CN106448789A - Processing method and system of radioactive chemical wastewater in nuclear power plant - Google Patents
Processing method and system of radioactive chemical wastewater in nuclear power plant Download PDFInfo
- Publication number
- CN106448789A CN106448789A CN201610944487.8A CN201610944487A CN106448789A CN 106448789 A CN106448789 A CN 106448789A CN 201610944487 A CN201610944487 A CN 201610944487A CN 106448789 A CN106448789 A CN 106448789A
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- nuclear power
- power station
- waste
- waste liquid
- gas
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/02—Treating gases
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
- G21F9/36—Disposal of solid waste by packaging; by baling
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Environmental & Geological Engineering (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
The invention discloses a processing method and a system of radioactive chemical wastewater in nuclear power plants, including the following steps: heat and dry the radioactive chemical wastewater; separate the wastewater into salt particles and gas with dust; use a dust remover to separate the gas into salt particles and exhaust gas; collect these salt particles to make into waste drum; filter the gas using a high-efficiency particulate air filter; exhaust the rest gas to atmosphere after passing test and perform the processing of chemical wastewater. Compared to existing technologies, the processing method of chemical wastewater has advantages of simple system configuration, high processing efficiency, non-secondary wastewater and high volume reduction factor. The generated secondary solid waste meets the requirement of waste package and waste disposal sites after effective packing. In addition to these advantages, the processing method also provides a processing system of radioactive chemical wastewater in nuclear power plants.
Description
Technical field
A kind of the invention belongs to chemical waste fluid processing technology field, it is more particularly related to nuclear power station radioactivity
The processing method of chemical waste fluid and system.
Background technology
Nuclear power station chemical waste fluid generally has the characteristics that complicated component, salt content are high, particularly containing radioactive substance
Chemical waste fluid, is not suitable for processing using methods such as ion exchanges.
At present, to the nuclear power station chemical waste fluid containing radioactive substance mainly using PROCESS FOR TREATMENT dry etc. in evaporation, bucket.
But, there is problems with the processing method of existing nuclear power station radio chemistry waste liquid:
First, treatment effeciency is low;
Secondly, chemical waste fluid and condensate liquid are both needed to by the steps such as evaporation, drying, system setting and cumbersome, the energy of operation
Consumption is high;
Again, secondary liquid waste can be produced in chemical waste fluid processing procedure it is impossible to avoid to carry radioactivity secretly, cause secondary dirt
Dye;
Finally, the radioactive activity of evaporation raffinate itself is higher, also of a relatively high to radiation shielding requirements, increased operation
And maintenance cost.
In view of this, it is necessory to provide, one kind can be effectively treated to nuclear power station radio chemistry waste liquid, system is joined
Put simply efficient nuclear power station radio chemistry method for treating waste liquid and system.
Content of the invention
It is an object of the invention to:Overcome the deficiencies in the prior art, provide one kind can be to nuclear power station radio chemistry waste liquid
Be effectively treated, the simply efficient nuclear power station radio chemistry method for treating waste liquid of system configuration and system.
