CN104332209A - Waste liquid processing system radiating waste liquid whirl separating purifying method and device - Google Patents
Waste liquid processing system radiating waste liquid whirl separating purifying method and device Download PDFInfo
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- CN104332209A CN104332209A CN201410452769.7A CN201410452769A CN104332209A CN 104332209 A CN104332209 A CN 104332209A CN 201410452769 A CN201410452769 A CN 201410452769A CN 104332209 A CN104332209 A CN 104332209A
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- ash bucket
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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
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- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01D—SEPARATION
- B01D21/00—Separation of suspended solid particles from liquids by sedimentation
- B01D21/26—Separation of sediment aided by centrifugal force or centripetal force
- B01D21/267—Separation of sediment aided by centrifugal force or centripetal force by using a cyclone
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- Chemical Kinetics & Catalysis (AREA)
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Abstract
The invention relates to a waste liquid processing system radiating waste liquid whirl separating purifying method and device and provides the waste liquid processing system radiating waste liquid whirl separating purifying method. The method comprises the following steps that (i) a micro whirl separating sleeve device is provided, wherein the micro whirl separating sleeve device comprises a shell body (1) including an upper cavity body, a middle cavity body (6) and a lower cavity body, a micro whirl separator (3) arranged inside the middle cavity body (6) and an ash bucket (9) arranged inside the upper cavity body, (ii) radiating waste liquid with particle impurities are sent to the middle cavity body of the micro whirl separating sleeve device, the micro whirl separator conducts the whirl separating on the radiating waste liquid, so that the particle impurities can be separated from the radiating waste liquid, and concentrate liquid with the particle impurities and clear liquid can be obtained; (iii) the obtained concentrate liquid with the particle impurities is sent to the upper cavity body to subside in the ash bucket, and filtering liquid is obtained; (iv) the obtained filtering liquid and the clear liquid are mixed and flow to downstream equipment.
Description
Technical field
The invention belongs to nuclear power field of Environment Protection, relate to that a kind of continuous cycle of operation is long, radioactivity solid waste generation is low and effectively can remove cyclonic separation method and the device of granule foreign in radioactive liquid waste, be specifically related to a kind of integrated mini-hydrocyclone separation device and filter the method that ash bucket purifies resin and other granule foreigns carried secretly in liquid waste treatment system of nuclear power plant radioactive liquid waste, and implement the method device used.
Background technology
Since nineteen ninety-five IAEA (International Atomic Energy Agency) delivers " nuclear power plant and nuclear fuel cycle terminal radioactive waste minimized " (No. 377, technical report book series), waste minimization has become the important component part of Radioactive waste management and nuclear Safety Culture attainment, and reflects the design level of nuclear power station, device systems reliability, safe operation and maintenance management level to a certain extent.In U.S.'s nuclear power URD at the beginning of the nineties (URD) and European nuclear power URD (EUR), regulation is made to the refuse cumulative volume (good-neighbourliness desired value) that the every platform unit of PWR nuclear power plant finally produces, require that final radioactive solid waste inclusion amasss <50m
3/ year.Whether current international nuclear power circle compares with this good-neighbourliness desired value and the nuclear power plant that running, and be one of 10 indexs of the nuclear power plant of function admirable in this, as this nuclear power plant of judge.And URD and EUR is while claiming to the safety of nuclear power station of future generation and designing technique, especially selecting of filtrator is proposed to the suggestion of " requiring to carry out strengths and weaknesses with other practicable techniques to compare ".
Filtrator is widely used in nuclear power station, for Daya Bay nuclear power plant, the system being applied to filtrator has cvcs (RCV), liquid waste treatment system (TEU), reactor boron and water supply system (REA), the cooling of reactor Spent Fuel Pool and disposal system (PTR) etc.; According to the preliminary statistics, nearly nearly hundred filtrators of the every platform of current operating CPR 1000 type nuclear power station unit.These filtrators carry the effect of the upstream device safety that purifies water, protects in nuclear power station.But major part is all in radioactive environment in these filtrators, its filter core needs after reaching the life-span to change on request, becomes the radioactive useless filter core of band and need to carry out isolation to store; Periodic filter element replacing is not only with high costs, causes a large amount of radioactivity solid waste, also to safeguarding that replacing work brings potential nuclear radiation risk.
