CN114646068A - Method for treating uranium-containing high-salt waste liquid in nitric acid system - Google Patents
Method for treating uranium-containing high-salt waste liquid in nitric acid system Download PDFInfo
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- CN114646068A CN114646068A CN202011504207.4A CN202011504207A CN114646068A CN 114646068 A CN114646068 A CN 114646068A CN 202011504207 A CN202011504207 A CN 202011504207A CN 114646068 A CN114646068 A CN 114646068A
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- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23G—CREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
- F23G7/00—Incinerators or other apparatus for consuming industrial waste, e.g. chemicals
- F23G7/04—Incinerators or other apparatus for consuming industrial waste, e.g. chemicals of waste liquors, e.g. sulfite liquors
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
- B01D53/34—Chemical or biological purification of waste gases
- B01D53/74—General processes for purification of waste gases; Apparatus or devices specially adapted therefor
- B01D53/77—Liquid phase processes
- B01D53/78—Liquid phase processes with gas-liquid contact
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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
- C02F1/02—Treatment of water, waste water, or sewage by heating
- C02F1/04—Treatment of water, waste water, or sewage by heating by distillation or evaporation
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23G—CREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
- F23G5/00—Incineration of waste; Incinerator constructions; Details, accessories or control therefor
- F23G5/02—Incineration of waste; Incinerator constructions; Details, accessories or control therefor with pretreatment
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23G—CREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
- F23G5/00—Incineration of waste; Incinerator constructions; Details, accessories or control therefor
- F23G5/08—Incineration of waste; Incinerator constructions; Details, accessories or control therefor having supplementary heating
- F23G5/12—Incineration of waste; Incinerator constructions; Details, accessories or control therefor having supplementary heating using gaseous or liquid fuel
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23G—CREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
- F23G5/00—Incineration of waste; Incinerator constructions; Details, accessories or control therefor
- F23G5/44—Details; Accessories
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23J—REMOVAL OR TREATMENT OF COMBUSTION PRODUCTS OR COMBUSTION RESIDUES; FLUES
- F23J15/00—Arrangements of devices for treating smoke or fumes
- F23J15/02—Arrangements of devices for treating smoke or fumes of purifiers, e.g. for removing noxious material
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23J—REMOVAL OR TREATMENT OF COMBUSTION PRODUCTS OR COMBUSTION RESIDUES; FLUES
- F23J15/00—Arrangements of devices for treating smoke or fumes
- F23J15/02—Arrangements of devices for treating smoke or fumes of purifiers, e.g. for removing noxious material
- F23J15/022—Arrangements of devices for treating smoke or fumes of purifiers, e.g. for removing noxious material for removing solid particulate material from the gasflow
- F23J15/025—Arrangements of devices for treating smoke or fumes of purifiers, e.g. for removing noxious material for removing solid particulate material from the gasflow using filters
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23J—REMOVAL OR TREATMENT OF COMBUSTION PRODUCTS OR COMBUSTION RESIDUES; FLUES
- F23J15/00—Arrangements of devices for treating smoke or fumes
- F23J15/02—Arrangements of devices for treating smoke or fumes of purifiers, e.g. for removing noxious material
- F23J15/04—Arrangements of devices for treating smoke or fumes of purifiers, e.g. for removing noxious material using washing fluids
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23J—REMOVAL OR TREATMENT OF COMBUSTION PRODUCTS OR COMBUSTION RESIDUES; FLUES
- F23J15/00—Arrangements of devices for treating smoke or fumes
- F23J15/06—Arrangements of devices for treating smoke or fumes of coolers
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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
- C02F2103/00—Nature of the water, waste water, sewage or sludge to be treated
- C02F2103/18—Nature of the water, waste water, sewage or sludge to be treated from the purification of gaseous effluents
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23G—CREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
- F23G2201/00—Pretreatment
- F23G2201/60—Separating
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23G—CREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
- F23G2204/00—Supplementary heating arrangements
- F23G2204/10—Supplementary heating arrangements using auxiliary fuel
- F23G2204/103—Supplementary heating arrangements using auxiliary fuel gaseous or liquid fuel
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23G—CREMATION FURNACES; CONSUMING WASTE PRODUCTS BY COMBUSTION
- F23G2209/00—Specific waste
- F23G2209/10—Liquid waste
