CN102876891A - Method for recycling uranium in beryllium and uranium ores by agitation leaching - Google Patents
Method for recycling uranium in beryllium and uranium ores by agitation leaching Download PDFInfo
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- CN102876891A CN102876891A CN2012104080114A CN201210408011A CN102876891A CN 102876891 A CN102876891 A CN 102876891A CN 2012104080114 A CN2012104080114 A CN 2012104080114A CN 201210408011 A CN201210408011 A CN 201210408011A CN 102876891 A CN102876891 A CN 102876891A
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- uranium
- beryllium
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- leaching solution
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- 229910052770 Uranium Inorganic materials 0.000 title claims abstract description 73
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims abstract description 72
- 238000002386 leaching Methods 0.000 title claims abstract description 47
- 238000000034 method Methods 0.000 title claims abstract description 21
- 238000013019 agitation Methods 0.000 title claims abstract description 14
- 229910052790 beryllium Inorganic materials 0.000 title claims abstract description 14
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 title claims abstract description 14
- 238000004064 recycling Methods 0.000 title abstract 4
- 239000007788 liquid Substances 0.000 claims abstract description 36
- 238000000498 ball milling Methods 0.000 claims abstract description 18
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 claims abstract description 15
- 238000005342 ion exchange Methods 0.000 claims abstract description 11
- 239000007787 solid Substances 0.000 claims abstract description 11
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 claims abstract description 7
- 239000003456 ion exchange resin Substances 0.000 claims abstract description 7
- 229920003303 ion-exchange polymer Polymers 0.000 claims abstract description 7
- 239000003957 anion exchange resin Substances 0.000 claims abstract description 6
- 239000012141 concentrate Substances 0.000 claims abstract description 6
- 238000001035 drying Methods 0.000 claims abstract description 6
- 238000001179 sorption measurement Methods 0.000 claims abstract description 6
- 238000003756 stirring Methods 0.000 claims abstract description 6
- 229910002651 NO3 Inorganic materials 0.000 claims abstract description 3
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 claims abstract description 3
- 235000011114 ammonium hydroxide Nutrition 0.000 claims abstract description 3
- RFEYGZBHMYIJPY-UHFFFAOYSA-N beryllium uranium Chemical compound [Be].[U] RFEYGZBHMYIJPY-UHFFFAOYSA-N 0.000 claims description 25
- 238000000926 separation method Methods 0.000 claims description 16
- 238000001556 precipitation Methods 0.000 claims description 15
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical group OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 claims description 12
- QAOWNCQODCNURD-UHFFFAOYSA-N Sulfuric acid Chemical compound OS(O)(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-N 0.000 claims description 12
- 238000010521 absorption reaction Methods 0.000 claims description 10
- 238000002360 preparation method Methods 0.000 claims description 10
- 239000001117 sulphuric acid Substances 0.000 claims description 10
- 235000011149 sulphuric acid Nutrition 0.000 claims description 10
- 239000003513 alkali Substances 0.000 claims description 8
- VKJKEPKFPUWCAS-UHFFFAOYSA-M potassium chlorate Chemical compound [K+].[O-]Cl(=O)=O VKJKEPKFPUWCAS-UHFFFAOYSA-M 0.000 claims description 6
- 239000000284 extract Substances 0.000 claims description 5
- 238000013467 fragmentation Methods 0.000 claims description 5
- 238000006062 fragmentation reaction Methods 0.000 claims description 5
- NUJOXMJBOLGQSY-UHFFFAOYSA-N manganese dioxide Inorganic materials O=[Mn]=O NUJOXMJBOLGQSY-UHFFFAOYSA-N 0.000 claims description 5
- 238000006386 neutralization reaction Methods 0.000 claims description 5
- 239000012286 potassium permanganate Substances 0.000 claims description 5
- 229920006395 saturated elastomer Polymers 0.000 claims description 5
- 238000005406 washing Methods 0.000 claims description 5
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 claims description 4
- 239000011347 resin Substances 0.000 claims description 4
- 229920005989 resin Polymers 0.000 claims description 4
- 239000000203 mixture Substances 0.000 claims description 3
- 239000011780 sodium chloride Substances 0.000 claims description 3
- FAPWRFPIFSIZLT-UHFFFAOYSA-M sodium chloride Inorganic materials [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 claims description 3
- 239000002253 acid Substances 0.000 claims description 2
- 229910021529 ammonia Inorganic materials 0.000 claims description 2
- 239000003480 eluent Substances 0.000 claims description 2
- 230000008901 benefit Effects 0.000 abstract description 3
