CN111020190B - Process linking method for extracting uranium by two-step ion exchange method - Google Patents

Process linking method for extracting uranium by two-step ion exchange method Download PDF

Info

Publication number
CN111020190B
CN111020190B CN201911258665.1A CN201911258665A CN111020190B CN 111020190 B CN111020190 B CN 111020190B CN 201911258665 A CN201911258665 A CN 201911258665A CN 111020190 B CN111020190 B CN 111020190B
Authority
CN
China
Prior art keywords
resin
leaching
uranium
ion exchange
solution
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201911258665.1A
Other languages
Chinese (zh)
Other versions
CN111020190A (en
Inventor
周志全
任燕
曹令华
牛玉清
赵凤岐
舒祖骏
曹笑豪
叶开凯
郑英
支梅峰
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Beijing Research Institute of Chemical Engineering and Metallurgy of CNNC
Original Assignee
Beijing Research Institute of Chemical Engineering and Metallurgy of CNNC
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Beijing Research Institute of Chemical Engineering and Metallurgy of CNNC filed Critical Beijing Research Institute of Chemical Engineering and Metallurgy of CNNC
Priority to CN201911258665.1A priority Critical patent/CN111020190B/en
Publication of CN111020190A publication Critical patent/CN111020190A/en
Application granted granted Critical
Publication of CN111020190B publication Critical patent/CN111020190B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/42Treatment or purification of solutions, e.g. obtained by leaching by ion-exchange extraction
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/04Extraction of metal compounds from ores or concentrates by wet processes by leaching
    • C22B3/06Extraction 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
    • C22B3/08Sulfuric acid, other sulfurated acids or salts thereof
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0221Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
    • C22B60/0226Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
    • C22B60/0234Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors sulfurated ion as active agent
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0265Obtaining 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

Landscapes

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

Abstract

The invention belongs to the technical field of uranium hydrometallurgy, and particularly relates to a process linking method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange. The method comprises the following steps: (1) carrying out first-step ion exchange in an acidic sulfuric acid leaching solution by using weak base resin to extract uranium to obtain saturated resin loaded with uranium; (2) washing the saturated resin loaded with uranium obtained in the step (1) with water to obtain washed resin; (3) leaching the washed resin; (4) periodically detecting the leacheate obtained in the step (3); (5) leaching the leached resin with mixed solution of sodium bicarbonate and sodium carbonate to obtain qualified leaching solution in one step; (6) adjusting the pH value of the qualified liquid obtained by the one-step leaching by using NaOH solution; (7) and (3) carrying out two-step adsorption by using strong basic resin. The method realizes the washing process of the carbonate on the resin, obtains the qualified washing liquid with higher concentration, and avoids the problem of gas generation in the washing process of the carbonate.