In order to realize foregoing invention purpose, the invention provides a kind of processing method of nuclear power station radio chemistry waste liquid,
It comprises the following steps:
Radio chemistry waste liquid heat drying is separated into salt grain and the gas containing dust;
Gas removing dust device containing dust is separated into salt grain and waste gas, collects salt grain, make waste drum;And
Gained waste gas is filtered through HEPA, residual gas is emitted into air through inspection is qualified, completes
The process of chemical waste fluid.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, separate in heat drying and radiate
Property chemical waste fluid before, collect radio chemistry waste liquid, and radio chemistry waste liquid pre-processed, filter out therein big
Granule foreign, to avoid affecting the detached operation of heat drying.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described pretreatment also includes adjusting
The pH value of section radio chemistry waste liquid is to neutrality.The pH value of sample analysis chemical waste fluid specifically can be passed through, add acid (as nitre
Acid) or alkali (as NaOH) come to adjust its pH value to neutrality, in order to subsequent operation.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, using the active-carbon bed mistake of GAC
Filter the large granular impurity in chemical waste fluid, so that the process of chemical waste fluid is more complete, it is to avoid produce secondary liquid waste or useless
Thing.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described radio chemistry waste liquid
Salt grain and the gas containing dust are separated into by spray dryer heat drying.Spray dryer is by the way of heating air
Heated, under the high temperature conditions, moisture evaporation in waste liquid, salts substances therein become salt grain, contain in chemical waste fluid
Radioactive substance is also mainly deposited in salt grain.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described radio chemistry waste liquid
It is thermally dried by spray dryer and be separated into salt grain and the gas detailed process containing dust is:
1) it is atomized:Chemical waste fluid, through the atomizer of spray dryer, dissipates into droplet;
2) it is dried:Make droplet with hot air using cocurrent mode and mix, the temperature official post mist of hot-air and droplet
Moisture evaporation in dripping drying;Concrete mode is:In spray dryer, droplet and the equidirectional flowing of hot-air;Droplet enters
Enter in spray dryer immediately with hot air, so that spray dryer internal temperature is declined, droplet can be at a lower temperature
It is dried;Drying can be divided into constant speed stage and decelerating phase:During the constant speed stage, moisture evaporation occurs in droplet surface, steams
Send out speed to be controlled by the diffusion velocity of surrounding air film by steam, chief motivation is the temperature difference of hot-air and droplet, water
Divide and evaporation rate is more than by the diffusion velocity of droplet, the saturation degree of particle surface can not be maintained again when diffusion velocity reduces
When, evaporation rate starts to slow down, and enters the decelerating phase;Now, particle temperature begins to ramp up, at the end of being dried, the temperature of material
Temperature close to surrounding air;
3) separate:The moisture evaporation discharged respectively in droplet is dried, formed produce when salt grain and evaporation containing dust
Gas.Concrete mode can be:Under Action of Gravity Field, salt grain is discharged by the bottom of spray dryer, the gas containing dust from
Another outlet of spray dryer is discharged.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described deduster removes for pocket type
Dirt device, the gas containing dust is separated into salt grain and waste gas.Sack cleaner have small volume, convenient and flexible operation, energy-conservation,
Efficiently the features such as, in the gas containing dust, it is entrained with salt grain, enter from the sidepiece of deduster, after the mesh through filter bag separates,
Salt grain is discharged through gravitational settling to floss hole, and gas drains into HEPA and processes.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described collection salt grain includes receiving
The salt grain that the collection salt grain isolated of heat drying and removing dust device are isolated.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described make waste drum
It is that salt grain is loaded metal waste bucket, then metal waste barreled is entered high integrity container, form waste drum.Concrete mode
For:Salt grain is loaded 200L metal waste bucket, output waste activity is about 2.75 × 107Bq/kg, the full salt grain of metal waste barreled
Load the high integrity container of concrete afterwards, the high integrity container of concrete can pack 4~6 200L metal waste buckets, shape
The waste drum becoming can be sent to waste temporary library.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described efficiency particulate air mistake
Filter is used for filtering a diameter of 0.5 μm of particles below in waste gas.HEPA may filter that the gas in waste gas is molten
The small particle harmful substance such as glue, when containing radioactive substance in waste gas, efficiently can remove radioactive substance, significantly reduce it and put
Penetrating property, can be emitted into atmospheric environment through inspection is qualified.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described heat drying separates and fills
It is provided with atomizer, for chemical waste fluid is atomized into droplet in putting.
As a kind of improvement of the processing method of nuclear power station radio chemistry waste liquid of the present invention, described nuclear power station radioactivity
Learn method for treating waste liquid both to can be used for processing common chemical waste fluid it is also possible to be used for processing radio chemistry waste liquid.
In order to realize foregoing invention purpose, present invention also offers a kind of processing system of nuclear power station radio chemistry waste liquid
System, it includes:
Heat drying separator, for being separated into salt grain and containing powder nuclear power station radio chemistry waste liquid heat drying
The gas of dirt;
Deduster, for being separated into salt grain and waste gas by the gas containing dust;
HEPA, for filtering waste gas;
Emission sensing device, the gaseous mass after filtering for detection and radiation value;And
Refuse packaging apparatus, for being packaged into waste drum by salt grain.
