CN117059292A - Pretreatment system for solid-liquid separation of nuclear medical radioactive wastewater and application method - Google Patents
Pretreatment system for solid-liquid separation of nuclear medical radioactive wastewater and application method Download PDFInfo
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- CN117059292A CN117059292A CN202311036063.8A CN202311036063A CN117059292A CN 117059292 A CN117059292 A CN 117059292A CN 202311036063 A CN202311036063 A CN 202311036063A CN 117059292 A CN117059292 A CN 117059292A
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Classifications
-
- 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
-
- 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
- G21F9/10—Processing by flocculation
-
- 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
- G21F9/30—Processing
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Separation Of Suspended Particles By Flocculating Agents (AREA)
Abstract
The invention discloses a nuclear medicine radioactive wastewater pretreatment system and an application method thereof, comprising the following steps: the device comprises a solid-liquid primary separation unit, a homogenizing unit, an inclined tube type solid-liquid secondary separation unit, a clear water output unit and a sludge reflux unit in an original decay tank; the monitoring module is matched with the solid-liquid secondary separation unit to monitor the slurry storage height in the solid-liquid secondary separation unit; the control module is in communication connection with the monitoring module; the homogenization unit configuration includes: at least two coagulation reaction tanks which are communicated with each other; stirring components and dosing modules matched with the coagulation reaction tanks. The invention discloses a pretreatment system for solid-liquid separation of nuclear medical radioactive wastewater and an application method thereof, wherein the nuclear medical radioactive wastewater is subjected to necessary pretreatment before deep purification, so that the efficiency of deep purification of rear-end radionuclides can be effectively improved, the service life of a treated material is prolonged, the cycle times are increased, the cost is reduced, and the irradiation risk during material replacement is reduced.
Description
Technical Field
The invention relates to the field of medical wastewater treatment. More particularly, the invention relates to a pretreatment system for solid-liquid separation of nuclear medical radioactive wastewater and an application method thereof.
Background
In recent years, the use amount of radionuclides in the medical field is explosive, and radioactive wastewater with complex components is generated in the nuclear medicine diagnosis and treatment process, and the treatment of the radioactive wastewater directly restricts the nuclear medicine consultation amount, so that great importance is attached to the treatment of the radioactive wastewater. The sources of nuclear medicine radioactive wastewater mainly comprise three aspects: (1) during diagnosis and treatment, the patient receives the radioactive isotope and the resulting excrement (70% of the medicine is excretedDischarged outside the body); (2) cleaning water generated by a medicine cup, a syringe, a pipette and other vessels used for dispensing the high-intensity radioactive isotopes taken by a patient; (3) preparation of medical labeling compounds (cyclotron, hot cell) and dumping of radioactive waste water discharged from excess doses of radioisotope. Commonly used radionuclides are 131 I (iodine), 99m Tc (technetium), 89 Sr (strontium), 153 Sm (samarium), 32 P (phosphorus), 18 F (fluorine), 125 I (iodine), etc. According to relevant regulations of the hospital sewage treatment technical guide issued by the national environmental protection agency in 2003: the concentration range of the hospital radioactive wastewater is 3.7X10 2 Bq/L～3.7×10 5 Bq/L belongs to low-level wastewater.
The nuclear medicine radioactive wastewater has the following characteristics: the popularity of the method is increased. Compared with the radioactive waste water in nuclear industry, the daily displacement of the radioactive waste water in nuclear medicine is small (about 0.2-5m according to the current hospital consultation quantity 3 D), the drainage volume of each patient is generally from tens to hundreds of liters, but with the popularization of nuclear medicine in various departments of hospitals, the drainage volume is also increasing; the species of the nuclides are multiple. The radionuclide used in the nuclear medical diagnosis and treatment process has a plurality of types, different nuclide decay periods and different generated ray types, and allows different emission quality and concentration, so that the design of the treatment process is quite difficult. The composition is complex. Based on the metabolic process of human body, the composition is a mixture of solid waste and liquid waste, contains a large amount of inorganic matters and organic matters, has high content of suspended matters and particles, and is particularly a water-soluble polymer which is difficult to degrade.
