CN106834686A - In a kind of gallium production procedure except uranium technique - Google Patents
In a kind of gallium production procedure except uranium technique Download PDFInfo
- Publication number
- CN106834686A CN106834686A CN201510885233.9A CN201510885233A CN106834686A CN 106834686 A CN106834686 A CN 106834686A CN 201510885233 A CN201510885233 A CN 201510885233A CN 106834686 A CN106834686 A CN 106834686A
- Authority
- CN
- China
- Prior art keywords
- gallium
- solid
- liquid
- uranium
- added
- 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.)
- Granted
Links
Landscapes
- Electrolytic Production Of Metals (AREA)
- Manufacture And Refinement Of Metals (AREA)
Abstract
The invention belongs to radioactive element recovery technology field, and in particular in a kind of gallium production procedure except uranium technique.The present invention is comprised the following steps：To ferrous sulfate or reduced iron powder is added in the sulfuric acid desorption liquid of gallium, with sodium hydrate regulator solution to alkalescence after stirring and dissolving；Vulcanized sodium is added, stirring and dissolving is simultaneously staticly settled；Withdrawal liquid part after separation of solid and liquid, solid portion is uranium-bearing tailings；Solution to acidity is adjusted to the concentrated sulfuric acid is added in the liquid for reclaiming；Solid gallium mud is obtained after separation of solid and liquid；Gallium mud lysate is obtained to sodium hydroxide solution is added in gallium mud；Electrolysis obtains thick gallium.The present invention solves the technical problem relatively low except the uranium technique gallium rate of recovery in existing gallium production procedure, significantly improves the purity and quality of gallium product, and the rate of recovery of gallium effectively improves.
Description
Technical field
The invention belongs to radioactive element recovery technology field, and in particular to removing in a kind of gallium production procedure
Uranium technique.
Background technology
At present, the production of gallium is mainly carried out using gallium special efficacy chelating resin to the process liquid that Bayer process produces aluminium
Selective absorption, gallium special efficacy chelating resin can effectively reclaim the gallium ion in alkaline solution.As shown in figure 1,
The resin of adsorption saturation is eluted through sulfuric acid, neutralizes the series of processes acquisition phase such as separation, precipitation dissolving, removal of impurities
Gallium electrolyte should be electrolysed, gallium product is obtained after electrolysis.
But, gallium specific resin also has certain suction-operated to radioactive nucleus uranium in above-mentioned technique.
Uranyl ion can form complex anion, uranyl complex anion and inclined gallic acid radical ion portion in strong alkali solution
Point property is similar, and the trend of uranium reaches unanimity with the trend of gallium in the production procedure of gallium, only small part
Uranium is separated in removal of impurities workshop section, and most of uranium is together adsorbed with gallium ion by gallium specific resin.
It is present in production of the impurity uranium in gallium electrolyte to gallium mainly to be endangered with following both sides：One
Aspect, electroaffinity and the gallium of uranium are approached, and it has the electrolysis for having a strong impact on gallium so that mixed in gallium product
Miscellaneous uranium impurity, influences the purity and quality of gallium product；On the other hand, uranium is a kind of radionuclide, if
Without effectively removal, the content of the content up to several percentage points of uranium in gallium product is obtained after electrolysis,
Influence the health of practitioner.Meanwhile, radioactive nucleus uranium is also a kind of valuable resource, when containing for uranium
Amount is necessary reasonably to be recycled when exceeding certain value, can be neglected when the content of uranium is less than certain value
Slightly it reclaims meaning.
In the prior art, it is that complexing is added before electrolysis that the way used in uranium technique is removed in gallium production procedure
Be complexed for uranium by agent, but the technical scheme causes the rate of recovery of gallium relatively low.Therefore, it is necessary to be produced to gallium
During radioactive nucleus uranium separated, the difficult point of separating technology be uranium in system content it is low,
Matrix component is complicated；The technological process of production of gallium is complicated, and the change of any workshop section can influence whole flow process.
The content of the invention
The technical problem to be solved in the invention is：Being electrolysed except uranium technique is used in existing gallium production procedure
The preceding technical scheme for adding complexing agent to be complexed uranium, causes the gallium rate of recovery relatively low.