The research of the new and effective separation method of current exploration nuclear power station comprises: Chinese patent ZL201010128657.8 discloses a kind of device utilizing supercritical water to filter nuclear power station fine particle potpourri, Chinese patent ZL 201110220075.7 discloses a kind of device arranging immersion type film and reclaim for radioactivity solid waste in nuclear power station radiology devices in solid-liquid separation tank, Chinese patent ZL 201010272918.3 discloses a kind of accurate filter that utilizes and carries out the method for purification filtering for nuclear power station condensation water precision processing system, but above method is all failed effectively to solve radioactive solid and to be given up secondary pollution, make the common problems such as device operation steady in a long-term.
At present, cyclone widespread use to numerous industries such as petrochemical complex, biological medicine, mining coal separations, correlative study comprises: Chinese patent ZL 200910045839.6 discloses a kind of square law device utilizing cyclone to remove particle in coal tar, Chinese patent ZL 200810042716.2 discloses one and utilizes micro-cyclone to reclaim the method for spent catalyst in MTO (methanol-to-olefins) quenched water and washing water, but current Nuclear Power Industry carries out the research report of radioactive liquid waste purification applications temporarily without application cyclone.
Therefore, this area is in the urgent need to developing a kind of defect of above-mentioned prior art that overcomes, the separating technology that solid waste generation is less when nuclear power station radioactive liquid waste purifies, the device continuous cycle of operation is longer and device.
Summary of the invention
The invention provides a kind of liquid waste treatment system radioactive liquid waste cyclonic separation purification method and device of novelty, replace filtrator to remove the resin and other granule foreign carried secretly in radioactive liquid waste at nuclear power field of Environment Protection mini-hydrocyclone separation device, thus solve problems of the prior art.
On the one hand, the invention provides a kind of liquid waste treatment system radioactive liquid waste cyclonic separation purification method, the method comprises the following steps:
I () provides mini-hydrocyclone separation complete equipment, this device comprises: the housing comprising upper chamber, middle part cavity and lower cavity; Be placed in the mini-hydrocyclone separation device of middle part cavity; Be placed in the ash bucket of upper chamber;
(ii) radioactive liquid waste containing granule foreign is transported in the middle part cavity of these mini-hydrocyclone separation complete equipment, by mini-hydrocyclone separation device, cyclonic separation is carried out to radioactive liquid waste, to be separated from radioactive liquid waste by granule foreign, obtain the concentrate containing granule foreign and clear liquid;
(iii) concentrate containing granule foreign of gained is sent in upper chamber, with sedimentation in ash bucket, obtain filtrate;
(iv) upstream device is flow to after the filtrate of gained and the clear liquid of gained being converged.
In one preferred embodiment, the separation efficiency of described mini-hydrocyclone separation device is 90% or higher, and pressure drop is no more than 0.15MPa.
Another preferred embodiment in, in step (iii), granule foreign is stopped by the filter screen of ash bucket periphery and is deposited in bottom, and filtrate is leached by the filter opening of ash bucket periphery or overflowed by ash bucket edge.
On the other hand, the invention provides a kind of liquid waste treatment system radioactive liquid waste cyclonic separation purification plant, this device comprises:
Comprise the housing of upper chamber, middle part cavity and lower cavity;
Be placed in the mini-hydrocyclone separation device of middle part cavity;
Be placed in the ash bucket of upper chamber.
In one preferred embodiment, the upper chamber in described housing, middle part cavity and lower cavity are formed by tube sheet, are three closed cavities.
Another preferred embodiment in, ash bucket is connected with the underflow opening of mini-hydrocyclone separation device by underflow header.
Another preferred embodiment in, described micro-eddy flow core pipe takes invert form to be assemblied in housing.
Another preferred embodiment in, movable assembly structure taked by described ash bucket; Ash bucket periphery is filter opening structure, and filter pore size is determined according to granule foreign domain size distribution.
Another preferred embodiment in, leave gap between described ash bucket and housing, on ash bucket along and Casing top between leave space, so that the discharge of purifying waste water leaching or overflow.