The pretreatment of the nuclear medical radioactive wastewater has the difficulty that the pollution load is high, the nuclear medical radioactive wastewater is in a stable colloid system, the components are extremely complex, and the nuclear medical radioactive wastewater is difficult to treat by adopting a single means. Therefore, the research and development of the efficient pretreatment method of the nuclear medicine radioactive wastewater reduces or eliminates the pollution of the nuclear medicine radioactivity to the environment and has great significance for the medical environment protection.
At present, the nuclear medicine radioactive wastewater treatment process mainly adopts a storage decay method, namely, the radioactivity of the radioactive wastewater is reduced or eliminated by means of natural decay. Radioactive waste water is discharged into a decay tank to be stored for a certain time for natural treatmentDecay (generally 10 half-lives of the nuclides with the longest half-life in the wastewater) and discharging the wastewater into a conventional waste liquid treatment pipe network system of a hospital when the radioactivity index of the wastewater reaches the national management limit, wherein two forms of continuous and intermittent decay tanks are mainly adopted in engineering. The continuous plug flow type decay tank (as shown in fig. 7) is usually built together with a septic tank, wherein the first cell is the septic tank, and the last three cells are all decay tanks. The water flows entering the lower-level tank bodies are separated by a guide wall. For the following 131 I, when the waste liquid flows out of the last stage decay tank, the duration is generally longer than 83 days, the radioactivity of the waste liquid is reduced to the limit value, the waste liquid can be used for conventional waste water treatment in hospitals after the sampling detection reaches the standard, and the nuclear medical waste water is required to be temporarily stored for 6 months at present.
The intermittent type decay tank (as shown in fig. 8) adopts an alternative storage mode, namely, the 1 st decay tank is filled with waste water and then is subjected to sealing treatment (the beginning decay time of the first decay tank is marked at the moment), then the next decay tank is started, and when the last decay Chi Qi is used, the waste liquid in the first decay tank reaches the non-discharge requirement and is used as common medical waste water for further treatment. The radiation protection of the decay tank can be realized by selecting a finished stainless steel plate water tank with protective measures and complete control equipment. Each group of decay tanks can alternately and intermittently run (a remote water level display device, an electric valve on-off state monitoring device, an alarm device and a manual control electromagnetic valve/submersible pump are needed).
The continuous decay tank has the advantages of small tank volume, small occupied area, low cost, simple operation, no need or little maintenance, and the like, and is a mode commonly adopted in engineering. However, the biggest disadvantage is poor impact resistance, and if accidents such as leakage of radioactive substances occur, and the radioactive substances in the waste water increase, the waste water still has to be discharged when the waste water is not decayed to the allowable discharge concentration in the decay tank, and the radioactive pollution accidents can be caused. The intermittent decay tank has the advantages of strong impact resistance, stable and reliable effluent quality, and can prolong the stay time of waste liquid in the decay tank through delayed discharge when radioactive substances in the waste water increase if accidents such as radioactive substance leakage occur, ensure that the waste water decays to the allowable discharge concentration and is discharged, and avoid causing radioactive pollution accidents. Its advantages are large volume, large area, high cost, and relatively complex control. Generally, the existing treatment scheme of the storage attenuation type is more convenient, but the method for treating the nuclear medicine radioactive wastewater has the advantages of limited water storage capacity and longer wastewater storage period (at least 3 months, generally 6 months), and can not meet the increasing requirements of nuclear medicine diagnosis and treatment and rapid development of nuclear medicine.
Disclosure of Invention
It is an object of the present invention to address at least the above problems and/or disadvantages and to provide at least the advantages described below.