Technical scheme is as described below：
In a kind of gallium production procedure except uranium technique, comprise the following steps：
Step one：To solid sulphuric acid ferrous salt or reduced iron powder is added in the sulfuric acid desorption liquid of gallium, fully stir
Solution is adjusted to pH=10~13 with solid sodium hydroxide after mixing dissolving, vulcanized sodium solid is added, and is fully stirred
Dissolving is mixed, is staticly settled；
Step 2：Withdrawal liquid part after separation of solid and liquid, solid portion is uranium-bearing tailings；
Step 3：To the concentrated sulfuric acid is slowly added in the liquid for reclaiming, solution to pH=5~9 is adjusted；
Step 4：Solid gallium mud is obtained after separation of solid and liquid；
Step 5：To saturation sodium hydroxide solution or sodium hydrate solid dissolving gallium mud is added in gallium mud, obtain
To gallium mud lysate；
Step 6：Electrolysis, obtains thick gallium.
Beneficial effects of the present invention are：
(1) in a kind of gallium production procedure of the invention except uranium technique, gallium produces after being separated except uranium
To be smoothed out, the purity and quality of gallium product are significantly improved；
(2) in a kind of gallium production procedure of the invention except uranium technique, the rate of recovery of gallium is effectively carried
It is high；
(3) in a kind of gallium production procedure of the invention except uranium technique, effectively reduce existing gallium production stream
Vulcanize the shortcoming of sodium waste electric energy present in journey electrolyte；
(4) in a kind of gallium production procedure of the invention except uranium technique, it is to avoid radiated in gallium production procedure
Harm of the property nucleic to practitioner.
Brief description of the drawings
Fig. 1 is gallium production procedure in the prior art；
Fig. 2 is gallium production procedure of the invention.
Specific embodiment
With reference to the accompanying drawings and examples to a kind of gallium production procedure of the invention in carry out in detail except uranium technique
Describe in detail bright.
In a kind of gallium production procedure of the invention except uranium technique, comprise the following steps：
Step one：To solid sulphuric acid ferrous salt or reduced iron powder is added in the sulfuric acid desorption liquid of gallium, fully stir
Solution is adjusted to pH=10~13 with solid sodium hydroxide after mixing dissolving, appropriate vulcanized sodium solid is added, and is filled
Divide stirring and dissolving, staticly settle；
Step 2：Withdrawal liquid part after separation of solid and liquid, solid portion is uranium-bearing tailings；
Step 3：To the appropriate concentrated sulfuric acid is slowly added in the liquid for reclaiming, solution to pH=5~9 is adjusted；
Step 4：Solid gallium mud is obtained after separation of solid and liquid；
Step 5：To saturation sodium hydroxide solution or sodium hydrate solid dissolving gallium mud is added in gallium mud, obtain
To gallium mud lysate；
Step 6：Electrolysis, obtains thick gallium.
Embodiment 1
Step one：It is about the 100m of 12 μ g/mL to uranium content3Solid sulfur is added in the sulfuric acid desorption liquid of gallium
Sour ferrous iron 15.0kg, is adjusted to pH=10.0 after being sufficiently stirred for dissolving with solid sodium hydroxide, adds 3.0kg
Vulcanized sodium solid, is sufficiently stirred for dissolving, staticly settles；
Step 2：Liquid portion is collected after separation of solid and liquid, solid portion is uranium-bearing tailings, gallium in solution
The rate of recovery>94%, the clearance ＞ 95% of uranium；
Step 3：To being slowly added to the appropriate concentrated sulfuric acid while stirring in the liquid collected, regulation solution to
PH=9.0, standing obtains white solid precipitation, the rate of recovery ＞ 95% of gallium；
Step 4：Solid gallium mud is obtained after separation of solid and liquid；
Step 5：To adding saturation sodium hydroxide solution to be sufficiently stirred in gallium mud, until gallium mud dissolves, obtain
To gallium mud lysate；
Step 6：Electrolysis gallium mud lysate, obtains thick gallium.
Embodiment 2
Step one：It is about the 100m of 18 μ g/mL to uranium content3Solid sulfur is added in the sulfuric acid desorption liquid of gallium
Sour ferrous iron 10.0kg, is adjusted to pH=11.0 after being sufficiently stirred for dissolving with solid sodium hydroxide, adds 6.0kg
Vulcanized sodium solid, is sufficiently stirred for dissolving, staticly settles；
Step 2：Liquid portion is collected after separation of solid and liquid, solid portion is uranium-bearing tailings, gallium in solution
The rate of recovery>96%, the clearance ＞ 99% of uranium；
Step 3：To being slowly added to the appropriate concentrated sulfuric acid while stirring in the liquid collected, regulation solution to
PH=8.0, standing obtains white solid precipitation, the rate of recovery ＞ 99% of gallium；
Step 4：Solid gallium mud is obtained after separation of solid and liquid；
Step 5：To adding saturation sodium hydroxide solution to be sufficiently stirred in gallium mud, until gallium mud dissolves, obtain
To gallium mud lysate；
Step 6：Electrolysis gallium mud lysate, obtains thick gallium.
