轻工大学 A kind of U-shaped ion exchange column
CN210150770U (en) * 2019-06-28 2020-03-17 济南巨力热能科技有限公司 U-shaped counter-current regeneration ion exchanger

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