- 238000004062 sedimentation Methods 0.000 abstract 2
- VHUUQVKOLVNVRT-UHFFFAOYSA-N Ammonium hydroxide Chemical compound [NH4+].[OH-] VHUUQVKOLVNVRT-UHFFFAOYSA-N 0.000 abstract 1
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 0.000 abstract 1
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 abstract 1
- 230000002378 acidificating effect Effects 0.000 abstract 1
- 238000005188 flotation Methods 0.000 abstract 1
- 229910052739 hydrogen Inorganic materials 0.000 abstract 1
- 239000001257 hydrogen Substances 0.000 abstract 1
- 239000002002 slurry Substances 0.000 description 4
- 238000011084 recovery Methods 0.000 description 3
- 239000010438 granite Substances 0.000 description 2
- 239000002994 raw material Substances 0.000 description 2
- 239000011435 rock Substances 0.000 description 2
- 230000031068 symbiosis, encompassing mutualism through parasitism Effects 0.000 description 2
- 150000001224 Uranium Chemical class 0.000 description 1
- 230000007123 defense Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000005272 metallurgy Methods 0.000 description 1
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- 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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- Manufacture And Refinement Of Metals (AREA)
Abstract
Disclosed is a method for recycling uranium in beryllium and uranium ores by agitation leaching. The method includes placing raw ores crushed by means of ball-milling into a molten bath, adding leaching solution in the molten bath, stirring, separating solid from liquid when a pH (potential of hydrogen) value of ore pulp ranges from 1.5 to 2.5, and extracting leachate; adsorbing uranium in the leachate by strong-base anion exchange resin via an ion exchange unit, and rinsing the ion exchange resin by acidic nitrate or chloride to obtain qualified uranium liquid after adsorption saturation of the ion exchange resin is reached; and performing neutralized sedimentation for the qualified uranium liquid by sodium hydroxide or ammonia water, controlling a sedimentation process so that a final pH value ranges from 7 to 8, separating solid from the liquid, drying and dewatering to obtain a uranium concentrate with uranium content higher than 60%. The method for recycling of the uranium in the beryllium and uranium ores has the advantages of high uranium leaching rate, low cost, good economical benefit and the like, and the uranium leaching rate is higher than 90%. Besides, beryllium with the content higher than 90% is remained in tailings after the solid is separated from the liquid, flotation recycling for the beryllium in the tailings is unaffected, and the method provides a novel and effective path for developing and utilizing novel beryllium and uranium mine resources.
Description
Technical field
The present invention relates to technical field of wet metallurgy, particularly a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium.
Background technology
Uranium is important defense strategy goods and materials, also is important nuclear power raw material, and current nuclear energy still is considered to substitute on a large scale the most real selection of conventional energy resources, can be increasing as the uranium demand of nuclear power raw material.
At present, it is found that a kind of novel uranium ore resource, this uranium ore resource is the beryllium uranium ore, and the beryllium uranium ore body is mainly composed the contact zones that are stored in granite porphyry rock mass and country rock, apart from 20～50m about the end contact surface, also sporadicly be distributed with the beryllium uranium ore body at the granite porphyry contact zones.Development and use the type symbiosis uranium ore resource, and recovery uranium is one of important channel that enlarges natural uranium throughput from the type symbiosis uranium ore, also is that people are studying problem demanding prompt solution.
Summary of the invention
The purpose of this invention is to provide a kind of method that reclaims uranium from the beryllium uranium ore, it adopts the method for agitation leach to reclaim uranium from the beryllium uranium ore, and the tailings behind the Leaching Uranium continues the floatation recovery beryllium.
Technical scheme of the present invention is: a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, carry out according to the following steps:
A, broken ball milling: with ball milling after the fragmentation of beryllium uranium ore, ore grain size is not more than 65 orders behind the ball milling.
B, leaching: the raw ore behind the ball milling is put into bath, adding leaching solution stirs, the mass ratio of leaching solution and raw ore is 2～5:1, churning time is not less than 8 hours, when being 1.5～2.5, slurry pH carries out solid-liquid separation, extract leach liquor, the elutant of tailings is returned the preparation leaching solution after the solid-liquid separation.