- F23G2209/101—Waste liquor
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23J—REMOVAL OR TREATMENT OF COMBUSTION PRODUCTS OR COMBUSTION RESIDUES; FLUES
- F23J2217/00—Intercepting solids
- F23J2217/10—Intercepting solids by filters
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23J—REMOVAL OR TREATMENT OF COMBUSTION PRODUCTS OR COMBUSTION RESIDUES; FLUES
- F23J2217/00—Intercepting solids
- F23J2217/10—Intercepting solids by filters
- F23J2217/102—Intercepting solids by filters electrostatic
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F23—COMBUSTION APPARATUS; COMBUSTION PROCESSES
- F23J—REMOVAL OR TREATMENT OF COMBUSTION PRODUCTS OR COMBUSTION RESIDUES; FLUES
- F23J2219/00—Treatment devices
- F23J2219/40—Sorption with wet devices, e.g. scrubbers
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Abstract
The invention belongs to the technical field of uranium purification, and particularly relates to a method for treating uranium-containing high-salt waste liquid in a nitric acid system. The waste liquid after filtration and impurity removal is conveyed to a waste liquid incinerator through a diaphragm metering pump, is uniformly sprayed into a combustion chamber of the waste liquid incinerator through a feeding nozzle, and flue gas generated after combustion of natural gas and air is used as a heat source, so that the waste liquid can be completely gasified, and organic phase and interface dirt contained in the waste liquid can be fully combusted and oxidized into carbon dioxide, nitrogen oxide, sulfur dioxide and water vapor by surplus air; the nitrate in the waste liquid is partially decomposed into metal oxide and nitrogen oxide gas by heating, the contained uranium is also decomposed into uranium oxide and nitrogen oxide gas, and the residual salt, metal oxide and uranium oxide in the waste liquid are discharged from the lower outlet of the waste liquid incinerator in a powder form for temporary storage. The invention combines the waste liquid incineration technology and the nitric acid rectification technology, thereby realizing the standard discharge of the waste liquid and the recycling of the nitric acid resource.
Description
Technical Field
The invention belongs to the technical field of uranium purification, and particularly relates to a method for treating uranium-containing high-salt waste liquid in a nitric acid system.
Background
The method is characterized in that a 'wet method' uranium purification extraction process is adopted for domestic natural uranium purification, a large amount of high-metal uranium-nitrate-containing waste liquid can be generated in the processes of extraction, tail gas treatment, raffinate rectification, concentration and the like, the waste liquid is complex in component and generally contains more residual uranium after extraction, other metal salt impurities, nitric acid insoluble substances, an extractant carried in a water phase, other organic phase interface pollutants and the like, and meanwhile, the nitric acid concentration of the waste liquid can reach more than 10mol/L, and the waste liquid has the characteristics of strong corrosivity, flammability and high toxicity. Along with domestic uranium purification conversion production capacity's promotion and stricter environmental protection requirement, the waste liquid treatment pressure that the uranium purification production field produced further increases, and the high metal uranium-bearing waste liquid of its production must be through removing technology processing such as uranium, makes it discharge within the 0.05mg/L that waste liquid uranium content reduced to the national requirement, and other impurity content also need accord with the relevant requirement of country simultaneously, realizes the innocent treatment of uranium purification production line waste liquid.
The treatment process of the high-metal uranium-containing waste liquid generated in domestic uranium purification production at present comprises alkali neutralization, precipitation, filtration, and then, the discharge treatment of the clear liquid through ion exchange uranium removal. The process is only suitable for treating the waste liquid without organic phase, interface dirt and other impurities which affect an ion exchange system, if the ion exchange system is used for treating the high-metal uranium-nitrate-containing waste liquid generated in uranium purification production, a set of pretreatment system is required to be additionally arranged, organic matters and other degradable impurities in the waste liquid are removed by methods such as supercritical oxidation, and then the waste liquid is treated by the ion exchange uranium removal system. The process system has the defects of large investment, high maintenance cost of an ion exchange system, high operating cost, limited waste liquid treatment capacity and the like, and nitric acid resources in waste liquid cannot be recycled.
Therefore, it is necessary to develop a treatment method for treating uranium-containing high-salt waste liquid in a nitric acid system, which can realize standard discharge of the waste liquid and recycle of nitric acid resources therein.
Disclosure of Invention
The invention aims to provide a method for treating uranium-containing high-salt waste liquid in a nitric acid system, which combines a waste liquid incineration technology and a nitric acid rectification technology, and can realize standard discharge of the waste liquid and recycle of nitric acid resources in the waste liquid.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a method for treating uranium-bearing high-salt waste liquid in a nitric acid system,
step 1: removing insoluble solid particles and other easily separated impurities in the waste liquid through a filter;
step 2: the waste liquid after filtration and impurity removal is conveyed to a waste liquid incinerator through a diaphragm metering pump, is uniformly sprayed into a combustion chamber of the waste liquid incinerator through a feeding nozzle, and flue gas generated after combustion of natural gas and air is used as a heat source, so that the waste liquid can be completely gasified, and organic phase and interface dirt contained in the waste liquid can be fully combusted and oxidized into carbon dioxide, nitrogen oxide, sulfur dioxide and water vapor by surplus air; the nitrate in the waste liquid is partially decomposed into metal oxide and nitrogen oxide gas by heating, the contained uranium is also decomposed into uranium oxide and nitrogen oxide gas, and the residual salt, metal oxide and uranium oxide in the waste liquid are discharged from the lower outlet of the waste liquid incinerator for temporary storage in a powder form;
and 3, step 3: tail gas at the outlet of the waste liquid incinerator enters a condenser after two-stage dust removal through a first-stage dust remover and a second-stage dust remover;
and 4, step 4: the tail gas of the condenser is further absorbed and purified by a leaching tower, the acidity of the nitric acid solution absorbed by the leaching tower reaches 5-8 mol/L, and the tail gas at the outlet of the leaching tower enters an alkaline washing tower for neutralization and absorption and then is discharged;
and 5, step 5: and (3) the mixed solution of the acid recovered from the condenser and the elution tower enters a rectifying tower, condensed water extracted from the top of the rectifying tower returns to the elution tower to elute and recover nitric acid, and concentrated nitric acid extracted from the tower kettle returns to the uranium purification main process to be recycled.
The filter is a centrifugal filter.
The step 2 is as follows: the flue gas generated after combustion of natural gas and air is used as a heat source, wherein the air is excessive by 20%.
The step 2 is as follows: the temperature of the combustion zone of the waste liquid incinerator is controlled to be 1200 ℃, so that the waste liquid can be completely gasified.
The temperature of the primary dust remover is 350-450 ℃.
The temperature of the secondary dust remover is 250-350 ℃.
The primary dust remover adopts a high-precision nickel tube filter.
The secondary dust remover adopts an electric dust remover.
The step 3: the concentration of the condensed liquid nitric acid collected by the condenser is 6-10 mol/L.
The rectifying tower adopts a packed tower form, the theoretical plate number is 10, the reflux ratio is less than 0.3, and the normal pressure rectification is carried out.
The beneficial effects obtained by the invention are as follows:
the main process devices such as an incinerator and the like applied to the method for treating the uranium-containing high-salt waste liquid in the nitric acid system have the advantages of simple structure, low manufacturing cost, convenience in processing, simplicity in operation, convenience in maintenance and the like. The process can oxidize and decompose organic matters and the like in the waste liquid in a combustion mode, thereby avoiding the oxidation treatment through a pretreatment process; the purification and recovery of nitric acid in the waste liquid can be realized, and the nitric acid is concentrated to the concentration of 10mol/L and then returns to the main process for use; the uranium content of the discharged alkali washing neutralization liquid is lower than 0.05mg/L, and the national discharge requirement is met. Meanwhile, the device can also be applied to the field of treatment of other high-salt acid-containing waste liquid, and the treatment of the waste liquid and the recovery of acid are realized.
Drawings
FIG. 1 is a process flow diagram of a treatment process of uranium-bearing high-salt waste liquid in a nitric acid system;
in the figure: 1, a filter; 2-a waste liquid incinerator; 3-first-stage dust remover; 4-secondary dust remover; 5, a condenser; 6-leaching tower; 7-a rectifying tower; 8-alkaline washing tower.
Detailed Description
The invention is described in detail below with reference to the figures and the specific embodiments.
The waste liquid incineration technology is utilized, natural gas and the like are used as fuels to provide heat sources, the waste liquid is gasified when meeting high-temperature flue gas, most of salt and other insoluble impurities in the waste liquid are discharged from the bottom of the incinerator after being granulated and precipitated, and part of nitrate is decomposed into oxide and nitrogen oxide gas; uranium in the waste liquid forms uranium oxide at high temperature and is discharged and temporarily stored together with salts; organic phase, interface dirt and other impurities in the waste liquid are oxidized and incinerated by high-temperature flue gas (900-1200 ℃) to form gases such as carbon dioxide, nitric oxide, sulfur dioxide and water vapor. The tail gas of the waste liquid incinerator is filtered by a high-precision stainless steel nickel pipe and subjected to electric precipitation and deep filtration to remove uranium and dust particles in the tail gas, and the tail gas is condensed and leached to recover water vapor and nitrogen oxide gas in the tail gas, so that a relatively pure nitric acid solution is obtained.
By utilizing a nitric acid rectification concentration technology, concentrating the nitric acid obtained by condensation and elution recovery to more than 10mol/L, returning condensed water (PH is more than 4) at the top of the tower to an elution tower to elute and recover the nitric acid, and conveying the concentrated nitric acid at the bottom of the tower to a uranium purification production line for recycling. The process combines the waste liquid incineration technology and the nitric acid rectification technology, so that the harmless treatment of the high-metal uranium-containing nitric acid waste liquid can be realized, and the cyclic utilization of nitric acid resources can also be realized.
The invention provides a method for treating uranium-bearing high-salt waste liquid in a nitric acid system, which comprises the steps of removing insoluble solid particles from the waste liquid through a filter, feeding the waste liquid into a waste liquid incinerator through a nozzle, incinerating and gasifying the waste liquid by hot flue gas in the waste liquid incinerator, discharging residual residues from the bottom of the waste liquid incinerator, removing dust from tail gas at an outlet of the waste liquid incinerator through a primary dust remover and a secondary dust remover in two stages, feeding the tail gas of a condenser into a condenser, further absorbing and purifying the tail gas of the condenser through an elution tower, feeding the tail gas of the condenser into an alkaline washing tower, neutralizing and discharging, feeding acid liquor recovered by the condenser and the elution tower into a rectifying tower, concentrating the acid liquor to 10mol/L, and returning the concentrated acid liquor to a main process for recycling.
The specific implementation mode is as follows:
step 1: the waste liquid is passed through a filter 1 for removing insoluble solid particles and other easily separable impurities, wherein the filter is a centrifugal filter.
Step 2: the waste liquid after filtration edulcoration is carried to waste liquid incinerator 2 through the diaphragm metering pump, evenly sprays through the feed nozzle and gets into in waste liquid incinerator 2 combustion chamber, adopts natural gas and air burning back flue gas as the heat source (air excess 20%), controls waste liquid incinerator 2 combustion area temperature and is about 1200 ℃, makes the waste liquid can gasify completely, and organic phase and interface filth etc. that contain in the waste liquid can be fully burnt by surplus air and oxidize into carbon dioxide, nitrogen oxide, sulfur dioxide and vapor etc.. The nitrate in the waste liquid is partially decomposed into metal oxide and nitrogen oxide gas by heating, the contained uranium is also decomposed into uranium oxide and nitrogen oxide gas, and the residual salt, metal oxide and uranium oxide in the waste liquid are discharged from the lower outlet of the waste liquid incinerator 2 in a powder form for temporary storage.
And 3, step 3: the tail gas at the outlet of the waste liquid incinerator 2 enters a condenser 5 after two-stage dust removal through a first-stage dust remover 3 (350-450 ℃) and a second-stage dust remover 4 (250-350 ℃). The first-stage dust remover 3 adopts a high-precision nickel tube filter (less than or equal to 10 mu m), and the second-stage dust remover 4 adopts an electric dust remover (the dust removal efficiency is more than 99.9%). The concentration of the condensed liquid nitric acid collected by the condenser 5 is 6-10 mol/L.
And 4, step 4: tail gas of the condenser 5 is further absorbed and purified by the leaching tower 6, the acidity of the nitric acid solution absorbed by the leaching tower 6 can reach 5-8 mol/L, tail gas at the outlet of the leaching tower 6 enters the alkaline washing tower 8 for neutralization and absorption and then is discharged, and the discharged tail gas standard meets the NO (nitric oxide) standard meeting the requirements of the Integrated emission Standard of atmospheric pollutants (GB16297-1996)XEmission limit 240mg/m3。
And 5, step 5: and (3) mixed liquor of the acid recovered by the condenser 5 and the elution tower 6 enters a rectifying tower 7, condensed water (PH is greater than 4 and [ U ] is less than or equal to 0.02mg/L) extracted from the top of the rectifying tower 7 returns to the elution tower 6 to elute and recover nitric acid, and concentrated nitric acid (nitric acid concentration is greater than 10mol/L) extracted from a tower kettle returns to the uranium purification main process to be recycled. The rectifying tower 7 adopts a packed tower form, the theoretical plate number is 10, the reflux ratio is less than 0.3, and the normal pressure rectification is carried out.