Nuclear power station radio chemistry waste liquid is separated into salt grain and the gas containing dust by heat drying separator, contains
The gas removing dust device having dust is separated into salt grain and waste gas, collects salt grain, makes waste drum through refuse packaging apparatus;Useless
After HEPA filtration, the gas filtering gained is emitted into after the assay was approved greatly gas through emission sensing device
Gas.
As a kind of improvement of the processing system of nuclear power station radio chemistry waste liquid of the present invention, described processing system also includes
Rough filtering device, for filtering the large granular impurity in nuclear power station radio chemistry waste liquid.
As a kind of improvement of the processing system of nuclear power station radio chemistry waste liquid of the present invention, described processing system also includes
Buffer unit, for housing nuclear power station radio chemistry waste liquid and adjusting its pH value.
As a kind of improvement of the processing system of nuclear power station radio chemistry waste liquid of the present invention, described heat drying separates and fills
It is provided with atomizer, for chemical waste fluid is atomized into droplet in putting.
As a kind of improvement of the processing system of nuclear power station radio chemistry waste liquid of the present invention, described heat drying separates and fills
Install the outlet for discharging salt grain and the exhaust outlet for discharging the gas containing dust, outlet is located at heat drying and separates
The bottom of device.
Compared with prior art, the processing method of nuclear power station radio chemistry waste liquid of the present invention and system have excellent as follows
Point:
1) processing method of nuclear power station radio chemistry waste liquid of the present invention is by being separated into salt by chemical waste fluid heat drying
When grain and the gas, particularly spray drying treatment containing dust, surface area can be increased, rapid evaporation 96 in high temperature gas flow
~98% moisture, completing drying only needs several seconds to 30 seconds, and treatment effeciency is high, and energy consumption is low;
2) processing method of nuclear power station radio chemistry waste liquid of the present invention does not produce secondary liquid waste, and capacity reduction factor is high, produces
Secondary solid waste meet waste packaging through effective packaging and waste disposal site accepts requirement, it is to avoid secondary waste is to ring
The threat that border, operating personnel, equipment etc. bring;
3) waste gas producing is filtered by the processing method of nuclear power station radio chemistry waste liquid of the present invention through efficiency particulate air
Device filter and detect up to standard after discharge again, overcome the defect being not provided with exhaust-gas treatment in prior art, environmentally friendly;
4) processing system of nuclear power station radio chemistry waste liquid of the present invention is arranged for single loop, simple system, number of devices
Less, easy to operate.
Brief description
With reference to the accompanying drawings and detailed description, the processing method to nuclear power station radio chemistry waste liquid of the present invention and be
System and its advantage are described in detail.
Fig. 1 is the flow chart of the processing method of nuclear power station radio chemistry waste liquid of the present invention.
Fig. 2 is the structural representation of the processing system of nuclear power station radio chemistry waste liquid of the present invention.
Fig. 3 is the structural representation of spray dryer in the processing system of nuclear power station radio chemistry waste liquid of the present invention.
Specific embodiment
In order that the goal of the invention of the present invention, technical scheme and Advantageous Effects become apparent from, with reference to embodiments,
The present invention will be described in further detail.It should be appreciated that the embodiment described in this specification is used for the purpose of explaining
The present invention, is not intended to limit the present invention, the formula of embodiment, ratio etc. can be suited measures to local conditions to make a choice and be had no reality to result
Matter affects.
Refer to shown in Fig. 1, the processing method of nuclear power station radio chemistry waste liquid of the present invention comprises the following steps:
Step S001, pretreatment, include adjust nuclear power station radio chemistry waste liquid pH value to neutrality, filter out therein
Large granular impurity (optional);
Step S002, nuclear power station radio chemistry waste liquid heat drying is separated into salt grain and the gas containing dust;
Step S003, the gas removing dust device containing dust is separated into salt grain and waste gas;
Step S004, the salt grain of collection step 002 and step 003 gained, make waste drum;
Step S005, waste gas, after HEPA filtration, filters gained gas through discharging after the assay was approved
To air.
Refer to shown in Fig. 2, the processing system of nuclear power station radio chemistry waste liquid of the present invention includes:
Heat drying separator 1, for being separated into salt grain by nuclear power station radio chemistry waste liquid heat drying and containing
The gas of dust;
Deduster 2, for being separated into salt grain and waste gas by the gas containing dust;
HEPA 3, for filtering waste gas;
Emission sensing device 4, the gaseous mass after filtering for detection and radiation value;
Refuse packaging apparatus 5, for being packaged into waste drum by salt grain;
Nuclear power station radio chemistry waste liquid is separated into salt grain and the gas containing dust by heat drying separator 1,
Gas removing dust device 2 containing dust is separated into salt grain and waste gas, collects salt grain, makes waste packaging through refuse packaging apparatus 5
Body;Waste gas after HEPA 3 filtration, check through emission sensing device 4 and qualified be emitted into air by residual gas.
It is below the processing method of nuclear power station radio chemistry waste liquid of the present invention and an embodiment of system.
Refer to shown in Fig. 1~3, for step S001, by nuclear power station radio chemistry waste collection in buffer unit 6
In, pH value is analyzed by sampler 9, adds acid or alkali in buffer unit 6, adjust pH value to neutrality;Through GAC active-carbon bed 7
Large granular impurity in filtering both chemical waste liquid, in order to avoid the normal use of impact heat drying separator;
For step S002, nuclear power station radio chemistry waste liquid is delivered to feed box 8, flow is controlled by feed pump, defeated
Deliver to heat drying separator 1, nuclear power station radio chemistry waste liquid passes through the atomizer 11 that heating separates in drying device 1,
Form the droplet being dispersed in, contact with droplet and mix through the air of heating, in the temperature official post droplet of hot-air and droplet
Moisture evaporation is simultaneously dried, and under gravity, salt grain separates the outlet 13 drying device 1 from heating and discharges;Containing dust
Gas is discharged from exhaust outlet 12;
For step S003, the gas removing dust device 2 containing dust is separated into salt grain and waste gas;
For step S004, the salt grain of collection step 002 and step 003 gained, make waste bag through refuse packaging apparatus 5
Dress body;
For step S005, waste gas filters through HEPA, and HEPA is mainly used in
Collect a diameter of 0.5 μm of particles below dust and various suspension, net for a diameter of 0.3 μm about of aerosol particles
Change effect and be up to 99.97%, filter gained gas and be emitted into air after the assay was approved through emission sensing device 4.
Can be seen that with respect to prior art in conjunction with the above detailed description to embodiment of the present invention, nuclear power of the present invention
The processing method of radio chemistry waste liquid of standing and system have the advantage that:
1) processing method of nuclear power station radio chemistry waste liquid of the present invention is by being separated into salt by chemical waste fluid heat drying
When grain and the gas, particularly spray drying treatment containing dust, surface area can be increased, rapid evaporation 96 in high temperature gas flow
~98% moisture, completing drying only needs several seconds to 30 seconds, and treatment effeciency is high, and energy consumption is low;
2) processing method of nuclear power station radio chemistry waste liquid of the present invention does not produce secondary liquid waste, and capacity reduction factor is high, produces
Secondary solid waste meet waste packaging through effective packaging and waste disposal site accepts requirement, it is to avoid secondary waste is to ring
The threat that border, operating personnel, equipment etc. bring;
3) waste gas producing is filtered by the processing method of nuclear power station radio chemistry waste liquid of the present invention through efficiency particulate air
Device filter and detect up to standard after discharge again, overcome the defect being not provided with exhaust-gas treatment in prior art, environmentally friendly;
4) processing system of nuclear power station radio chemistry waste liquid of the present invention is arranged for single loop, simple system, number of devices
Less, easy to operate.
The announcement of book and teaching according to the above description, those skilled in the art in the invention can also be to above-mentioned embodiment party
Formula carries out suitable change and modification.Therefore, the invention is not limited in specific embodiment disclosed and described above, to this
In the scope of the claims that some modifications and changes of invention should also be as fall into the present invention.Although additionally, this specification
In employ some specific terms, but these terms are merely for convenience of description, do not constitute any restriction to the present invention.
Claims (15)
1. a kind of processing method of nuclear power station radio chemistry waste liquid is it is characterised in that comprise the following steps:
Radio chemistry waste liquid heat drying is separated into salt grain and the gas containing dust;
Gas removing dust device containing dust is separated into salt grain and waste gas, collects salt grain, make waste drum;And
Gained waste gas is filtered through HEPA, residual gas is emitted into air through inspection is qualified, completes chemistry
The process of waste liquid.
2. the processing method of nuclear power station radio chemistry waste liquid according to claim 1 is it is characterised in that in heat drying
Before separating radio chemistry waste liquid, collect radio chemistry waste liquid, and radio chemistry waste liquid is pre-processed, filter out
Large granular impurity therein.
3. the processing method of nuclear power station radio chemistry waste liquid according to claim 2 is it is characterised in that described pretreatment
The pH value also including regulation radio chemistry waste liquid is to neutrality.
4. the processing method of nuclear power station radio chemistry waste liquid according to claim 2 is it is characterised in that lived using GAC
Property charcoal bed filters out the large granular impurity in chemical waste fluid.
5. the processing method of nuclear power station radio chemistry waste liquid according to claim 1 is it is characterised in that described radioactivity
Chemical waste fluid is separated into salt grain and the gas containing dust by spray dryer heat drying.
6. the processing method of nuclear power station radio chemistry waste liquid according to claim 5 is it is characterised in that described radioactivity
Chemical waste fluid is thermally dried by spray dryer and is separated into salt grain and the gas detailed process containing dust is:
1) it is atomized:Chemical waste fluid, through the atomizer of spray dryer, dissipates into droplet;
2) it is dried:Make droplet with hot air using cocurrent mode and mix, in the temperature official post droplet of hot-air and droplet
Moisture evaporation and be dried;
3) separate:The moisture evaporation discharged respectively in droplet is dried, and forms the gas containing dust producing when salt grain and evaporation.
7. the processing method of nuclear power station radio chemistry waste liquid according to claim 1 is it is characterised in that described deduster
For sack cleaner, the gas containing dust is separated into salt grain and waste gas.
8. the processing method of nuclear power station radio chemistry waste liquid according to claim 1 is it is characterised in that described collection salt
Grain includes collecting the salt grain that the salt grain isolated of heat drying and removing dust device are isolated.
9. nuclear power station radio chemistry waste liquid according to claim 1 processing method it is characterised in that described make useless
Thing package body is that salt grain is loaded metal waste bucket, then metal waste barreled is entered high integrity container, forms waste drum.
10. nuclear power station radio chemistry waste liquid according to claim 1 processing method it is characterised in that described efficiently
Particulate air filter is used for filtering a diameter of 0.5 μm of particles below in waste gas.
A kind of 11. processing systems of nuclear power station radio chemistry waste liquid are it is characterised in that include:
Heat drying separator, for being separated into salt grain and containing dust by nuclear power station radio chemistry waste liquid heat drying
Gas;
Deduster, for being separated into salt grain and waste gas by the gas containing dust;
HEPA, for filtering waste gas;
Emission sensing device, the gaseous mass after filtering for detection and radiation value;And
Refuse packaging apparatus, for being packaged into waste drum by salt grain.
The processing system of 12. nuclear power station radio chemistry waste liquids according to claim 11 is it is characterised in that described process
System also includes rough filtering device, for filtering the large granular impurity in nuclear power station radio chemistry waste liquid.
The processing system of 13. nuclear power station radio chemistry waste liquids according to claim 11 is it is characterised in that described process
System also includes buffer unit, for housing nuclear power station radio chemistry waste liquid and adjusting its pH value.
The processing system of 14. nuclear power station radio chemistry waste liquids according to claim 11 is it is characterised in that described heating
It is provided with atomizer, for chemical waste fluid is atomized into droplet in Drying separator.