Again on the one hand, the present invention relates to said method or the device purposes for radioactive liquid waste purifications all in nuclear power station three wastes system.
Accompanying drawing explanation
According to carrying out following detailed description by reference to the accompanying drawings, object of the present invention and feature will become more obvious, in accompanying drawing:
Fig. 1 is the process chart purified according to the liquid waste treatment system radioactive liquid waste cyclonic separation of an embodiment of the invention.
Fig. 2 is the process chart of the liquid waste treatment system radioactive liquid waste cyclonic separation purification comprising liquid waste treatment system radioactive liquid waste cyclonic separation purification plant of the present invention according to an embodiment of the invention.
Embodiment
Present inventor finds after have passed through extensive and deep research, cyclone has the advantages such as separation efficiency is high, reliability is high, applied widely, be applied to nuclear power station cleaning system, it is the most effective and cheap that the solid-liquid system large for this operational ton of liquid waste treatment system radioactive liquid waste, solids content is low carries out isolation of purified; Replace liquid waste treatment system of nuclear power plant filtrator to remove granule foreign with cyclone, can significantly reduce solid waste generation, and obviously extend the cleaning system continuous cycle of operation, effectively avoid the nuclear radiation that equipment replacement causes; Meet the target that cleaning system effectively reduces the solid waste in waste liquid simultaneously, guarantee that follow-up liquid waste treatment system properly runs.Based on above-mentioned discovery, the present invention is accomplished.
In a first aspect of the present invention, provide a kind of method that efficient low-consume removes granule foreign in nuclear power liquid waste treatment system radioactive liquid waste, it comprises the following steps:
Radioactive liquid waste containing granule foreign enters mini-hydrocyclone separation device group, is separated by most granule foreign from waste liquid, the radioactive liquid waste be purified;
Collect from mini-hydrocyclone separation device group underflow opening out concentrated containing solid waste liquid and be pooled to movable ash bucket by underflow header, concentrating spent liquor experiences in good time sedimentation in ash bucket, and liquid phase is leached by the filter opening of ash bucket periphery;
The filtrate leached through ash flue bucket is with cyclone overflow product stream to upstream device.
In the present invention, ash bucket is changed by specific purpose tool during major overhaul.
Method of the present invention is applicable to all radioactive liquid waste process for purifying in nuclear power station three wastes system.
In the present invention, be 0.5MPa by simulated waste disposal system intake pressure, flow is 10m
3/ h contains micro-resin wastewater, and after cyclonic separation, in waste liquid, solid particle separation efficiency reaches 90%, and tripping device pressure drop continues at about 0.15MPa.
In the present invention, after underflow is collected to ash bucket, solid phase stays hopper bottom through in good time sedimentation, and filtrate is leached by ash bucket surrounding filter screen, or is overflowed by ash bucket top sedimentation, leach or the filtrate of overflowing substantially not containing solid particle.
In the present invention, be 0.5MPa for intake pressure, flow is 10m
3the radioactive wastewater of/h carries out purified treatment, by appropriate design ash bucket arrangement and size, can guarantee that the replacement cycle of ash bucket is 10 years, avoid in traditional handicraft a large amount of radioactivity solid wastes adopting filtrator to cause.
In a second aspect of the present invention, provide a kind of device for said method, this device comprises:
For the housing of integrated a whole set of separating technology, for the mini-hydrocyclone separation device assembly that radioactive liquid waste is separated with solid particle polluter, the underflow header be connected with described mini-hydrocyclone separation device assembly underflow opening, and the movable ash bucket be connected with underflow header.
In the present invention, mini-hydrocyclone separation device takes invert form to be assemblied in housing.
In the present invention, forms three closed chambers by tube sheet in housing, be respectively the underflow collection chamber on the overflow collection chamber of bottom, the feed cavity at middle part and top.
In the present invention, movable assembly structure taked by underflow ash bucket, so that follow-up replacing.
In the present invention, ash bucket periphery is filter opening structure, and filter pore size is determined according to impurity domain size distribution, to guarantee that solid particle is all collected in ash bucket.
