CN110349689B - Radioactive waste liquid treatment device for nuclear power station - Google Patents
Radioactive waste liquid treatment device for nuclear power station Download PDFInfo
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- CN110349689B CN110349689B CN201810290181.4A CN201810290181A CN110349689B CN 110349689 B CN110349689 B CN 110349689B CN 201810290181 A CN201810290181 A CN 201810290181A CN 110349689 B CN110349689 B CN 110349689B
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- 239000007788 liquid Substances 0.000 title claims abstract description 192
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 47
- 238000001223 reverse osmosis Methods 0.000 claims abstract description 199
- 238000005342 ion exchange Methods 0.000 claims abstract description 94
- 238000011033 desalting Methods 0.000 claims abstract description 74
- 238000000034 method Methods 0.000 claims abstract description 68
- 239000002699 waste material Substances 0.000 claims abstract description 40
- 239000002894 chemical waste Substances 0.000 claims abstract description 27
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 63
- 239000012528 membrane Substances 0.000 claims description 48
- 150000002500 ions Chemical class 0.000 claims description 30
- 239000012141 concentrate Substances 0.000 claims description 18
- 229910052792 caesium Inorganic materials 0.000 claims description 17
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 claims description 17
- 229910052712 strontium Inorganic materials 0.000 claims description 16
- CIOAGBVUUVVLOB-UHFFFAOYSA-N strontium atom Chemical compound [Sr] CIOAGBVUUVVLOB-UHFFFAOYSA-N 0.000 claims description 16
- 239000012190 activator Substances 0.000 claims description 12
- 239000000084 colloidal system Substances 0.000 claims description 8
- 238000009296 electrodeionization Methods 0.000 claims description 7
- 238000000926 separation method Methods 0.000 claims description 7
- 238000010612 desalination reaction Methods 0.000 claims description 2
- 238000000746 purification Methods 0.000 abstract description 18
- 238000011002 quantification Methods 0.000 abstract description 3
- 230000002285 radioactive effect Effects 0.000 description 34
- 239000003456 ion exchange resin Substances 0.000 description 28
- 229920003303 ion-exchange polymer Polymers 0.000 description 28
- 239000002354 radioactive wastewater Substances 0.000 description 21
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 20
- 238000001179 sorption measurement Methods 0.000 description 18
- 208000028659 discharge Diseases 0.000 description 15
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 14
- 238000005202 decontamination Methods 0.000 description 13
- 230000003588 decontaminative effect Effects 0.000 description 13
- 238000011084 recovery Methods 0.000 description 12
- PWYYWQHXAPXYMF-UHFFFAOYSA-N strontium(2+) Chemical compound [Sr+2] PWYYWQHXAPXYMF-UHFFFAOYSA-N 0.000 description 12
- 239000003463 adsorbent Substances 0.000 description 8
- 239000012535 impurity Substances 0.000 description 8
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- 238000005265 energy consumption Methods 0.000 description 2
- 238000001095 inductively coupled plasma mass spectrometry Methods 0.000 description 2
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- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 1
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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
-
- 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
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
- Water Treatment By Electricity Or Magnetism (AREA)
Abstract
The embodiment of the invention provides a radioactive waste liquid treatment device for a nuclear power station. The device comprises a first continuous electric desalting device, a reverse osmosis unit and a first ion exchange unit; a concentrated solution outlet of the first continuous electric desalting equipment is connected with an inlet of the reverse osmosis unit, and a concentrated solution outlet of the reverse osmosis unit is connected with an inlet of the first ion exchange unit; separating the process waste liquid by the first continuous electric desalting equipment to obtain a first purified liquid and a first concentrated liquid; separating the chemical waste liquid and the first concentrated solution through the reverse osmosis unit to obtain a second purified liquid and a second concentrated solution; and carrying out ion exchange treatment on the second concentrated solution through the first ion exchange unit to obtain a third purified solution. The radioactive waste liquid treatment device for the nuclear power station, provided by the embodiment of the invention, has a higher radioactive waste liquid purification level, can obviously reduce the generation amount of radioactive waste, and realizes the small quantification of the radioactive waste.
Description
Technical Field
The invention relates to the technical field of nuclear power station radioactive waste liquid treatment, in particular to a nuclear power station radioactive waste liquid treatment device.