C, ion-exchange: the uranium in the leach liquor is adopted strongly basic anion exchange resin absorption by ion exchange unit, adsorption tail liquid returns the preparation leaching solution, after ion exchange resin absorption is saturated, adopt acid nitrate or muriate to carry out drip washing, obtaining uranium concentration is 8～15 g.L
-1The uranium qualifying liquid.
D, precipitation: the uranium qualifying liquid adopts sodium hydroxide or ammonia neutralization precipitation, and control precipitation endpoint pH is 7～8, and the solid-liquid separation post-drying is anhydrated, and obtains uranium-bearing greater than 60% uranium concentrate.
The beryllium uranium ore of described A in the step: beryllium content is 0.05～1.0%, and uranium content is 0.04～1.0%.
The leaching solution of described B in the step is sulphuric acid soln and oxygenant, and wherein sulphuric acid soln concentration is 20～40 g.L
-1Oxygenant is hydrogen peroxide or for Potcrate or for potassium permanganate or for pyrolusite, perhaps be the composition of hydrogen peroxide, Potcrate, potassium permanganate, pyrolusite, oxygenant is determined its add-on according to the leaching solution redox potential, keeps the leaching solution current potential more than 550mV.
The strongly basic anion exchange resin model was 201x7 or macroporous resin during described C went on foot, and eluent is 1mol.L
-1NH
4NO
3+ 0.1molL
-1HNO
3Or 1molL
-1NaCl+0.05molL
-1H
2SO
4
Sodium hydroxide was solid piece alkali during described D went on foot, and solid piece alkali directly adds, and ammoniacal liquor is strong aqua, and concentration is 22～25%.
The present invention has following features:
1, adopts method provided by the invention from the beryllium uranium ore, to reclaim uranium, have the advantages such as the uranium leaching yield is high, cost is low, good in economic efficiency.
2, after the solid-liquid separation, the beryllium overwhelming majority is stayed in the tailings, without impact, provides a kind of new effective way for developing new beryllium uranium ore resource on the floatation recovery of beryllium in the tailings.
The invention will be further described below in conjunction with the drawings and specific embodiments.
Description of drawings
Accompanying drawing 1 is process flow sheet of the present invention.
Embodiment
Embodiment one, a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, carry out according to the following steps:
A, broken ball milling: be 0.05% with beryllium content, uranium content be after 1.0% the beryllium uranium ore fragmentation ball milling to-65 orders.
B, leaching: the raw ore behind the ball milling is put into bath, add leaching solution and stir, the mass ratio of leaching solution and raw ore is 2:1, churning time is 8 hours, slurry pH is to carry out solid-liquid separation at 1.50 o'clock, extracts leach liquor, and the elutant of tailings is returned the preparation leaching solution after the solid-liquid separation.
Leaching solution is sulphuric acid soln and oxygenant, and wherein sulphuric acid soln concentration is 40 g.L
-1, oxygenant is hydrogen peroxide, oxygenant is determined its add-on according to the leaching solution redox potential, keeps the leaching solution current potential more than 550mV.
C, ion-exchange: by ion exchange unit the uranium in the leach liquor is adopted the absorption of 201x7 strongly basic anion exchange resin, adsorption tail liquid returns the preparation leaching solution; After ion exchange resin absorption is saturated, adopt 1mol.L
-1NH
4NO
3+ 0.1molL
-1HNO
3Carry out drip washing, obtaining uranium concentration is 10.86 g.L
-1The uranium qualifying liquid.
D, precipitation: the uranium qualifying liquid adopts solid piece alkali neutralization precipitation, and solid piece alkali directly adds, and control precipitation endpoint pH is 7, and the solid-liquid separation post-drying is anhydrated, and obtains uranium-bearing greater than 60% uranium concentrate.
Embodiment two, a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, carry out according to the following steps:
A, broken ball milling: be 0.8% with beryllium content, uranium content be after 0.05% the beryllium uranium ore fragmentation ball milling to-100 orders.
B, leaching: the raw ore behind the ball milling is put into bath, add leaching solution and stir, the mass ratio of leaching solution and raw ore is 3:1, churning time is 10 hours, slurry pH is to carry out solid-liquid separation at 2.02 o'clock, extracts leach liquor, and the elutant of tailings is returned the preparation leaching solution after the solid-liquid separation.
Leaching solution is sulphuric acid soln and oxygenant, and wherein sulphuric acid soln concentration is 30 g.L
-1, oxygenant is Potcrate, oxygenant is determined its add-on according to the leaching solution redox potential, keeps the leaching solution current potential more than 550mV.