In the present invention, leave gap between ash bucket and housing, ash bucket also leaves space between edge and Casing top, the liquid phase of being convenient to leach or overflow is discharged.
In the present invention, the quantity of the mini-hydrocyclone separation device assembly in described housing can make the appropriate adjustments according to liquid waste processing amount, and the grey bucket structure of corresponding adjustment, to meet the effluent purifying in different system and flow process.
In the present invention, return to the import of mini-hydrocyclone separation device to realize multi-cycle separation through the waste liquid that movable ash bucket limit wall filters or standing sedimentation overflows, thus improve magazins' layout efficiency.
Below method of the present invention is described with reference to the accompanying drawings in detail.
Fig. 1 is the process chart purified according to the liquid waste treatment system radioactive liquid waste cyclonic separation of an embodiment of the invention.As shown in Figure 1, mini-hydrocyclone separation complete equipment comprise: the housing 1 comprising upper chamber, middle part cavity 6 and lower cavity; Be placed in the mini-hydrocyclone separation device 3 of middle part cavity 6; Be placed in the ash bucket 9 of upper chamber, it is connected with mini-hydrocyclone separation device underflow opening 5 by underflow header 7; This housing 1 also comprises import 2, overflow vent 4 and underflow outlet 8, and wherein, radioactive liquid waste is transported in the middle part cavity 6 of device through import 2, carries out cyclonic separation by mini-hydrocyclone separation device 3 pairs of radioactive liquid wastes, to remove the solid impurities such as the resin particle carried secretly; Isolated concentrate is through mini-hydrocyclone separation device underflow opening 5 and enter in upper chamber through underflow header 7, sedimentation in ash bucket 9, solid impurity is stopped by the filter screen of ash bucket 9 periphery and is deposited in hopper bottom, and liquid phase is leached by the filter opening of ash bucket 9 periphery or overflowed by ash bucket edge; The filtrate leached through ash flue bucket is flowed out through underflow outlet 8, with the overflow of mini-hydrocyclone separation device through overflow vent 4 assemble jamming to upstream device, to meet follow-up operating mode.Fig. 1 also show the sectional view of wherein A-A line and B-B line.
Fig. 2 is the process chart of the liquid waste treatment system radioactive liquid waste cyclonic separation purification comprising liquid waste treatment system radioactive liquid waste cyclonic separation purification plant of the present invention according to an embodiment of the invention.As shown in Figure 2, the radioactive liquid waste collected from unit waste liquid Rendezvous Point leaves standstill storage tank 21, enters the charging cavity of separation vessel 22, evenly enter each micro-eddy flow core pipe through valve regulated and pumping; After being separated, the waste liquid be cleaned from mini-hydrocyclone separation device overflow vent out; Underflow liquid enters ash bucket by underflow chamber by underflow header, underflow suitably leaves standstill in ash bucket, and liquid part is overflowed from the filter opening of ash bucket periphery, and collects with mini-hydrocyclone separation overflow, flow to cation bed desalination device 23 and the desalination of mixed bed desalination device 24 in downstream, realize the further purification of waste liquid; Waste liquid flows into surge tank 25 in parallel afterwards, is finally pooled to de-liquid in evaporator 26, realizes the complete process of radioactive liquid waste.
Major advantage of the present invention is:
A, obviously reduction radioactivity solid waste generation;
B, significantly improve the device continuous cycle of operation;
C, suitably reduce separation costs.
Embodiment
The present invention is set forth further below in conjunction with specific embodiment.But, should be understood that these embodiments only do not form limitation of the scope of the invention for illustration of the present invention.The test method of unreceipted actual conditions in the following example, usually conveniently condition, or according to the condition that manufacturer advises.Except as otherwise noted, all number percent and number are by weight.
embodiment 1:
liquid waste treatment system of nuclear power plant radioactive liquid waste cyclonic separation purifies
1. implementing procedure
As shown in Figure 2.
2. key equipment
In this technological process, key equipment is the complete separation vessel of mini-hydrocyclone separation device and filterableness ash bucket of being coupled.Wherein, be inverted vertical mini-hydrocyclone separation device assembly side by side and be placed within separation vessel, filterableness ash bucket is placed in separation vessel top to be connected mini-hydrocyclone separation device underflow.Device processes amount is 10m
3/ h, physical dimension is Φ 600 × 2400.And separation vessel top takes tube-sheet type to close, be convenient to follow-up ash bucket and change.