Background
At present, the process waste liquid generated by the nuclear power station has less salt species and low salt content, and is mainly purified by an ion exchange process; for chemical waste liquid generated by a nuclear power station, the salt content is complex and the salt content is high, and the chemical waste liquid is mainly purified by an evaporation process. However, the problem of this approach is: the purification treatment capacity is insufficient, the radioactivity level of the effluent is high, and the effluent can not meet the requirements of the discharge standard; the radioactive concentrated solution is generated, the subsequent treatment is carried out by a solidification process, the volume package capacity of radioactive waste liquid in a solidified body is only about 20 percent, a large amount of secondary radioactive solid waste is generated, and the treatment process is complex.
Disclosure of Invention
The embodiment of the invention provides a radioactive waste liquid treatment device for a nuclear power station, which has higher radioactive waste liquid purification level, can obviously reduce the generation amount of radioactive waste and realize small quantification of the radioactive waste.
The embodiment of the invention provides a radioactive waste liquid treatment device for a nuclear power station, which comprises a first continuous electric desalting device, a reverse osmosis unit and a first ion exchange unit; a concentrated solution outlet of the first continuous electric desalting equipment is connected with an inlet of the reverse osmosis unit, and a concentrated solution outlet of the reverse osmosis unit is connected with an inlet of the first ion exchange unit; separating the process waste liquid by the first continuous electric desalting equipment to obtain a first purified liquid and a first concentrated liquid; separating the chemical waste liquid and the first concentrated solution through a reverse osmosis unit to obtain a second purified liquid and a second concentrated solution; and carrying out ion exchange treatment on the second concentrated solution through the first ion exchange unit to obtain third purified solution.
According to the device for treating the radioactive waste liquid in the nuclear power station, provided by the embodiment of the invention, the process waste liquid is purified through the first continuous electric desalting, the obtained first purified liquid meets the requirement even superior to the emission standard, most of radioactive nuclides in the process waste liquid are retained in the first concentrated liquid, the first concentrated liquid and the chemical waste liquid are used as inlet water of a reverse osmosis unit and enter the reverse osmosis unit for separation treatment, the obtained second purified liquid meets the requirement even superior to the emission standard, most of radioactive nuclides are retained in the second concentrated liquid, the second concentrated liquid has higher concentration of the radioactive nuclides, and the second concentrated liquid is subjected to ion exchange treatment, so that the utilization efficiency of the ion exchange resin can be obviously improved, and the generation amount of the radioactive waste ion exchange resin is obviously reduced. The whole device does not produce radioactive concentrated solution, saves the solidification process and further reduces the production of radioactive wastes.
According to one aspect of an embodiment of the invention, the purified liquid outlet of the first ion exchange unit is connected to the inlet of the reverse osmosis unit; wherein all or part of the third purified liquid is returned to be used as a part of the water inlet of the reverse osmosis unit.
According to one aspect of an embodiment of the invention, the apparatus further comprises a second continuous electrodeionization device; wherein, the purified liquid outlet of the reverse osmosis unit is connected with the purified liquid inlet of the second continuous electric desalting equipment, and the concentrated liquid outlet of the second continuous electric desalting equipment is connected with the inlet of the reverse osmosis unit.
According to one aspect of an embodiment of the invention, the purified liquid outlet of the second continuous electrodeionization device is connected to the inlet of the first continuous electrodeionization device.
According to one aspect of an embodiment of the invention, the apparatus further comprises an intermediate water tank and an activator tank, the intermediate water tank being connected to the activator tank; wherein, the purified liquid outlet of the second continuous electric desalting equipment is connected with the inlet of the first continuous electric desalting equipment through the middle water tank.
According to one aspect of an embodiment of the invention, the reverse osmosis unit comprises one or two stages of reverse osmosis membrane equipment.
According to an aspect of an embodiment of the present invention, the reverse osmosis apparatus employs one reverse osmosis membrane module or more than two reverse osmosis membrane modules connected in series, and when more than two reverse osmosis membrane modules are employed, the concentrate outlet of the previous reverse osmosis membrane module is connected to the inlet of the next reverse osmosis membrane module.
According to one aspect of an embodiment of the invention, the reverse osmosis unit comprises a primary reverse osmosis device, the concentrate outlet of the reverse osmosis device is divided into two branches by a pipeline, one branch is connected with the inlet of the reverse osmosis device, and the other branch is connected with the inlet of the first ion exchange unit.
According to one aspect of an embodiment of the invention, the reverse osmosis unit comprises two stages of reverse osmosis units, wherein the purified liquid outlet of the first stage of reverse osmosis unit is connected to the inlet of the second stage of reverse osmosis unit, the concentrated liquid outlet of the second stage of reverse osmosis unit is connected to the inlet of the first stage of reverse osmosis unit, and the concentrated liquid outlet of the first stage of reverse osmosis unit is connected to the inlet of the first ion exchange unit.