To achieve these objects and other advantages and in accordance with the purpose of the invention, there is provided a nuclear medicine radioactive wastewater pretreatment system, comprising:
a solid-liquid primary separation unit in the original decay tank;
a homogenizing unit communicated with the solid-liquid primary separation unit;
a solid-liquid secondary separation unit communicated with the wastewater output end of the homogenizing unit;
a clear water output unit communicated with the clear water output end of the solid-liquid secondary separation unit;
a monitoring module which is matched with the solid-liquid secondary separation unit to monitor the slurry storage height in the solid-liquid secondary separation unit;
the control module is in communication connection with the monitoring module;
the sludge reflux unit is connected with the control module;
wherein the homogenization unit is configured to include:
at least two flocculation reaction tanks which are communicated with each other;
and the stirring assembly and the dosing module are matched with each flocculation and coagulation-assisting reaction tank.
Preferably, the solid-liquid primary separation unit is a filter screen which is arranged in the original decay tank and the periphery of which is closed;
wherein, the filter screen is internally provided with a water pump for conveying stock solution of solid-liquid separation to the homogenizing unit.
Preferably, the solid-liquid secondary separation unit is configured to adopt at least one primary sedimentation tank provided with inclined pipes in a sedimentation zone, wherein the sedimentation tank comprises a mud-water separation zone, an inclined pipe sedimentation zone, a clear water zone and a sludge reflux zone in terms of space according to functions;
the inclined tube sedimentation zone is formed by constructing a plurality of parallel inclined tubes and branch tubes in space so as to divide the inclined tube sedimentation zone into a series of shallow sedimentation layers in a horizontal flow type or vertical flow type.
Preferably, the monitoring module is configured to include:
the sensor is arranged in the solid-liquid secondary separation unit and used for monitoring the height of slurry formed by solid-liquid separation;
a flowmeter for detecting the flow of wastewater.
Preferably, the sludge reflux unit is started when the monitoring module performs positive feedback, and the sludge separated by the solid-liquid secondary separation unit is pumped back to the original decay tank.
An application method of a nuclear medicine radioactive wastewater pretreatment system, comprising the following steps:
step one, after nuclear medical radioactive wastewater flows into a primary decay tank, a pretreatment raw liquid is separated by a solid-liquid primary separation unit, the raw liquid is pumped into a homogenizing unit by a controllable pump, and radioactive solid waste is retained in the primary decay tank, so that solid-liquid primary separation is realized.
Step two, after the treatment fluid enters a homogenizing unit, adding a compound coagulant and a coagulant aid through a dosing module under the stirring condition to carry out coagulation treatment;
after the wastewater subjected to coagulation treatment flows through a solid-liquid secondary separation unit, solid-liquid separation treatment is carried out through an inclined tube sedimentation zone in the wastewater to obtain corresponding supernatant and slurry;
step three, enabling the supernatant to enter a clear water output unit through a wastewater lifting module I and a filtering module for further homogenization, and then pumping the supernatant into a deep purification unit through a wastewater lifting module II for further treatment so as to enable the supernatant to meet the standard of standard emission;
the on-line monitoring module monitors the slurry storage height in the solid-liquid separation unit in real time so as to pump the separated radioactive solid waste back to the decay tank through the sludge reflux unit pump for storage decay treatment after the height reaches a preset value, and the radioactive solid waste is discharged to a conventional sewage treatment system in a hospital after the radioactive solid waste decays to an allowable discharge concentration.
Preferably, the coagulant aid includes, but is not limited to, polyacrylamide, activated silica, clay, polyelectrolyte; the coagulant includes, but is not limited to, polyaluminum chloride, potassium aluminum sulfate, sodium sulfate, ferric chloride.
Preferably, the particles in the wastewater are interfered by structures of all shallow sedimentation layers, and move and separate from each other in all shallow sedimentation layers;
the mutual movement direction is divided into three types of different flow, same flow and lateral flow.
The invention at least comprises the following beneficial effects: the nuclear medical wastewater is mainly in a solid and liquid mixture state, and has extremely complex components, and the invention carries out necessary pretreatment on the radionuclide in the nuclear medical wastewater before carrying out the deep purification treatment on the radionuclide by arranging the pretreatment system, so that the efficiency of the rear-end deep treatment can be effectively improved, the service life of the treated material can be prolonged, the cycle times can be increased, the cost can be reduced, and the irradiation risk during material replacement can be reduced.
Additional advantages, objects, and features of the invention will be set forth in part in the description which follows and in part will become apparent to those having ordinary skill in the art upon examination of the following or may be learned from practice of the invention.
Drawings
FIG. 1 is a schematic process flow diagram of a wastewater pretreatment system of the present invention;
FIG. 2 is a schematic diagram of the structural layout of the wastewater pretreatment system of the present invention;
FIG. 3 is a schematic diagram of the structural layout of a homogenization unit of the present invention;
FIG. 4 is a schematic diagram showing the structural layout of the combination of the homogenizing unit and the solid-liquid secondary separating unit and the clear water output unit;
FIG. 5 is a schematic top view of FIG. 4;
FIG. 6 is a schematic view of the construction of the chute bracket of the present invention;
FIG. 7 is a schematic process flow diagram of a prior art continuous decay cell;
FIG. 8 is a schematic process flow diagram of a batch decay cell of the prior art.
Detailed Description
The present invention is described in further detail below with reference to the drawings to enable those skilled in the art to practice the invention by referring to the description.
As shown in fig. 1 to 6, the wastewater pretreatment system of the present invention mainly comprises a solid-liquid primary separation unit 1 of a decay tank, a homogenization unit 2 of wastewater coagulation reaction, a slant pipe type solid-liquid secondary separation unit 3, a sludge backflow unit 4, a clear water output unit (also called a clear water zone) 5, an on-line monitoring module 6, and a control unit (not shown). The control unit adopts a PLC with an operation station to monitor, control, interlock and alarm the process parameters, the electrical parameters and the running conditions of the pump of the production unit. The on-line monitoring module mainly monitors the waste water flow, the storage height of the slurry, etc., of course, in order to realize solid-liquid transfer of each stage, a matched executing mechanism (such as a waste water lifting module and a sludge reflux pump, which will be described later) needs to be arranged between each stage, and the control unit is in communication connection with each executing mechanism so as to control the switching of the working states of the executing mechanisms.
The solid-liquid primary separation unit is arranged in the original decay tank, and the periphery of the solid-liquid primary separation unit is provided with a filter screen with a closed periphery;
wherein, the filter screen is internally provided with a water pump, and the stock solution of solid-liquid separation is conveyed to the homogenizing unit.
The homogenization unit of the coagulation reaction of the mixed wastewater mainly comprises at least two flocculation tanks 20, 21, a mechanical stirrer 22 and a dosing module (not shown), wherein the flocculation and coagulation reaction is carried out by at least two stages, the collected nuclear medical wastewater passes through the first-stage flocculation tank and the second-stage flocculation tank, the control unit carries out real-time measurement on the wastewater flow rate through an electronic flowmeter, the corresponding dosing amount is calculated according to the measurement result, the dosing module is controlled to pump quantitative coagulant aid and flocculant according to the calculated dosing amount, the mechanical stirrer is controlled to be in an operating state, so that the added coagulant aid and flocculant are mixed with the wastewater under the rapid stirring action of the mechanical stirrer, the control unit determines the standing time after mixing according to the wastewater flow rate or the amount of the wastewater in the flocculation tank, the whole coagulation treatment is completed, the measurement of the wastewater is realized by an electronic or ultrasonic liquid level meter, in practical application, the flocculation tank and the coagulation aid tank are integrally arranged through an external shell, the two corresponding coagulation reaction tanks are obtained through two partition plates 23 at intervals, the partition plate heights in the flocculation tank are configured to be smaller than the shell heights, the upper partition plate heights are matched with the coagulation aid tank through a cone-shaped structure II, and the upper partition plate I is communicated with the coagulation aid tank through a lower partition plate II, and the lower partition plate II is communicated with the coagulation aid tank through a cone-shaped structure 25, and the upper part is communicated with the bottom part of the coagulation aid tank is communicated with the upper part through a bottom part of a cone-shaped tank 25;
further, the mechanical agitators respectively arranged in the flocculation tank and the coagulation assisting tank comprise a corresponding motor 27, a stirring shaft 28 and stirring blades 29, and the positions of the stirring blades are at a preset distance from the bottom.
The inclined tube sedimentation tank is characterized in that an inclined tube sedimentation area is arranged in the sedimentation tank, and the inclined tube sedimentation tank specifically comprises: the settling zone 30, the inclined tube settling zone 31, the mud-water separation zone 32 and the sludge reflux zone 33 are assembled in the form of two inclined tubes and branch tubes, and the inclined parallel tubes or parallel pipelines (sometimes using honeycomb fillers) are utilized to divide the settling zone of the horizontal flow type or vertical flow type settling tank into a series of shallow settling layers, and the treated and settled sludge moves and is separated in each settling shallow layer. According to the mutual movement direction, the three different separation modes of reverse (different) flow, same-direction flow and lateral flow are divided.
The sludge reflux zone consists of a sludge collecting zone and a relative sludge reflux pump, the output end of the sludge reflux pump is communicated with a sludge reflux unit, the monitoring module is arranged at the position of the top end of the sludge collecting zone, and the sludge reflux unit is communicated with an external decay tank 7;
the mud-water separation area is positioned between the inclined tube sedimentation area and the sludge reflux area;
the pipe chute sedimentation zone is composed of a pipe chute bracket 34 and a plurality of pipe chute arranged on the pipe chute bracket, the pipe chute is mutually parallel in space, a series of shallow sedimentation layers composed of a plurality of layers of pipe chute which are horizontally or obliquely arranged are formed, when wastewater in the mud-water separation zone enters the pipe chute sedimentation zone, the mud-water which moves mutually in each sedimentation shallow layer is influenced by the pipe chute in each shallow sedimentation layer, and moves mutually and separates to finish sedimentation, and honeycomb filler is arranged in gaps between adjacent pipe chute to finish further solid-liquid separation in the water feeding process.
The clear water output unit comprises a water collecting area 50 and corresponding pipelines, and the output end of the pipeline is communicated with the advanced purification treatment device of the next stage;
the wastewater pretreatment system also comprises a corresponding power supply unit, the installed capacity of the power supply unit is about 0.5-10KW, the power supply unit is 380/220v low-voltage equipment, the single-machine capacity is 0.2-0.5KW at maximum, and the electric equipment is three-level load. And the power supply unit establishes a low-voltage distribution box according to the electricity load condition of the engineering, and the low-voltage power supply is led in by a low-voltage bus of an owner transformer substation and connected to the low-voltage distribution box to be responsible for the power supply of all electric equipment of the engineering. In order to improve the work rate factor, the engineering is realized by adopting a low-voltage electrostatic capacitor and a reactive compensation mode, and the power factor on the low-voltage bus reaches more than 0.95 after compensation. The low-voltage power distribution is mainly characterized in that when chain power supply is adopted individually, three electric equipment is generally connected in series, and the low-voltage switch cabinet in the low-voltage power distribution box transmits power to each electric equipment, the corresponding electric equipment has anti-corrosion and dust-proof properties, when the corresponding cable is laid, the power supply outside line adopts a crosslinked polyethylene insulated power cable (YJV type), the control cable adopts a polyvinyl chloride insulated polyvinyl chloride sheath control cable (KVV type), and the power cable and the control cable are copper cores;
further, the cable laying mode mainly adopts a cable penetrating protection steel pipe, and the outdoor line penetrating protection steel pipe is directly buried and laid to all electric equipment. The YJV type power cable for the power cable in the house is characterized in that the KVA type control cable is adopted as the control cable, the cable laying mode mainly adopts the mode of laying along a cable bridge, and then the protection steel pipe is penetrated to each electric equipment.
The protection level of the field instrument is not lower than IP 6-5, and the protection level of the field instrument is not lower than IP 68 for sensors and the like installed on underground pipelines; in addition, measures such as an outer frame protection box and the like are adopted for the transmitter according to the requirements.
The process flow for preprocessing the nuclear medical radioactive wastewater by using the preprocessing system comprises the following steps:
the nuclear medical radioactive wastewater directly flows into a solid-liquid primary separation unit of a pretreatment system, is separated by the primary separation unit, enters a homogenizing unit, is added with a compounded coagulant and a coagulant aid under stirring condition to carry out coagulation treatment, flows into an inclined tube type solid-liquid secondary separation unit after coagulation, is subjected to solid-liquid separation in an inclined tube sedimentation tank of the solid-liquid secondary separation unit, and enters a clear water output pool to be further homogenized, and then enters a deep purification device to be treated by a wastewater lifting pump to be further treated and discharged after reaching standards; and the slurry formed by solid-liquid separation is collected for a period of time, the slurry storage height is monitored by an on-line monitoring module, after the slurry storage height reaches the design value of equipment, the slurry is automatically pumped back to a decay tank by an automatic sludge pumping unit for further storage decay treatment, and after the solid radioactive waste decays to the allowable discharge concentration, the solid radioactive waste is discharged to a septic tank of a hospital sewage treatment station and is discharged after reaching the standard through biochemical treatment.
Chemical flocculants (also called coagulants) in the present invention are chemical aids having a coagulation effect including, but not limited to, polyaluminium chloride (PAC), potassium aluminum sulfate, sodium sulfate, ferric chloride; while chemical coagulant aids (also called coagulant aids) are chemical aids with a coacervation effect including, but not limited to, polyacrylamide (PAM), activated silica, clay, polyelectrolyte;
the coagulation effect of the coagulant and the coagulant aid compounded by the invention in the use process is verified by the following embodiment cases 1-3:
example 1
5g of flocculant aluminum-containing flocculant was added to the beaker and dissolved with deionized water to prepare a one percent mass fraction of flocculated solution. 0.5g of nonionic coagulant aid is added into a beaker and dissolved by deionized water, so as to prepare a coagulant aid solution with mass fraction of one thousandth. After preparing flocculation solution and coagulation-aiding solution, taking 1000ml of nuclear medical wastewater in a beaker, adding 1.5ml of flocculation solution and 1.0ml of coagulation-aiding solution, rapidly stirring for 1.5min, and standing for 20min immediately, wherein more flocculent precipitates appear in the wastewater; after 2h of standing, the precipitate was settled to the bottom of the beaker, and the upper solution was clear. The Chemical Oxygen Demand (COD) removal rate was 71.15% and the suspended matter (SS) removal rate was 92.4%.
Example 2
5g of flocculant containing aluminum iron flocculant was added to the beaker and dissolved with deionized water to prepare a one percent by mass flocculation solution. 0.5g of anionic coagulant aid is added into a beaker and dissolved by deionized water, so as to prepare a coagulant aid solution with mass fraction of one thousandth. After preparing flocculation solution and coagulation-aiding solution, taking 1000ml of nuclear medical wastewater in a beaker, adding 1.5ml of flocculation solution and 1.0ml of coagulation-aiding solution, rapidly stirring for 1.5min, and standing for 20min immediately, wherein more flocculent precipitates appear in the wastewater; after 2h of standing, the precipitate was settled to the bottom of the beaker, and the upper solution was clear. The COD removal rate was 74.62% and the SS removal rate was 96.20%.
Example 3
5g of flocculant containing aluminum iron flocculant was added to the beaker and dissolved with deionized water to prepare a one percent by mass flocculation solution. 0.5g of nonionic coagulant aid is added into a beaker and dissolved by deionized water, so as to prepare a coagulant aid solution with mass fraction of one thousandth. After preparing flocculation solution and coagulation-aiding solution, taking 1000ml of nuclear medical wastewater in a beaker, adding 1.5ml of flocculation solution and 1.0ml of coagulation-aiding solution, rapidly stirring for 1.5min, and standing for 20min immediately, wherein more flocculent precipitates appear in the wastewater; after 2h of standing, the precipitate was settled to the bottom of the beaker, and the upper solution was clear. The COD removal rate was 77.31% and the SS removal rate was 94.94%.
In the three cases, 2.5ml of flocculant and 1.0ml of coagulant aid are respectively added into 1000ml of wastewater for precipitation treatment (precipitation time is 20 min), the pretreatment effects are shown in table 1, and the mixing of the coagulant aid and the compound coagulant of the invention in the use process can be knownThe coagulation effect meets the use requirement, wherein, 1 in the table 1 # Is an aluminum-containing flocculant; 2 # Is an aluminum-containing ferric flocculant; a is nonionic coagulant aid; b is an anionic coagulant aid.
TABLE 1
As can be seen from the above table, 2 using an aluminum-containing iron flocculant # After being compounded with the anionic coagulant aid B, the SS removal rate and the solid yield are improved compared with the prior art.
Further, the nuclear medicine raw wastewater collected by the invention is subjected to solid-liquid primary separation unit, primary and secondary flocculation and then subjected to solid-liquid secondary separation, radioactive solid waste after secondary separation is pumped into an original decay tank of a hospital and then subjected to natural decay, upper liquid (namely wastewater) enters an inclined tube sedimentation tank of the solid-liquid secondary separation unit, a small amount of solid particles separated by the inclined tube sedimentation tank enter a sludge collecting area at the bottom, and supernatant liquid is pumped out from a sedimentation area above the inclined tube sedimentation tank to reach a clear water output unit for transfer and then is subjected to a deep purification unit of the next step.
In summary, since the nuclear medical wastewater is mainly in a solid and liquid mixture state and has extremely complex components, the pretreatment system is arranged in the invention to carry out necessary pretreatment on the nuclear medical wastewater before the advanced treatment, specifically, the homogenization unit at the front end is used for realizing the solid-liquid separation of most of the nuclear medical wastewater, the separated supernatant is further treated for the second time through the solid-liquid separation unit, so that the content of particles in the output clear water is smaller, and the clear water output unit is communicated with the advanced treatment unit at the rear end, thereby effectively improving the efficiency of the advanced treatment at the rear end, prolonging the service life of the material treated at the rear end, increasing the circulation times of equipment in use, reducing the equipment cost and reducing the irradiation risk when the material is replaced.
Furthermore, the invention directly applies the existing decay pool of the hospital, divides the functions into three, one plays a temporary storage role, the other plays a solid-liquid primary separation role, the other is to store the solid returned by the sludge reflux unit independently to complete the natural decay role, the division of the functionality enables the decay pool to reduce more than 90 percent compared with the prior art, namely, a large amount of liquid is subjected to the next stage of treatment through the solid-liquid primary separation, a small amount of solid returns to the decay pool to complete the burden reduction of the decay pool, the pretreatment unit can carry out continuous operation, meanwhile, the functional division also realizes the effective utilization of the existing equipment, and the upgrading cost of the treatment system is controllable due to the small improvement on the existing treatment equipment, so that the upgrading and rectifying period of the treatment system is short;
meanwhile, the pretreatment process of the invention realizes the automatic treatment of the whole flow, and is safer and more efficient.
The above is merely illustrative of a preferred embodiment, but is not limited thereto. In practicing the present invention, appropriate substitutions and/or modifications may be made according to the needs of the user.
The number of equipment and the scale of processing described herein are intended to simplify the description of the present invention. Applications, modifications and variations of the present invention will be readily apparent to those skilled in the art.
Although embodiments of the invention have been disclosed above, they are not limited to the use listed in the specification and embodiments. It can be applied to various fields suitable for the present invention. Additional modifications will readily occur to those skilled in the art. Therefore, the invention is not to be limited to the specific details and illustrations shown and described herein, without departing from the general concepts defined in the claims and their equivalents.