Description

Process linking method for extracting uranium by two-step ion exchange method
Technical Field
The invention belongs to the technical field of uranium hydrometallurgy, and particularly relates to a process linking method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange.
Background
In the existing industrial hydrometallurgy process of natural uranium, most ore leachate (obtained by stirring leaching, heap leaching or in-situ leaching) is subjected to ion exchange adsorption, or solvent extraction, or ion exchange and solvent extraction processes, and leaching solution or back extraction solution is obtained to perform uranium precipitation to obtain a natural uranium product. At present, a uranium extraction process adopting two-step ion exchange is not available.
At present, the uranium extraction leaching liquid is generally a sulfuric acid system. The ion exchange extraction of uranium by a sulfuric acid system generally adopts strong basic resin. The resin adsorbs sulfate and uranyl sulfate anion complexes. And leaching the saturated resin by using acid-containing sodium chloride, and replacing sulfate radical uranyl sulfate anion complexes by using chloride ions to obtain uranium leacheate containing a large amount of sulfate radicals. Adding alkali to obtain a uranium product.
The realization of resin two-step ion exchange uranium extraction has a plurality of difficulties. One important difficulty is that two-step ion exchange is difficult to join. One is that the eluent obtained by one-step ion exchange still has the characteristics of strong eluent, and is difficult to adsorb during two-step ion exchange. The reasons for this are manifold. One is that chlorine in the one-step eluent has a large proportion of chlorine remaining in the eluent, which adversely affects adsorption; but a large amount of sulfate radicals also have stronger leaching effect and can generate adverse effect on ion exchange; carbonate leaching generally has low leaching efficiency and low leaching solution concentration, and gas can be generated during leaching, so that saturated resin and leaching solution gradient are damaged.
In the conventional technical scheme, due to the defects, a process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is urgently needed to be developed, so that the problems are solved.
Disclosure of Invention
The invention aims to solve the technical problem of providing a process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange, solving the process connection problem of the two-step ion exchange uranium extraction process, and enabling two-step ion exchange resin to adsorb uranium in leacheate of one-step ion exchange.
In order to realize the purpose, the invention adopts the technical scheme that:
a process linking method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange comprises the following steps:
(1) carrying out first-step ion exchange in an acidic sulfuric acid leaching solution by using weak base resin to extract uranium to obtain saturated resin loaded with uranium;
(2) washing the saturated resin loaded with uranium obtained in the step (1) with water to obtain washed resin;
(3) leaching the washed resin
(3.1) draining the washing water, and adding a NaOH solution;
(3.2) standing for a set time, and continuously pumping NaOH solution to rinse the washed resin obtained in the step (2);
(4) periodically detecting the leacheate obtained in the step (3), finishing leaching when the amount of sulfate radicals reaches 0.1-2 g/L, and transferring to the step (5);
(5) leaching the leached resin with mixed solution of sodium bicarbonate and sodium carbonate to obtain qualified leaching solution in one step;
(6) adjusting the pH value of the qualified liquid obtained by the one-step leaching to 9.5-10.5 by using NaOH solution;
(7) and (4) carrying out two-step adsorption on the one-step leaching qualified liquid obtained in the step (6) after the pH value is adjusted by adopting strong basic resin.
Further, the process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described as follows, in step (1): the type of the weak base resin is one of D301, D302, D303 and D331.
Further, the process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described as follows, in step (1): the adsorption capacity of the weak alkaline resin to uranium is 5 mg/ml-80 mg/ml.
Further, the process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described as follows, in step (1): the volume of the acid sulfuric acid leaching solution is 10 BV-8000 BV, and the retention time is 5 min-30 min.
Further, the process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described as follows, and in the step (2): the volume of water is 1-3 BV, and the washing time is 5-30 min.