3. control
At full capacity under operating mode, separation vessel feed rate is 10m
3/ h, feed pressure is 0.5MPa (gauge pressure), and operating temperature is normal temperature.
4. operation result
Under operating condition, the waste water containing micro-resin particle enters separation vessel under pumping action, converges laggard cyclone separator in a subtle way by the feed cavity in portion in the separator; Experimental simulation charging is density is 1.15g/cm
3resin concentration is the mixture of 10ppm, and in charging, solid phase distribution is continuous.Enter the mixed phase of mini-hydrocyclone separation device under centrifugal action, rely on density difference to realize rapidly being separated in mini-hydrocyclone separation device, in overflow, disperse phase resin particle concentration is greatly reduced, and laboratory ON-LINE SEPARATION efficiency is all more than 90%.And overflowed into ash bucket by the underflow thing after significantly concentrating by the underflow conduit connecting ash bucket in underflow chamber, then under ash bucket peripheral overflow hole is blocked, continuous phase clear water is got rid of gradually, and be back to separation vessel import; Meanwhile, the solid particle be blocked by slowly leaving standstill, deposits gradually in ash bucket in ash bucket, realizes being separated of solid particle polluter and clear water, meets the separation accuracy requirement of nuclear power station three wastes system.Under there is obvious fluctuation situation in solid particle polluter concentration in charging, mini-hydrocyclone separation device and ash bucket sedimentation filtration efficiency normal, realistic fluctuation operating mode, overall operation is good.
Energy consumption aspect, the piping loss in mini-hydrocyclone separation device and separation vessel is no more than 0.15MPa, and relative filtrator is separated, especially there is certain advantage in the filtrator work later stage; And the pressure drop that the sedimentation filtration process of ash bucket produces does not impact actual process flow process.
5. technique effect
A () obviously reduces radioactivity solid waste generation
By adopting mini-hydrocyclone separation technique purification radioactive liquid waste, substituting traditional filtration and separation techniques, significantly reducing a large amount of solid waste because filter element replacing causes and supporting standby redundancy expends quantity.According to the preliminary statistics, the filter element replacing quantity that separate unit CPR 1000 unit is annual is more than 100; Single useless filter core weight room treatment capacity after filtration and processing accuracy require to be not quite similar, but at least all more than tens kilograms, namely the solid waste that rough estimation causes thus reaches several ton.For Daya Bay nuclear power plant's No. 1 unit, the solid waste caused because of filter core is every year more than 6 tons; Especially in three wastes system, most waste liquid belongs to high radioactivity, and Renewal process more exists obvious potential safety hazard.Progressively reduce the requirement of nuclear power station solid waste according to IAEA, by the replacing repeatedly taking mini-hydrocyclone separation technique to avoid filter core, positive environmental benefit will be produced; The minimizing that simultaneously also can expend because of filter core and produce outstanding economic benefit.
B () significantly improves the device continuous cycle of operation
For nuclear power generating sets, especially for the system containing radiomaterial, the replacing of equipment not only threatens the critical path of unit maintenance, more causes the danger that unnecessary radiating medium is revealed, and the radiation dose that periphery staff is unnecessary.By taking mini-hydrocyclone separation technique, equipment is by appropriate design ash bucket size, and can guarantee that the continuous cycle of operation of separation vessel reaches 10 years, this relative filtrator has had obvious lifting less than the cycle of operation of 1 year.
C () suitably reduces separation costs
Mini-hydrocyclone separation technique by continuing to optimize device structure, under the basicly stable condition of feed rate, within the pressure drop basic controlling 0.15MPa of detachment process; And filtrator progressively gathering along with filter residue, the pressure drop that waste liquid causes progressively is increased, until the designing requirement of pressure drop operating procedure, again reduces pressure drop by filter element replacing.And the design pressure drop of filtrator is usually at 0.25MPa, this proposes requirements at the higher level to pump consumption, and mini-hydrocyclone separation has more advantage comparatively speaking.Meanwhile, the pressure drop of metre filter process is the process gradually changed, and obviously, this is also unfavorable for the stable and high effective operation of follow-up equipment in period fluctuation; And mini-hydrocyclone separation device can guarantee pressure drop all-the-time stable in the situation that inlet flow rate is stable.