Claims (8)
1. A nuclear medicine radioactive wastewater pretreatment system, comprising:
a solid-liquid primary separation unit in the original decay tank;
a homogenizing unit communicated with the solid-liquid primary separation unit;
a solid-liquid secondary separation unit communicated with the wastewater output end of the homogenizing unit;
a clear water output unit communicated with the clear water output end of the solid-liquid secondary separation unit;
a monitoring module which is matched with the solid-liquid secondary separation unit to monitor the slurry storage height in the solid-liquid secondary separation unit;
the control module is in communication connection with the monitoring module;
the sludge reflux unit is connected with the control module;
wherein the homogenization unit is configured to include:
at least two flocculation reaction tanks which are communicated with each other;
and the stirring assembly and the dosing module are matched with each flocculation and coagulation-assisting reaction tank.
2. The nuclear medicine radioactive wastewater pretreatment system according to claim 1, wherein the solid-liquid primary separation unit is a filter screen which is arranged in an original decay tank and has a closed periphery;
wherein, the filter screen is internally provided with a water pump for conveying the stock solution for solid-liquid separation to the homogenizing unit.
3. The nuclear medicine radioactive wastewater pretreatment system of claim 1, wherein the solid-liquid secondary separation unit is configured to adopt at least one stage of sedimentation tank provided with inclined pipes in a sedimentation zone, and the sedimentation tank comprises a mud-water separation zone, an inclined pipe sedimentation zone, a clear water zone and a sludge reflux zone in terms of space division by functions;
the inclined tube sedimentation zone is formed by constructing a plurality of parallel inclined tubes and branch tubes in space so as to divide the inclined tube sedimentation zone into a series of shallow sedimentation layers in a horizontal flow type or vertical flow type.
4. The nuclear medicine radioactive wastewater pretreatment system of claim 1, wherein the sludge reflux unit is started when the monitoring module performs positive feedback, and pumps the sludge separated by the solid-liquid secondary separation unit back to the original decay tank.
5. The nuclear medicine radioactive wastewater pretreatment system of claim 1, wherein the monitoring module is configured to include:
and the sensor is arranged in the solid-liquid secondary separation unit to monitor the height of slurry formed by solid-liquid separation.
6. A method of using the nuclear medicine radioactive wastewater pretreatment system according to any one of claims 1 to 5, comprising:
step one, after nuclear medical radioactive wastewater flows into a primary decay tank, a pretreatment raw liquid is separated by a solid-liquid primary separation unit, the raw liquid is pumped into a homogenizing unit by a controllable pump, and radioactive solid waste is retained in the primary decay tank to realize solid-liquid primary separation;
step two, after the treatment fluid enters a homogenizing unit, adding a compound coagulant and a coagulant aid through a dosing module under the stirring condition to carry out coagulation treatment;
after the wastewater subjected to coagulation treatment flows through a solid-liquid secondary separation unit, solid-liquid separation treatment is carried out through an inclined tube sedimentation zone in the wastewater to obtain corresponding supernatant and slurry;
step three, enabling the supernatant to enter a clear water output unit through a wastewater lifting module I and a filtering module for further homogenization, and then pumping the supernatant into a deep purification unit through a wastewater lifting module II for further treatment so as to enable the supernatant to meet the standard of standard emission;
the on-line monitoring module monitors the slurry storage height in the solid-liquid separation unit in real time so as to pump the separated radioactive solid waste back to the decay tank through the sludge reflux unit pump after the slurry storage height reaches a preset value and carry out storage decay treatment on the radioactive solid waste, and the radioactive solid waste is discharged to a conventional sewage treatment system in a hospital after the radioactive solid waste decays to an allowable discharge concentration.
7. The method of using the pretreatment system for nuclear medicine radioactive wastewater of claim 6, wherein the coagulant aid comprises, but is not limited to, polyacrylamide, activated silica, clay, polyelectrolyte; the coagulant includes, but is not limited to, polyaluminum chloride, potassium aluminum sulfate, sodium sulfate, ferric chloride.
8. The method for applying the nuclear medicine radioactive wastewater solid-liquid separation pretreatment system according to claim 6, wherein particles in the wastewater are interfered by structures of shallow precipitation layers, and move and separate from each other in each shallow precipitation layer;
the mutual movement direction is divided into three types of different flow, same flow and lateral flow.
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