Further, a process linking method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described above, wherein in the step (3.1): the concentration of the NaOH solution is more than or equal to 80g/L, and the adding speed is more than or equal to 0.1 BV/min.
Further, a process linking method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described above, wherein in the step (3.2): standing for 15 min-2 h, and continuously pumping NaOH solution with the concentration of 40 g/L-160 g/L; contact time t for rinsing washed resinContact withIs 30 min-2 h.
Further, the process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described as follows, and in the step (5): the concentration of the sodium bicarbonate is 40-80 g/L, and the concentration of the sodium carbonate is 20-50 g/L; the leaching volume is 2-10 BV, and the first 1-5 BV is taken as qualified liquid for one-step leaching.
Further, the process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is described as follows, and in the step (7): the model of the strong basic resin is D201 x 7, and the adsorption capacity to uranium is 30 mg/ml-100 mg/ml; the adsorption retention time in the two-step adsorption is 0.5-2 h, and the adsorption volume is 8-80 BV.
The technical scheme of the invention has the beneficial effects that:
(1) the elution of the ion exchange weak-base resin in one step is realized, and the eluted resin can be circularly adsorbed.
(2) The method realizes the washing process of the carbonate on the resin, obtains the qualified washing liquid with higher concentration, and avoids the problem of gas generation in the washing process of the carbonate.
(3) By the process, sulfate radicals in the system are removed, and the problem that the sulfate radicals enter uranium products and become impurities is solved.
(4) Because no adverse effect of sulfate radicals on the two-step adsorption is caused, the adsorption capacity of the sulfate radicals on the two-step ion exchange can be greatly improved.
(5) And impurities such as molybdenum, vanadium and the like dissolved in strong basicity are favorably removed through the strong basicity leaching process.
(6) The obtained eluent can be used for two-step ion exchange adsorption, and the connection of two-step ion exchange is realized.
Drawings
FIG. 1 is a schematic process flow diagram of the present invention.
Detailed Description
The technical scheme of the invention is explained in detail in the following by combining the drawings and the specific embodiment.
As shown in figure 1, the invention relates to a process connection method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange, which comprises the following steps:
(1) carrying out first-step ion exchange in an acidic sulfuric acid leaching solution by using weak base resin to extract uranium to obtain saturated resin loaded with uranium;
the type of the weak base resin is one of D301, D302, D303 and D331; the adsorption capacity of the alkalescent resin to uranium is 5 mg/ml-80 mg/ml; the volume of the acid sulfuric acid leaching solution is 10 BV-8000 BV, and the retention time is 5 min-30 min.
(2) Washing the saturated resin loaded with uranium obtained in the step (1) with water to obtain washed resin;
the volume of water is 1-3 BV, and the washing time is 5-30 min.
(3) Leaching the washed resin
(3.1) draining the washing water, and adding a NaOH solution; the concentration of the NaOH solution is more than or equal to 80g/L, and the adding speed is more than or equal to 0.1 BV/min.
(3.2) standing for a set time, and continuously pumping NaOH solution to rinse the washed resin obtained in the step (2);
specifically, after standing for 15min to 2h, continuously pumping NaOH solution with the concentration of 40g/L to 160 g/L; contact time t for rinsing washed resinContact withIs 30 min-2 h.
(4) Periodically detecting the leacheate obtained in the step (3), finishing leaching when the amount of sulfate radicals reaches 0.1-2 g/L, and transferring to the step (5);
(5) leaching the leached resin with mixed solution of sodium bicarbonate and sodium carbonate to obtain qualified leaching solution in one step;
the concentration of the sodium bicarbonate is 40-80 g/L, and the concentration of the sodium carbonate is 20-50 g/L; the leaching volume is 2-10 BV, and the first 1-5 BV is taken as qualified liquid for one-step leaching.
(6) Adjusting the pH value of the qualified liquid obtained by the one-step leaching to 9.5-10.5 by using NaOH solution;
(7) performing two-step adsorption on the one-step leaching qualified liquid obtained in the step (6) after the pH value is adjusted by using strong basic resin;
the model of the strong basic resin is D201 x 7, and the adsorption capacity to uranium is 30 mg/ml-100 mg/ml; the adsorption retention time in the two-step adsorption is 0.5-2 h, and the adsorption volume is 8-80 BV.