According to one aspect of an embodiment of the invention, the concentrate outlet of the first stage reverse osmosis unit is divided into two branches by a pipeline, one branch being connected to the inlet of the first stage reverse osmosis unit and the other branch being connected to the inlet of the first ion exchange unit.
According to an aspect of the embodiment of the present invention, the first ion exchange unit includes one or more stages of ion exchangers.
According to one aspect of the embodiment of the invention, the device further comprises a second ion exchange unit, wherein the purified liquid outlet of the second ion exchange unit is connected with the inlet of the first continuous electric desalting device; wherein, the process waste liquid is firstly subjected to ion exchange treatment through the second ion exchange unit and then is subjected to separation treatment through the first continuous electric desalting equipment.
According to an aspect of the embodiment of the present invention, the second ion exchange unit includes one or more stages of ion exchangers.
According to an aspect of the embodiments of the present invention, the apparatus further comprises: the first pretreatment unit is connected with an inlet of the first continuous electric desalting equipment and is used for pretreating the process waste liquid to remove more than one of oil, colloid, particulate matters, strontium and cesium in the process waste liquid; and/or the second pretreatment unit is connected with the inlet of the reverse osmosis unit and is used for pretreating the chemical waste liquid so as to remove more than one of oil, colloid, particulate matters, strontium and cesium in the chemical waste liquid.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings required to be used in the embodiments of the present invention will be briefly described below, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
Fig. 1 shows a process flow diagram of a nuclear power plant radioactive waste liquid treatment device according to an embodiment of the present invention.
Fig. 2 shows a process flow diagram of a nuclear power plant radioactive waste liquid treatment device according to another embodiment of the present invention.
Fig. 3 shows a process flow diagram of a nuclear power plant radioactive liquid waste treatment device according to another embodiment of the present invention.
Fig. 4 shows a process flow diagram of a nuclear power plant radioactive waste liquid treatment device according to another embodiment of the present invention.
Description of reference numerals:
1, a first pretreatment unit; 11, an activated carbon filter; 12, an inorganic adsorption column;
2, a second ion exchange unit; 21, a buffer water tank; 22, an ion exchanger;
31, a first continuous electric desalination apparatus;
41, producing a water tank;
5, a second pretreatment unit; 51, an oil-water separator; 52, a cartridge filter; 53, a paper core filter; 54, a self-cleaning filter; 55, an ultrafilter; 56, a buffer water tank;
6, a reverse osmosis unit; 61, a buffer water tank; 62, a cartridge filter; 63, a high pressure pump; 64, a first stage reverse osmosis unit; 65, a second stage reverse osmosis device; 66, a circulation pump; 67, reverse osmosis equipment;
7, a first ion exchange unit, 71, an ion exchanger;
81, a second continuous electrodeionization device;
93, an intermediate water tank; 94, an activator tank; 95, a dosing pump.
Detailed Description
Features and exemplary embodiments of various aspects of the present invention will be described in detail below, and in order to make objects, technical solutions and advantages of the present invention more apparent, the present invention will be further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not to be construed as limiting the invention. It will be apparent to one skilled in the art that the present invention may be practiced without some of these specific details. The following description of the embodiments is merely intended to provide a better understanding of the present invention by illustrating examples of the present invention.
It is noted that, herein, relational terms such as first and second, and the like may be used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Also, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising … …" does not exclude the presence of other identical elements in a process, method, article, or apparatus that comprises the element.
The mass concentration of radioactive nuclide ions in the radioactive wastewater of the nuclear power station is extremely low, and the concentration of the radioactive nuclide ions is further reduced to reach the radioactivity of 10Bq/L required by environmental emission, so that very high requirements are provided for the treatment capacity of the radioactive wastewater treatment technology. An important principle in radioactive wastewater treatment is the requirement for small amounts of radioactive waste. In addition, the operability and maintainability of the apparatus under radioactive conditions also needs to be considered.
Based on the above special requirements of radioactive waste water treatment of the nuclear power station, the embodiment of the invention provides a radioactive waste liquid treatment device for the nuclear power station, which has the advantages of obviously improving the purification level of radioactive waste liquid, obviously reducing the generation amount of radioactive waste and realizing the small quantification of the radioactive waste. The present invention will be described in detail below with reference to fig. 1 to 4.
Herein, the "concentration factor" is calculated as (volume of feed water)/(volume of concentrated solution); the "water recovery" is calculated as (purified liquid yield)/(water intake).