Study by experiment, full simulation CPR 1000 type nuclear power station three wastes system radioactive liquid waste solid particle polluter process for purifying, experimental result shows that mini-hydrocyclone separation process operation is stablized, simple operation, period, the separation efficiency of separation vessel remained at more than 90%, and pressure drop is no more than 0.15MPa, this measure meets on-the-spot unit operation requirement completely.Simultaneously, mini-hydrocyclone separation technique is adopted to substitute traditional filtrator separating technology, not only will obviously reduce the operating cost of unit, and will significantly reduce solid waste generation, also the stable operation cycle of system was brought up to 10 years by the filtrator epoch less than 1 year, not only reduce the workload of filter element replacing, also reduce the radiation dose that operations staff is unnecessary, there is significant environmental benefit and economic benefit.
The all documents mentioned in the present invention are quoted as a reference all in this application, are just quoted separately as a reference as each section of document.In addition should be understood that those skilled in the art can make various changes or modifications the present invention, and these equivalent form of values fall within the application's appended claims limited range equally after having read above-mentioned instruction content of the present invention.
Claims (10)
1. a liquid waste treatment system radioactive liquid waste cyclonic separation purification method, the method comprises the following steps:
I () provides mini-hydrocyclone separation complete equipment, this device comprises: the housing (1) comprising upper chamber, middle part cavity (6) and lower cavity; Be placed in the mini-hydrocyclone separation device (3) at middle part cavity (6); Be placed in the ash bucket (9) of upper chamber;
(ii) radioactive liquid waste containing granule foreign is transported in the middle part cavity of these mini-hydrocyclone separation complete equipment, by mini-hydrocyclone separation device, cyclonic separation is carried out to radioactive liquid waste, to be separated from radioactive liquid waste by granule foreign, obtain the concentrate containing granule foreign and clear liquid;
(iii) concentrate containing granule foreign of gained is sent in upper chamber, with sedimentation in ash bucket, obtain filtrate;
(iv) upstream device is flow to after the filtrate of gained and the clear liquid of gained being converged.
2. the method for claim 1, is characterized in that, the separation efficiency of described mini-hydrocyclone separation device is 90% or higher, and pressure drop is no more than 0.15MPa.
3. method as claimed in claim 1 or 2, is characterized in that, in step (iii), granule foreign is stopped by the filter screen of ash bucket periphery and is deposited in bottom, and filtrate is leached by the filter opening of ash bucket periphery or overflowed by ash bucket edge.
4. a liquid waste treatment system radioactive liquid waste cyclonic separation purification plant, this device comprises:
Comprise the housing (1) of upper chamber, middle part cavity (6) and lower cavity;
Be placed in the mini-hydrocyclone separation device (3) at middle part cavity (6);
Be placed in the ash bucket (9) of upper chamber.
5. device as claimed in claim 4, it is characterized in that, the upper chamber in described housing, middle part cavity and lower cavity are formed by tube sheet, are three closed cavities.
6. device as claimed in claim 4, it is characterized in that, ash bucket (9) is connected with the underflow opening (5) of mini-hydrocyclone separation device by underflow header (7).
7. the device according to any one of claim 4-6, is characterized in that, described micro-eddy flow core pipe takes invert form to be assemblied in housing.
8. the device according to any one of claim 4-6, is characterized in that, movable assembly structure taked by described ash bucket; Ash bucket periphery is filter opening structure, and filter pore size is determined according to granule foreign domain size distribution.
9. the device according to any one of claim 4-6, is characterized in that, leaves gap between described ash bucket and housing, and ash bucket leaves space between edge and Casing top, so that the filtrate discharge leaching or overflow.
10. the method according to any one of claim 1-3 or the device according to any one of claim 4-9 are used for the purposes of all radioactive liquid waste purifications in nuclear power station three wastes system.
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