Claims (1)

1. A process linking method for extracting uranium from a sulfuric acid system by adopting two-step ion exchange is characterized by comprising the following steps:
(1) carrying out first-step ion exchange in an acidic sulfuric acid leaching solution by using weak base resin to extract uranium to obtain saturated resin loaded with uranium;
(2) washing the saturated resin loaded with uranium obtained in the step (1) with water to obtain washed resin;
(3) leaching the washed resin
(3.1) draining the washing water, and adding a NaOH solution;
(3.2) standing for a set time, and continuously pumping NaOH solution to rinse the washed resin obtained in the step (2);
(4) periodically detecting the leacheate obtained in the step (3), finishing leaching when the amount of sulfate radicals reaches 0.1-2 g/L, and transferring to the step (5);
(5) leaching the leached resin with mixed solution of sodium bicarbonate and sodium carbonate to obtain qualified leaching solution in one step;
(6) adjusting the pH value of the qualified liquid obtained by the one-step leaching to 9.5-10.5 by using NaOH solution;
(7) performing two-step adsorption on the one-step leaching qualified liquid obtained in the step (6) after the pH value is adjusted by using strong basic resin;
in the step (1): the type of the weak base resin is one of D301, D302, D303 and D331; the adsorption capacity of the alkalescent resin to uranium is 5 mg/mL-80 mg/mL; the volume of the acid sulfuric acid leaching solution is 10 BV-8000 BV, and the retention time is 5 min-30 min;
in the step (2): the volume of water is 1-3 BV, and the washing time is 5-30 min;
in the step (3.1): the concentration of the NaOH solution is more than or equal to 80g/L, and the adding speed is more than or equal to 0.1 BV/min;
in the step (3.2): standing for 15 min-2 h, and continuously pumping NaOH solution with the concentration of 40 g/L-160 g/L; contact time t for rinsing washed resinContact withIs 30min to 2 h;
in the step (5): the concentration of the sodium bicarbonate is 40-80 g/L, and the concentration of the sodium carbonate is 20-50 g/L; leaching the qualified liquid at a leaching volume of 2-10 BV, and taking the first 1-5 BV as the qualified liquid for one-step leaching;
in the step (7): the model of the strong basic resin is D201 x 7, and the adsorption capacity of the strong basic resin to uranium is 30 mg/mL-100 mg/mL; the adsorption retention time in the two-step adsorption is 0.5-2 h, and the adsorption volume is 8-80 BV.
CN201911258665.1A 2019-12-10 2019-12-10 Process linking method for extracting uranium by two-step ion exchange method Active CN111020190B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201911258665.1A CN111020190B (en) 2019-12-10 2019-12-10 Process linking method for extracting uranium by two-step ion exchange method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201911258665.1A CN111020190B (en) 2019-12-10 2019-12-10 Process linking method for extracting uranium by two-step ion exchange method

Publications (2)

Publication Number Publication Date
CN111020190A CN111020190A (en) 2020-04-17
CN111020190B true CN111020190B (en) 2021-10-22

Family

ID=70205296

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201911258665.1A Active CN111020190B (en) 2019-12-10 2019-12-10 Process linking method for extracting uranium by two-step ion exchange method

Country Status (1)

Country Link
CN (1) CN111020190B (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112680608B (en) * 2020-12-16 2022-08-19 核工业北京化工冶金研究院 Method for extracting uranium from chlorinated carbonate system
CN115572848B (en) * 2022-09-26 2023-12-15 核工业北京化工冶金研究院 Technological method capable of realizing efficient leaching of uranium-bearing resin and regeneration of leaching agent

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RO122641B1 (en) * 2005-09-29 2009-10-30 Institutul Naţional De Cercetare-Dezvoltare Pentru Metale Şi Resurse Radioactive - Icpmrr Process for recovering uranium from acid uranium-bearing leach solutions by ion exchange
CN106507822B (en) * 2007-11-30 2011-02-16 核工业北京化工冶金研究院 The method for reclaiming uranium from the alkalescent leachate of high chloride ion high salinity
CN102031369A (en) * 2010-12-01 2011-04-27 核工业北京化工冶金研究院 Method for extracting uranium by using ion exchange fixed tower under alternate Ph condition
CN102477489A (en) * 2010-11-26 2012-05-30 韩国地质资源研究院 Uranium ion exchange adsorption method using ultrasound
CN106507827B (en) * 2009-12-10 2012-07-04 核工业北京化工冶金研究院 A kind of ion exchange with water closed cycle puies forward uranium technique
CN102876891A (en) * 2012-10-24 2013-01-16 南华大学 Method for recycling uranium in beryllium and uranium ores by agitation leaching
CN102876890A (en) * 2012-10-24 2013-01-16 南华大学 Method for recovering uranium from beryllium uranium ore with wet process
CN104531987A (en) * 2014-12-22 2015-04-22 核工业北京化工冶金研究院 Method for lowering leaching alkali consumption of alkaline uranium ore rich in gypsum