Fig. 1 is a process flow diagram of a radioactive liquid waste treatment apparatus according to an embodiment of the present invention, and according to fig. 1, the radioactive liquid waste treatment apparatus according to the embodiment of the present invention includes a first continuous electric desalting device 31, a reverse osmosis unit 6, and a first ion exchange unit 7; wherein the concentrated solution outlet of the first continuous electric desalting device 31 is connected with the inlet of the reverse osmosis unit 6, and the concentrated solution outlet of the reverse osmosis unit 6 is connected with the inlet of the first ion exchange unit 7.
The nuclear power station radioactive waste liquid treatment device provided by the embodiment of the invention performs continuous electric desalting treatment on the process waste liquid through the first continuous electric desalting equipment 31 to obtain a first purified liquid and a first concentrated liquid, wherein the first purified liquid meets or even exceeds the requirement of a discharge standard and is subjected to discharge treatment, most of radioactive nuclides in the process waste liquid are retained in the first concentrated liquid, then the first concentrated liquid and the chemical waste liquid are taken as inlet water of the reverse osmosis unit 6 to enter the reverse osmosis unit 6 for separation treatment to obtain a second purified liquid and a second concentrated liquid, wherein the second purified liquid meets or even exceeds the requirement of the discharge standard, the concentration multiple of the reverse osmosis unit 6 is more than 2 times, preferably 2-3 times, most of radioactive nuclides are retained in the second concentrated liquid, and the mass concentration of radioactive nuclides in the second concentrated liquid can reach or more than 2 times of the mass concentration of the radioactive nuclides in the inlet water of the reverse osmosis unit 6, because the second concentrated solution has higher radionuclide concentration, the second concentrated solution is subjected to ion exchange treatment by the first ion exchange unit 7, and the equilibrium adsorption capacity of the ion exchange resin is obviously improved, so that the utilization efficiency of the ion exchange resin is obviously improved, and the generation amount of radioactive waste ion exchange resin is obviously reduced. Because the whole device does not produce radioactive concentrated solution in the process, the solidification process is saved, and the production amount of radioactive waste is further reduced.
And (3) performing ion exchange treatment on the second concentrated solution to obtain a third purified solution, and performing discharge treatment when the radioactivity of the third purified solution meets the requirement of a discharge standard. And (3) detecting that the third purified liquid is mixed with the first purified liquid and/or the second purified liquid and then meets the requirement of the discharge standard, mixing the third purified liquid with the first purified liquid and/or the second purified liquid and then discharging.
According to some embodiments of the present invention, one or two stages of reverse osmosis devices are used in the reverse osmosis unit 6, but the present invention is not limited thereto, and three, four or more stages of reverse osmosis devices may be used as the case may be.
In some embodiments, referring to fig. 3, the reverse osmosis unit 6 is a primary reverse osmosis device, the liquid supply port of the chemical waste liquid and the concentrate outlet of the first continuous electric desalting device 31 are respectively connected to the inlet of the reverse osmosis device 67, and the concentrate outlet of the reverse osmosis device 67 is connected to the inlet of the first ion exchange unit 7. The purified liquid sent from the reverse osmosis device 67 is already lower than 10Bq/L, meets the requirement of the discharge standard, and can be discharged for treatment.
In order to increase the reverse osmosis recovery rate, the reverse osmosis unit 6 is provided with a circulation of the concentrate. Specifically, referring to fig. 3, the concentrated solution outlet of the reverse osmosis device 67 is divided into two branches by a pipeline, one branch is connected to the inlet of the reverse osmosis device 67, the other branch is connected to the inlet of the first ion exchange unit 7, so that a part of the concentrated solution returns to the reverse osmosis device 67 for circulation treatment, and the other part of the concentrated solution enters the first ion exchange unit 7 for ion exchange treatment, so as to obtain a third purified solution. Through set up the concentrate circulation at reverse osmosis unit 6, can also improve the concentration multiple, reduce the discharge amount of concentrate to reduce first ion exchange unit 7's load, further improve ion exchange resin's utilization ratio, and avoided the energy waste, practiced thrift the energy consumption.
Further, the reverse osmosis device 67 may employ one reverse osmosis membrane module, or two or more reverse osmosis membrane modules may be connected in series to further improve the reverse osmosis recovery rate. When more than two reverse osmosis membrane modules are adopted, the concentrated solution outlet of the previous reverse osmosis membrane module is connected with the inlet of the next reverse osmosis membrane module, namely, the concentrated solution generated by the previous reverse osmosis membrane module is used as the inlet water of the next reverse osmosis membrane module, and the purified solutions sent by all the reverse osmosis membrane modules are converged into the purified solution of the reverse osmosis equipment 67.