Embodiment 3
Step one：It is about the 00m of 6 μ g/mL to 1 uranium content3Solid sulfur is added in the sulfuric acid desorption liquid of gallium
Sour ferrous ammonium 3.0kg, is adjusted to pH=12.0 after being sufficiently stirred for dissolving with solid sodium hydroxide, is added
5.0kg vulcanized sodium solids, are sufficiently stirred for dissolving, staticly settle；
Step 2：Liquid portion is collected after separation of solid and liquid, solid portion is uranium-bearing tailings, gallium in solution
The rate of recovery>99%, the clearance ＞ 96% of uranium；
Step 3：To being slowly added to the appropriate concentrated sulfuric acid while stirring in the liquid collected, regulation solution to
PH=6.5, standing obtains white solid precipitation；
Step 4：Solid gallium mud is obtained after separation of solid and liquid；
Step 5：To adding saturation sodium hydroxide solution to be sufficiently stirred in gallium mud, until gallium mud dissolves, obtain
To gallium mud lysate；
Step 6：Electrolysis gallium mud lysate, obtains thick gallium.
Embodiment 4
Step one：It is about the 100m of 26 μ g/mL to uranium content3Solid is added in the sulfuric acid desorption liquid of gallium also
Former iron powder 3.0kg, is adjusted to pH=13.0 after being sufficiently stirred for dissolving with solid sodium hydroxide, adds 7.0kg
Vulcanized sodium solid, is sufficiently stirred for dissolving, staticly settles；
Step 2：Liquid portion is collected after separation of solid and liquid, solid portion is uranium-bearing tailings, gallium in solution
The rate of recovery>99%, the clearance ＞ 95% of uranium；
Step 3：To being slowly added to the appropriate concentrated sulfuric acid while stirring in the liquid collected, regulation solution to
PH=5.0, standing obtains white solid precipitation；
Step 4：Solid gallium mud is obtained after separation of solid and liquid；
Step 5：To adding saturation sodium hydroxide solution to be sufficiently stirred in gallium mud, until gallium mud dissolves, obtain
To gallium mud lysate；
Step 6：Electrolysis gallium mud lysate, obtains thick gallium.
Claims (2)
1. in a kind of gallium production procedure except uranium technique, it is characterised in that：Comprise the following steps：
Step one：To solid sulphuric acid ferrous salt or reduced iron powder is added in the sulfuric acid desorption liquid of gallium, fully stir
Solution is adjusted to pH=10~13 with solid sodium hydroxide after mixing dissolving, vulcanized sodium solid is added, and is fully stirred
Dissolving is mixed, is staticly settled；
Step 2：Withdrawal liquid part after separation of solid and liquid, solid portion is uranium-bearing tailings；
Step 3：To the concentrated sulfuric acid is slowly added in the liquid for reclaiming, solution to pH=5~9 is adjusted；
Step 4：Solid gallium mud is obtained after separation of solid and liquid；
Step 5：To NaOH dissolving gallium mud is added in gallium mud, gallium mud lysate is obtained；
Step 6：Electrolysis, obtains thick gallium.
2. in a kind of gallium production procedure according to claim 1 except uranium technique, it is characterised in that：
In step 5, the NaOH is saturation sodium hydroxide solution or sodium hydrate solid.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510885233.9A CN106834686B (en) | 2015-12-04 | 2015-12-04 | Uranium technique is removed in a kind of gallium production procedure |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510885233.9A CN106834686B (en) | 2015-12-04 | 2015-12-04 | Uranium technique is removed in a kind of gallium production procedure |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106834686A true CN106834686A (en) | 2017-06-13 |
| CN106834686B CN106834686B (en) | 2018-07-27 |
Family
ID=59151102
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510885233.9A Active CN106834686B (en) | 2015-12-04 | 2015-12-04 | Uranium technique is removed in a kind of gallium production procedure |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106834686B (en) |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2780519A (en) * | 1950-12-21 | 1957-02-05 | Kaufman David | Recovery of uranium from ores |
| JPS5817130B2 (en) * | 1980-04-02 | 1983-04-05 | 理化学研究所 | Manufacturing method of ultra-high purity alumina |
| CN102527493A (en) * | 2010-12-15 | 2012-07-04 | 核工业北京地质研究院 | Uranium and beryllium separating technology for ore containing uranium and beryllium |
| CN102741433A (en) * | 2010-02-02 | 2012-10-17 | 奥图泰有限公司 | Extraction process |
| CN102747225A (en) * | 2012-07-10 | 2012-10-24 | 中南大学 | Method for comprehensively recycling copper, selenium and uranium from stone coal extraction vanadic acid immersion liquid |
-
2015
- 2015-12-04 CN CN201510885233.9A patent/CN106834686B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2780519A (en) * | 1950-12-21 | 1957-02-05 | Kaufman David | Recovery of uranium from ores |
| JPS5817130B2 (en) * | 1980-04-02 | 1983-04-05 | 理化学研究所 | Manufacturing method of ultra-high purity alumina |
| CN102741433A (en) * | 2010-02-02 | 2012-10-17 | 奥图泰有限公司 | Extraction process |
| CN102527493A (en) * | 2010-12-15 | 2012-07-04 | 核工业北京地质研究院 | Uranium and beryllium separating technology for ore containing uranium and beryllium |
| CN102747225A (en) * | 2012-07-10 | 2012-10-24 | 中南大学 | Method for comprehensively recycling copper, selenium and uranium from stone coal extraction vanadic acid immersion liquid |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106834686B (en) | 2018-07-27 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN111926180B (en) | Method for extracting ion adsorption type rare earth | |
| CN103073061B (en) | Method for extracting tungsten and molybdenum in high molybdenum scheelite | |
| CN102191391B (en) | Method for extracting germanium from high-impurity low-grade complex zinc oxide powder | |
| CN109182791B (en) | Method for removing aluminum from rare earth feed liquid by organic acid complexation-solid phase adsorption | |
| CN105483400A (en) | Method for synchronously extracting and separating uranium and molybdenum | |
| CN107058757A (en) | A kind of production method of the separation of Silver from silver-containing liquid waste | |
| KR101467356B1 (en) | Recovering Method of high concentration nickel from waste electroless nickel plating | |
| CN102816931A (en) | Method for recovering copper and iron from copper-containing acid wastewater and producing gypsum | |
| CN105420495B (en) | In a kind of Bayer process alumina producing in gallium processing procedure uranium separation method | |
| CN108467942A (en) | A method of Selectively leaching zinc, lead, gallium and germanium from zinc replacement slag | |
| CN103993182A (en) | Comprehensive recovery method for secondary resources in iron vitriol slag | |
| CN104561541A (en) | Method for separating tungsten and molybdenum from tungsten molybdenum ore | |
| Cao et al. | Separation of tungsten and molybdenum with solvent extraction using functionalized ionic liquid tricaprylmethylammonium bis (2, 4, 4-trimethylpentyl) phosphinate | |
| CN103898323B (en) | The method of magnesium is reclaimed in a kind of lower concentration nickel cobalt biochemical lixivium | |
| CN106834698A (en) | A kind of method of enriching and reclaiming indium in acid solution containing indium from low concentration | |
| CN104561545A (en) | Method for separating tungsten and molybdenum from tungsten molybdenum ore | |
| CN106283109B (en) | The processing method of high ferro electrodeposition lean solution during a kind of wet-milling processing | |
| CN105347547A (en) | Heavy metal waste water treatment method | |
| CN107815541A (en) | The Fe loaded in hydrofluoric acid back extraction P204 organic phases3+And the method for strip liquor processing | |
| CN103572053B (en) | Abandoned car or plating wastes hydrometallurgic recovery method and poisoning extractant processing method thereof | |
| CN105567986B (en) | A kind of method for reclaiming gallium germanium from zinc dust precipitation gallium germanium slag with resin | |
| CN109133178B (en) | Production process of manganese sulfate | |
| CN106834686A (en) | In a kind of gallium production procedure except uranium technique | |
| US9279168B2 (en) | Process for recovery of technical grade molybdenum from diluted leaching acid solutions (PLS), with highly concentrated arsenic, from metallurgical residues | |
| CN105543475B (en) | Method for enriching and recovering rare earth from rare earth-containing phosphorite |
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 |