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RO122641B1 (en) * 2005-09-29 2009-10-30 Institutul Naţional De Cercetare-Dezvoltare Pentru Metale Şi Resurse Radioactive - Icpmrr Process for recovering uranium from acid uranium-bearing leach solutions by ion exchange
CN106507822B (en) * 2007-11-30 2011-02-16 核工业北京化工冶金研究院 The method for reclaiming uranium from the alkalescent leachate of high chloride ion high salinity
CN106507827B (en) * 2009-12-10 2012-07-04 核工业北京化工冶金研究院 A kind of ion exchange with water closed cycle puies forward uranium technique
CN102477489A (en) * 2010-11-26 2012-05-30 韩国地质资源研究院 Uranium ion exchange adsorption method using ultrasound
CN102031369A (en) * 2010-12-01 2011-04-27 核工业北京化工冶金研究院 Method for extracting uranium by using ion exchange fixed tower under alternate Ph condition
CN102876891A (en) * 2012-10-24 2013-01-16 南华大学 Method for recycling uranium in beryllium and uranium ores by agitation leaching
CN102876890A (en) * 2012-10-24 2013-01-16 南华大学 Method for recovering uranium from beryllium uranium ore with wet process
CN104531987A (en) * 2014-12-22 2015-04-22 核工业北京化工冶金研究院 Method for lowering leaching alkali consumption of alkaline uranium ore rich in gypsum

Also Published As

Publication number Publication date
CN111020190A (en) 2020-04-17

Similar Documents

Publication Publication Date Title
CN111020190B (en) Process linking method for extracting uranium by two-step ion exchange method
CN111876598B (en) Method for separating uranium and niobium through co-extraction
CN103789552B (en) Method for recovering rhenium from high-temperature alloy pickle liquor
CN111020186B (en) Method for comprehensively recycling uranium, niobium and titanium from uranium-niobium-titanium ore
US20150096412A1 (en) Nickel and cobalt recovery using continuous ion exchange
CN106507827B (en) A kind of ion exchange with water closed cycle puies forward uranium technique
CN103288172A (en) Recycling method of board washing wastewater produced in PCB (Printed Circuit Board) etching section
KR960029491A (en) Method for recovering antimony and bismuth from copper electrolytic solution
JP2013095979A (en) Metal recovering method
CN105420495B (en) In a kind of Bayer process alumina producing in gallium processing procedure uranium separation method
CN105567958B (en) Uranium molybdenum extraction separating method in high uranium molybdenum ore solution leachate
CN106460091A (en) Silver recovery by ion exchange
CN105420494B (en) A kind of Pb-Zn tailings leachate separation and concentration handling process
CN109971954A (en) A kind of abbreviated system preparing high-purity cobalt from low content nickel cobalt biochemical lixivium
KR101662725B1 (en) Method of extracting nickel and cobalt
CN109437343B (en) Preparation method of sodium pertechnetate solution
CN111087114A (en) Treatment method of tantalum-niobium production wastewater
CN109929998A (en) A kind of regeneration method of copper-molybdenum saturated resin
CN205999182U (en) Special Resin trundle bed acid-restoring plant
CN205687982U (en) A kind of system decomposing white tungsten fine ore
CN113699392B (en) Method for improving leaching rate of acid leaching uranium
CN110923470B (en) Comprehensive recovery process of zinc electrolysis waste liquid
RU2310692C1 (en) Gold saturated anion-exchange resins regeneration process
AU2014219373A1 (en) Continuous ion exchange process integrated with membrane separation for recovering uranium
CN112553484B (en) Method for improving flow benefit of uranium extraction by triple-fatty amine leaching

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant