CN109987738A - Uranium recovery process in a kind of uranium-bearing waste liquid - Google Patents
Uranium recovery process in a kind of uranium-bearing waste liquid Download PDFInfo
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- CN109987738A CN109987738A CN201711477628.0A CN201711477628A CN109987738A CN 109987738 A CN109987738 A CN 109987738A CN 201711477628 A CN201711477628 A CN 201711477628A CN 109987738 A CN109987738 A CN 109987738A
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F9/00—Multistage treatment of water, waste water or sewage
-
- 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
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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
- C22B7/00—Working up raw materials other than ores, e.g. scrap, to produce non-ferrous metals and compounds thereof; Methods of a general interest or applied to the winning of more than two metals
- C22B7/005—Separation by a physical processing technique only, e.g. by mechanical breaking
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/28—Treatment of water, waste water, or sewage by sorption
-
- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/44—Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
- C02F1/442—Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis by nanofiltration
-
- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F1/00—Treatment of water, waste water, or sewage
- C02F1/66—Treatment of water, waste water, or sewage by neutralisation; pH adjustment
-
- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2101/00—Nature of the contaminant
- C02F2101/006—Radioactive compounds
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2209/00—Controlling or monitoring parameters in water treatment
- C02F2209/02—Temperature
-
- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2209/00—Controlling or monitoring parameters in water treatment
- C02F2209/03—Pressure
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2209/00—Controlling or monitoring parameters in water treatment
- C02F2209/06—Controlling or monitoring parameters in water treatment pH
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- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2301/00—General aspects of water treatment
- C02F2301/04—Flow arrangements
- C02F2301/046—Recirculation with an external loop
-
- C—CHEMISTRY; METALLURGY
- C02—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F—TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
- C02F2301/00—General aspects of water treatment
- C02F2301/08—Multistage treatments, e.g. repetition of the same process step under different conditions
-
- 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)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Environmental & Geological Engineering (AREA)
- Organic Chemistry (AREA)
- Geology (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
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- Manufacturing & Machinery (AREA)
- Hydrology & Water Resources (AREA)
- Water Supply & Treatment (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
Abstract
The invention belongs to uranium recovery process in a kind of uranium-bearing waste liquid.(1) uranium-containing waste water pH value is adjusted；(2) waste liquid filters；(3) waste liquid adsorbs, it is sent after uranium concentration >=200mg/L to novel absorption material system, the dope that the clear liquid and 3 filtration systems that 2 filterings generate generate, which returns, to be recycled in pre-filtering intermediate storage tank, it continues through 1 filtration system and carries out concentration, the clear liquid uranium concentration that 3 filtration systems generate is 0.02-0.03mg/L, send to blowdown vessel and is discharged, the dope that 3 filtration systems generate, uranium concentration is 200mg/L, is adsorbed using Novel Uranium adsorbent material；(4) it is parsed after being saturated, it is final to generate the uranium-containing materials that uranium concentration is about 1-5g/L or more.It is an advantage of the invention that membrane technology equipment simply can be achieved automatically control, normal-temperature operation, without chemical change, low energy consumption, cleanliness without any pollution.Realize that chain control carries out safeguard protection to film processing system.
Description
Technical field
The invention belongs to uranium reclaiming clean techniques in a kind of uranium-containing waste water, and in particular to uranium recycling in a kind of uranium-bearing waste liquid
Technique.
Background technique
In natural hex production process, a large amount of uranium-bearing process waste liquor can be generated.The recycling benefit of metal uranium resource
With and discharged wastewater met the national standard problem be all extensive concern in industry wide.
In the uranium-containing waste water generated in uranium conversion production process, the alkalinity that especially fluorination tail gas elution process generates contains
Uranium waste liquid system is complicated.The domestic resin that currently used ion exchange technique is chosen is carried out except uranium, it is difficult to realize 50 μ g/L of <
Qualified discharge index, and a large amount of spent resin can be generated and be difficult to handle.And pass through investigation, domestic and international industrial adsorbent material
Discharged wastewater met the national standard, but this kind of material price valuableness can be achieved in (such as: new type resin, novel synthetic fibers), will increase at waste water
Manage the operating cost of facility.Therefore the design makes to handle most of waste water realization qualified discharge using film processing system, and at film
The a small amount of concentrate generated is managed by the way of combining novel absorption material to be handled, on the one hand reduces making for adsorbent material
On the other hand dosage solves the problems, such as that film process concentrate can not qualified discharge.
Domestic and international membrane technology and ion exchange technique have the successful experience for uranium-containing waste water processing, the present invention
Patent is designed mainly for the procedure of domestic uranium conversion production line uranium-containing waste water processing, realizes that whole process can optimized control.
Summary of the invention
The object of the present invention is to provide uranium recovery process in a kind of uranium-bearing waste liquid, have chosen film processing system and novel suction
Unit of the enclosure material as uranium-containing waste water treatment process realizes the purpose of 50 μ g/L of uranium concentration < after uranium-containing waste water processing.
The invention is realized in this way uranium recovery process in a kind of uranium-bearing waste liquid, it includes the following steps,
(1) uranium-containing waste water pH value is adjusted；
(2) waste liquid filters；
(3) waste liquid adsorbs, and the clear liquid generated to novel absorption material system, 2 filterings is sent after uranium concentration >=200mg/L
The dope generated with 3 filtration systems, which returns, to be recycled in pre-filtering intermediate storage tank, is continued through 1 filtration system and is concentrated
Processing, the clear liquid uranium concentration that 3 filtration systems generate are 0.02-0.03mg/L, send to blowdown vessel and are discharged, 3 filterings system
The dope that system generates, uranium concentration 200mg/L are adsorbed using Novel Uranium adsorbent material；
(4) it is parsed after being saturated, it is final to generate the uranium-containing materials that uranium concentration is about 1-5g/L or more.
Described step (1) uranium-containing waste water first carries out PH adjusting, and PH is adjusted to less than 3.
Deployed waste liquid is sent the dope generated to 1 nanofiltration filtration system, 1 filtration system by the step (2)
It send to 2 filtration systems and continues to be concentrated, clear liquid, which is sent to 3 nanofiltration filtration systems, to be continued to be concentrated；2 filtration systems
The dope of generation need to carry out circular treatment.
1 nanofiltration filtration system described in the step (2), 40 DEG C of pump work temperature <, pump pressure is less than
2.0Mpa。
2 nanofiltration filtration systems described in the step (2), 40 DEG C of pump work temperature <, pump pressure is less than
2.0Mpa。
2 nanofiltration filtration systems described in the step (2), 50 DEG C of pump work temperature <, pump pressure is less than
2.0Mpa。
It is an advantage of the invention that membrane technology equipment simply can be achieved automatically control, normal-temperature operation, without chemical change,
Low energy consumption, cleanliness without any pollution.Realize that chain control carries out safeguard protection to film processing system.
Specific embodiment
It describes in detail combined with specific embodiments below to the present invention:
Uranium recovery process in a kind of uranium-bearing waste liquid, it includes the following steps:
(1) uranium-containing waste water pH value is adjusted, uranium-containing waste water first carries out PH adjusting, and PH is adjusted to less than 3；
(2) waste liquid filters, and deployed waste liquid is sent to 1 nanofiltration filtration system (40 DEG C of pump work temperature <, pump pressure
Power is less than 2.0Mpa), the dope (uranium concentration about 20-50mg/L) that 1 filtration system generates is sent to 2 filtration system (pump works
40 DEG C of temperature <, pump pressure is less than 2.0Mpa) continue to be concentrated, clear liquid (uranium concentration < 10mg/L) send to 3 nanofiltrations and filters
System (50 DEG C of pump work temperature <, pump pressure are less than 2.0Mpa) continues to be concentrated；The dope that 2 filtration systems generate needs
Carry out circular treatment；
(3) waste liquid adsorbs, and the clear liquid generated to novel absorption material system, 2 filterings is sent after uranium concentration >=200mg/L
The dope generated with 3 filtration systems, which returns, to be recycled in pre-filtering intermediate storage tank, is continued through 1 filtration system and is concentrated
Processing, the clear liquid uranium concentration that 3 filtration systems generate is about 0.02-0.03mg/L, send to blowdown vessel and is discharged, 3 filterings
The dope that system generates, uranium concentration 200mg/L are adsorbed using Novel Uranium adsorbent material；
(4) it is parsed after being saturated, it is final to generate the uranium-containing materials that uranium concentration is about 1-5g/L or more.
The continuous processing of uranium-containing waste water can be realized according to the technical solution, the flow for the clear liquid that 3 filterings generate is considered as this
The processing capacity of system.1 time, 2 filterings are designed to realize the continuous circular flow of total system by membranous system type selecting.
In addition, film unit, pipeline, pump, valve, container use acidproof material in the system, while in order to protect system need to be to each confession
Chain termination of pumping design is arranged in batch can.
Pretreatment refers mainly to mechanical filter, is to remove the suspended matter in stoste, colloid, turbidity, coloration, peculiar smell etc.
The substances such as mud, large granular impurity, clay and minimal amount of colloid, prevent these substances to later period ultrafiltration, and nanofiltration is reverse osmosis
The influence of film.Main filtration mode has disc type filtering, bag type filtering.The material of processing system film is polyacrylic material, acidproof
Alkalinity is stronger.
Micro-filtration is the size using micropore diameter, and in the case where pressure difference is motive force, it is outstanding that particle of membrane aperture etc. will be greater than in solution
Floating object matter is retained down, and reaches the removal and the clear membrane separation technique of solution of particle.Micropore membrane aperture used in the present invention is
1 μm (being filter core used in micro-filtration, the bulky grain suspended matter in different range can be isolated according to the difference of filter core),
Optimum pH range is 0-14, and temperature can retain the substances such as clay, suspended matter in (5~50) DEG C, can to subsequent ultrafiltration,
Nanofiltration and reverse osmosis film play a protective role.Since the particle that micro-filtration is removed is typically much deeper than reverse osmosis and ultrafiltration point
From solute and macromolecular, therefore do not have osmotic pressure, operation pressure difference it is smaller, about (0.01~0.2) MPa.
Nanofiltration membrane is a kind of pressure drive membrane between reverse osmosis between ultrafiltration membrane, be develop in the world in recent years compared with
One of fast film brand.The different nanofiltration membrane of molecular cut off, the substances such as ion filtered have a certain difference.It is molten
When liquid passes through nanofiltration membrane, under the effect of the pressure, it can be separated from permeate through the substance of nanofiltration membrane, it is not permeable
Part is trapped.
The material of the used nanofiltration membrane of the present invention is polyamide composite film, their molecular cut off is respectively 300 dongles
(nanofiltration membrane), 200 dalton (secondary nanofiltration membrane) and 200 dalton (nanofiltration membrane three times).Nanofiltration membrane adequate operation temperature
It spends and is selected in (5~45) DEG C operating pressure according to the pressure that film filter area, processing capacity etc. are pumped, continuous operation pH value
Range is 2~11.
Claims (6)
1. uranium recovery process in a kind of uranium-bearing waste liquid, it is characterised in that: it includes the following steps,
(1) uranium-containing waste water pH value is adjusted；
(2) waste liquid filters；
(3) waste liquid adsorbs, and the clear liquid generated to novel absorption material system, 2 filterings and 3 times are sent after uranium concentration >=200mg/L
The dope that filtration system generates is returned and is recycled in pre-filtering intermediate storage tank, is continued through 1 filtration system and is carried out concentration, and 3
The clear liquid uranium concentration that secondary filtration system generates is 0.02-0.03mg/L, send to blowdown vessel and is discharged, and 3 times filtration system generates
Dope, uranium concentration 200mg/L, using Novel Uranium adsorbent material adsorb；
(4) it is parsed after being saturated, it is final to generate the uranium-containing materials that uranium concentration is about 1-5g/L or more.
2. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: described step (1) uranium-bearing
Waste water first carries out PH adjusting, and PH is adjusted to less than 3.
3. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) will be adjusted
The waste liquid prepared is sent to 1 nanofiltration filtration system, the dope that 1 filtration system generates send to 2 filtration systems continue it is dense
Contracting, clear liquid, which is sent to 3 nanofiltration filtration systems, to be continued to be concentrated；The dope that 2 filtration systems generate need to carry out circular treatment.
4. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) is described
1 nanofiltration filtration system, 40 DEG C of pump work temperature <, pump pressure be less than 2.0Mpa.
5. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) is described
2 nanofiltration filtration systems, 40 DEG C of pump work temperature <, pump pressure be less than 2.0Mpa.
6. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) is described
2 nanofiltration filtration systems, 50 DEG C of pump work temperature <, pump pressure be less than 2.0Mpa.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201711477628.0A CN109987738A (en) | 2017-12-29 | 2017-12-29 | Uranium recovery process in a kind of uranium-bearing waste liquid |
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| CN201711477628.0A CN109987738A (en) | 2017-12-29 | 2017-12-29 | Uranium recovery process in a kind of uranium-bearing waste liquid |
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| CN109987738A true CN109987738A (en) | 2019-07-09 |
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| CN201711477628.0A Pending CN109987738A (en) | 2017-12-29 | 2017-12-29 | Uranium recovery process in a kind of uranium-bearing waste liquid |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112708759A (en) * | 2020-11-27 | 2021-04-27 | 核工业北京化工冶金研究院 | Method for enriching uranium from sulfuric acid leaching solution |
| CN112779426A (en) * | 2020-11-30 | 2021-05-11 | 核工业北京化工冶金研究院 | CO (carbon monoxide)2+O2Method for recovering uranium from waste water of in-situ leaching uranium mining evaporation pool |
| CN113707353A (en) * | 2020-12-25 | 2021-11-26 | 核工业北京化工冶金研究院 | Sponge iron filter material activation and reuse method |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112708759A (en) * | 2020-11-27 | 2021-04-27 | 核工业北京化工冶金研究院 | Method for enriching uranium from sulfuric acid leaching solution |
| CN112779426A (en) * | 2020-11-30 | 2021-05-11 | 核工业北京化工冶金研究院 | CO (carbon monoxide)2+O2Method for recovering uranium from waste water of in-situ leaching uranium mining evaporation pool |
| CN112779426B (en) * | 2020-11-30 | 2022-08-19 | 核工业北京化工冶金研究院 | CO (carbon monoxide) 2 +O 2 Method for recycling uranium in wastewater of in-situ leaching uranium mining evaporation pool |
| CN113707353A (en) * | 2020-12-25 | 2021-11-26 | 核工业北京化工冶金研究院 | Sponge iron filter material activation and reuse method |
| CN113707353B (en) * | 2020-12-25 | 2023-08-29 | 核工业北京化工冶金研究院 | Method for activating and reusing sponge iron filter material |
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Application publication date: 20190709 |