The processing system of 15. nuclear power station radio chemistry waste liquids according to claim 11 is it is characterised in that described heating
Drying separator is provided with the outlet for discharging salt grain and the exhaust outlet for discharging the gas containing dust, and outlet is located at and adds
The bottom of heated drying separator.
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CN201610944487.8A CN106448789A (en) | 2016-10-26 | 2016-10-26 | Processing method and system of radioactive chemical wastewater in nuclear power plant |
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Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN108062990A (en) * | 2018-01-11 | 2018-05-22 | 航天晨光股份有限公司 | A kind of radioactive liquid waste crystallizing and drying system and method |
CN108630335A (en) * | 2018-03-13 | 2018-10-09 | 中国核电工程有限公司 | Vacuum microwave drying system and drying means in a kind of radioactivity wet type pail for used dressings |
CN111681798A (en) * | 2020-04-30 | 2020-09-18 | 中国辐射防护研究院 | Small-size nuclear facility field radioactivity effluent treatment plant that retires |
JP2020183922A (en) * | 2019-05-09 | 2020-11-12 | 大川原化工機株式会社 | Contaminated water drying processing apparatus and contaminated water drying processing method |
Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4579069A (en) * | 1983-02-17 | 1986-04-01 | Rockwell International Corporation | Volume reduction of low-level radioactive wastes |
CN86106420A (en) * | 1985-10-04 | 1987-05-20 | 索马费尔公司 | Radioactive liquid waste is handled |
JPH05203795A (en) * | 1992-01-27 | 1993-08-10 | Ngk Insulators Ltd | Treatment of decontamination waste liquid |
JPH10311897A (en) * | 1997-05-09 | 1998-11-24 | Hitachi Ltd | Method and facility for disposing of waste liquid |
CN202034074U (en) * | 2011-03-30 | 2011-11-09 | 西北核技术研究所 | Liquid radioactive waste treating device |
CN104575651A (en) * | 2014-12-11 | 2015-04-29 | 中国核电工程有限公司 | Treatment device of radioactive contaminated wastewater |
CN105405485A (en) * | 2015-10-23 | 2016-03-16 | 西南科技大学 | Radioactive liquid waste treatment device |
-
2016
- 2016-10-26 CN CN201610944487.8A patent/CN106448789A/en active Pending
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4579069A (en) * | 1983-02-17 | 1986-04-01 | Rockwell International Corporation | Volume reduction of low-level radioactive wastes |
CN86106420A (en) * | 1985-10-04 | 1987-05-20 | 索马费尔公司 | Radioactive liquid waste is handled |
JPH05203795A (en) * | 1992-01-27 | 1993-08-10 | Ngk Insulators Ltd | Treatment of decontamination waste liquid |
JPH10311897A (en) * | 1997-05-09 | 1998-11-24 | Hitachi Ltd | Method and facility for disposing of waste liquid |
CN202034074U (en) * | 2011-03-30 | 2011-11-09 | 西北核技术研究所 | Liquid radioactive waste treating device |
CN104575651A (en) * | 2014-12-11 | 2015-04-29 | 中国核电工程有限公司 | Treatment device of radioactive contaminated wastewater |
CN105405485A (en) * | 2015-10-23 | 2016-03-16 | 西南科技大学 | Radioactive liquid waste treatment device |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN108062990A (en) * | 2018-01-11 | 2018-05-22 | 航天晨光股份有限公司 | A kind of radioactive liquid waste crystallizing and drying system and method |
CN108062990B (en) * | 2018-01-11 | 2024-06-07 | 航天晨光股份有限公司 | Radioactive waste liquid crystallization drying system and method thereof |
CN108630335A (en) * | 2018-03-13 | 2018-10-09 | 中国核电工程有限公司 | Vacuum microwave drying system and drying means in a kind of radioactivity wet type pail for used dressings |
JP2020183922A (en) * | 2019-05-09 | 2020-11-12 | 大川原化工機株式会社 | Contaminated water drying processing apparatus and contaminated water drying processing method |
CN111681798A (en) * | 2020-04-30 | 2020-09-18 | 中国辐射防护研究院 | Small-size nuclear facility field radioactivity effluent treatment plant that retires |
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Application publication date: 20170222 |