C, ion-exchange: by ion exchange unit the uranium in the leach liquor is adopted the absorption of D263 macroporous strong basic anionite-exchange resin, adsorption tail liquid returns the preparation leaching solution, after ion exchange resin absorption is saturated, adopts 1mol.L
-1NH
4NO
3+ 0.1molL
-1HNO
3Carry out drip washing, obtaining uranium concentration is 12.32 g.L
-1The uranium qualifying liquid.
D, precipitation: the uranium qualifying liquid adopts solid piece alkali neutralization precipitation, and solid piece alkali directly adds, and control precipitation endpoint pH is 7.5, and the solid-liquid separation post-drying is anhydrated, and obtains uranium-bearing greater than 60% uranium concentrate.
Embodiment three, a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, carry out according to the following steps:
A, broken ball milling: be 0.1% with beryllium content, uranium content be after 0.5% the beryllium uranium ore fragmentation ball milling to-200 orders.
B, leaching: the raw ore behind the ball milling is put into bath, add leaching solution and stir, the mass ratio of leaching solution and raw ore is 5:1, churning time is 12 hours, slurry pH is to carry out solid-liquid separation at 2.50 o'clock, extracts leach liquor, and the elutant of tailings is returned the preparation leaching solution after the solid-liquid separation.
Leaching solution is sulphuric acid soln and oxygenant, and wherein sulphuric acid soln concentration is 20 g.L
-1, oxygenant is the composition of hydrogen peroxide, Potcrate, potassium permanganate, pyrolusite, oxygenant is determined its add-on according to the leaching solution redox potential, keeps the leaching solution current potential more than 550mV.
C, ion-exchange: by ion exchange unit the uranium in the leach liquor is adopted the absorption of D263 macroporous strong basic anionite-exchange resin, adsorption tail liquid returns the preparation leaching solution, after ion exchange resin absorption is saturated, adopts 1molL
-1NaCl+0.05molL
-1H
2SO
4Carry out drip washing, obtaining uranium concentration is 13.62 g.L
-1The uranium qualifying liquid.
D, precipitation: it is 22～25% strong aqua neutralization precipitation that the uranium qualifying liquid adopts concentration, and control precipitation endpoint pH is 8, and the solid-liquid separation post-drying is anhydrated, and obtains uranium-bearing greater than 60% uranium concentrate.
Claims (5)
- One kind from the beryllium uranium ore agitation leach reclaim the method for uranium, it is characterized in that: carry out according to the following steps:A, broken ball milling: with ball milling after the fragmentation of beryllium uranium ore, ore grain size is not more than 65 orders behind the ball milling;B, leaching: the raw ore behind the ball milling is put into bath, adding leaching solution stirs, the mass ratio of leaching solution and raw ore is 2～5:1, churning time is not less than 8 hours, when being 1.5～2.5, the pH value in the ore pulp carries out solid-liquid separation, extract leach liquor, the elutant of tailings is returned the preparation leaching solution after the solid-liquid separation;C, ion-exchange: the uranium in the leach liquor is adopted strongly basic anion exchange resin absorption by ion exchange unit, adsorption tail liquid returns the preparation leaching solution, after ion exchange resin absorption is saturated, adopt acid nitrate or muriate to carry out drip washing, obtaining uranium concentration is 8～15 g.L -1The uranium qualifying liquid;D, precipitation: the uranium qualifying liquid adopts sodium hydroxide or ammonia neutralization precipitation, and control precipitation endpoint pH is 7～8, and the solid-liquid separation post-drying is anhydrated, and obtains uranium-bearing greater than 60% uranium concentrate.
- According to claim 1 a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, it is characterized in that: the beryllium uranium ore of described A in the step: beryllium content is 0.05～1.0%, and uranium content is 0.04～1.0%.
- According to claim 1 and 2 a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, it is characterized in that: the leaching solution of described B in the step is sulphuric acid soln and oxygenant, and wherein sulfuric acid concentration is 20～40 g.L in the sulphuric acid soln -1Oxygenant is hydrogen peroxide or for Potcrate or for potassium permanganate or for pyrolusite, perhaps be the composition of hydrogen peroxide, Potcrate, potassium permanganate, pyrolusite, oxygenant is determined its add-on according to the leaching solution redox potential, keeps the leaching solution current potential more than 550mV.