The main flow, main apparatus, main features, advantages of the present invention, and the like of the present invention have been shown and described above. The invention is not excluded from the scope of protection of the invention, whether it is modified or equivalently based on the solution of the invention.
Claims (10)
1. A method for treating uranium-containing high-salt waste liquid in a nitric acid system is characterized by comprising the following steps:
step 1: removing insoluble solid particles and other easily separated impurities in the waste liquid through a filter;
step 2: the waste liquid after filtration and impurity removal is conveyed to a waste liquid incinerator through a diaphragm metering pump, is uniformly sprayed into a combustion chamber of the waste liquid incinerator through a feeding nozzle, and flue gas generated after combustion of natural gas and air is used as a heat source, so that the waste liquid can be completely gasified, and organic phase and interface dirt contained in the waste liquid can be fully combusted and oxidized into carbon dioxide, nitrogen oxide, sulfur dioxide and water vapor by surplus air; the nitrate in the waste liquid is partially decomposed into metal oxide and nitrogen oxide gas by heating, the contained uranium is also decomposed into uranium oxide and nitrogen oxide gas, and the residual salt, metal oxide and uranium oxide in the waste liquid are discharged from the lower outlet of the waste liquid incinerator for temporary storage in a powder form;
and 3, step 3: tail gas at the outlet of the waste liquid incinerator enters a condenser after two-stage dust removal through a first-stage dust remover and a second-stage dust remover;
and 4, step 4: the tail gas of the condenser is further absorbed and purified by a leaching tower, the acidity of the nitric acid solution absorbed by the leaching tower reaches 5-8 mol/L, and the tail gas at the outlet of the leaching tower enters an alkaline washing tower for neutralization and absorption and then is discharged;
and 5, step 5: and (3) the mixed solution of the acid recovered from the condenser and the elution tower enters a rectifying tower, condensed water extracted from the top of the rectifying tower returns to the elution tower to elute and recover nitric acid, and concentrated nitric acid extracted from the tower kettle returns to the uranium purification main process to be recycled.
2. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the filter is a centrifugal filter.
3. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the step 2 is as follows: the flue gas generated after combustion of natural gas and air is used as a heat source, wherein the air is excessive by 20%.
4. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the step 2 is as follows: the temperature of the combustion zone of the waste liquid incinerator is controlled to be 1200 ℃, so that the waste liquid can be completely gasified.
5. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the temperature of the primary dust remover is 350-450 ℃.
6. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the temperature of the secondary dust remover is 250-350 ℃.
7. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the primary dust remover adopts a high-precision nickel tube filter.
8. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the secondary dust remover adopts an electric dust remover.
9. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the step 3: the concentration of the condensed liquid nitric acid collected by the condenser is 6-10 mol/L.
10. The method for treating the uranium-bearing high-salt waste liquid in the nitric acid system according to claim 1, which is characterized in that: the rectifying tower adopts a packed tower form, the theoretical plate number is 10, the reflux ratio is less than 0.3, and the normal pressure rectification is carried out.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011504207.4A CN114646068A (en) | 2020-12-18 | 2020-12-18 | Method for treating uranium-containing high-salt waste liquid in nitric acid system |
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| CN202011504207.4A CN114646068A (en) | 2020-12-18 | 2020-12-18 | Method for treating uranium-containing high-salt waste liquid in nitric acid system |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115404349A (en) * | 2022-09-30 | 2022-11-29 | 中核四0四有限公司 | System and method for recycling metallic uranium in uranium ore indissoluble residues |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115404349A (en) * | 2022-09-30 | 2022-11-29 | 中核四0四有限公司 | System and method for recycling metallic uranium in uranium ore indissoluble residues |
| CN115404349B (en) * | 2022-09-30 | 2023-10-27 | 中核四0四有限公司 | Method for recycling metallic uranium in uranium ore indissolvable residues |
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