- According to claim 1 and 2 a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, it is characterized in that: described C in the step strongly basic anion exchange resin model be 201x7 or macroporous resin, eluent is 1mol.L -1NH 4NO 3+ 0.1molL -1HNO 3Or 1molL -1NaCl+0.05molL -1H 2SO 4
- According to claim 1 and 2 a kind of from the beryllium uranium ore agitation leach reclaim the method for uranium, it is characterized in that: described D in the step sodium hydroxide be solid piece alkali, solid piece alkali directly adds; Ammoniacal liquor is strong aqua, and concentration is 22～25%.
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Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN105420495A (en) * | 2015-11-17 | 2016-03-23 | 中国铝业股份有限公司 | Uranium separation method during gallium treatment in aluminum oxide production through Bayer process |
| CN105970007A (en) * | 2016-07-08 | 2016-09-28 | 东华理工大学 | Method for recovering associated rhenium resource from starved resin on basis of sandstone-type uranium ore in-situ leaching uranium process |
| CN106756130A (en) * | 2016-12-30 | 2017-05-31 | 核工业北京化工冶金研究院 | The device and method of uranium are extracted in a kind of ore pulp from high density |
| CN106932246A (en) * | 2015-12-30 | 2017-07-07 | 核工业北京地质研究院 | The preparation facilities and preparation method of a kind of radioactivity uranium ore standard substance |
| CN109482619A (en) * | 2018-12-06 | 2019-03-19 | 王少明 | A kind of industrial residue recovery and processing system |
| CN109761514A (en) * | 2019-02-14 | 2019-05-17 | 长沙中硅水泥技术开发有限公司 | Beryllium slag detoxification and cement kiln synergistic resource treatment system and process |
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| CN111020190A (en) * | 2019-12-10 | 2020-04-17 | 核工业北京化工冶金研究院 | Process linking method for extracting uranium by two-step ion exchange method |
| CN111215255A (en) * | 2019-12-02 | 2020-06-02 | 南华大学 | Method for recycling collecting agent for floating uranyl carbonate ions |
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| 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 |
| CN105420495A (en) * | 2015-11-17 | 2016-03-23 | 中国铝业股份有限公司 | Uranium separation method during gallium treatment in aluminum oxide production through Bayer process |
| CN106932246A (en) * | 2015-12-30 | 2017-07-07 | 核工业北京地质研究院 | The preparation facilities and preparation method of a kind of radioactivity uranium ore standard substance |
| CN106932246B (en) * | 2015-12-30 | 2020-02-18 | 核工业北京地质研究院 | A kind of preparation device and preparation method of radioactive uranium ore standard substance |
| CN105970007B (en) * | 2016-07-08 | 2018-02-27 | 东华理工大学 | A kind of method that association rhenium resource is reclaimed in the poor resin from sandstone-type uranium mineralization with respect ground dipping uranium extracting process |
| CN105970007A (en) * | 2016-07-08 | 2016-09-28 | 东华理工大学 | Method for recovering associated rhenium resource from starved resin on basis of sandstone-type uranium ore in-situ leaching uranium process |
| CN106756130A (en) * | 2016-12-30 | 2017-05-31 | 核工业北京化工冶金研究院 | The device and method of uranium are extracted in a kind of ore pulp from high density |
| CN106756130B (en) * | 2016-12-30 | 2019-02-26 | 核工业北京化工冶金研究院 | A kind of device and method for extracting uranium from high density ore pulp |
| CN109482619A (en) * | 2018-12-06 | 2019-03-19 | 王少明 | A kind of industrial residue recovery and processing system |
| CN109482619B (en) * | 2018-12-06 | 2021-12-21 | 徐佩登 | Industrial waste residue recovery processing system |
| CN109761514A (en) * | 2019-02-14 | 2019-05-17 | 长沙中硅水泥技术开发有限公司 | Beryllium slag detoxification and cement kiln synergistic resource treatment system and process |
| CN109939832B (en) * | 2019-04-10 | 2021-04-09 | 南华大学 | Manganese ore enrichment method combining selection and smelting |
| CN109939832A (en) * | 2019-04-10 | 2019-06-28 | 南华大学 | A kind of manganese ore enrichment method combined with beneficiation and smelting |
| CN111215255A (en) * | 2019-12-02 | 2020-06-02 | 南华大学 | Method for recycling collecting agent for floating uranyl carbonate ions |
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| CN111020190B (en) * | 2019-12-10 | 2021-10-22 | 核工业北京化工冶金研究院 | Process linking method for extracting uranium by two-step ion exchange method |
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