In some embodiments, referring to fig. 4, the reverse osmosis unit 6 employs two stages of reverse osmosis units, wherein the first stage 64 and the second stage 65 are connected in series in two stages. Specifically, a liquid supply interface of the chemical waste liquid and a concentrated liquid outlet of the first continuous electric desalting device 31 are respectively connected with an inlet of the first-stage reverse osmosis device 64, a purified liquid outlet of the first-stage reverse osmosis device 64 is connected with an inlet of the second-stage reverse osmosis device 65, a concentrated liquid outlet of the second-stage reverse osmosis device 65 is connected with an inlet of the first-stage reverse osmosis device 64, and a concentrated liquid outlet of the first-stage reverse osmosis device 64 is connected with an inlet of the first ion exchange unit 7. The purified liquid from the second stage reverse osmosis device 65 is already below 10Bq/L and meets the requirements of discharge standards, and can be discharged for disposal.
Similarly, in order to increase the reverse osmosis recovery rate, the reverse osmosis unit 6 is provided with a circulation of the concentrate. Specifically, referring to fig. 4, the concentrated solution outlet of the first stage reverse osmosis device 64 is divided into two branches by a pipeline, one branch is connected to the inlet of the first stage reverse osmosis device 64, and the other branch is connected to the inlet of the first ion exchange unit 7, so that part of the concentrated solution returns to the first stage reverse osmosis device 64 for circulation treatment, and the other part of the concentrated solution enters the first ion exchange unit 7 for ion exchange treatment, so as to obtain a third purified solution. Through set up the concentrate circulation at reverse osmosis unit 6, can also improve the concentration multiple, reduce the discharge amount of concentrate to reduce first ion exchange unit 7's load, further improve ion exchange resin's utilization ratio, and avoided the energy waste, practiced thrift the energy consumption.
Similarly, the first stage reverse osmosis unit 64 may employ one reverse osmosis membrane module or may employ more than two reverse osmosis membrane modules in series to further increase the reverse osmosis recovery rate. When more than two reverse osmosis membrane modules are adopted, the concentrated solution outlet of the previous reverse osmosis membrane module is connected with the inlet of the next reverse osmosis membrane module, that is, the concentrated solution generated by the previous reverse osmosis membrane module is used as the inlet water of the next reverse osmosis membrane module, and the purified solutions sent by all the reverse osmosis membrane modules are merged into the purified solution of the first-stage reverse osmosis equipment 64.
The second stage reverse osmosis device 65 may employ one reverse osmosis membrane module, or may employ more than two reverse osmosis membrane modules connected in series, to further improve the reverse osmosis recovery rate. When more than two reverse osmosis membrane modules are adopted, the concentrated solution outlet of the previous reverse osmosis membrane module is connected with the inlet of the next reverse osmosis membrane module, that is, the concentrated solution generated by the previous reverse osmosis membrane module is used as the inlet water of the next reverse osmosis membrane module, and the purified solutions sent by all the reverse osmosis membrane modules are combined into the purified solution of the second-stage reverse osmosis equipment 65.
As an alternative, the first stage reverse osmosis device 64 and the second stage reverse osmosis device 65 are connected in series by three sections of reverse osmosis membrane modules to form a two-stage three-section reverse osmosis unit for separating and treating radioactive wastewater, so that the purification capacity and the concentration multiple are high, the load of the ion exchange unit 300 is reduced, and the reverse osmosis recovery rate is improved.
According to some embodiments of the present invention, the first ion exchange unit 7 may employ one-stage ion exchanger, or may employ more than two-stage ion exchangers.
As shown in fig. 3 and 4, the first ion exchange unit 7 adopts a first-stage ion exchanger 71, and the second concentrated solution sent out by the reverse osmosis unit 6 enters the ion exchanger 71 to be subjected to ion exchange treatment, so as to obtain a third purified solution, and the third purified solution is subjected to discharge treatment as described above.
When the first ion exchange unit 7 employs more than two stages of ion exchangers, the more than two stages of ion exchangers may be connected in series, and the second concentrated solution sent out by the reverse osmosis unit 6 is subjected to deep purification treatment by sequentially passing through the more than two stages of ion exchangers to obtain a third purified solution, and then the third purified solution is subjected to discharge treatment as described above.
The third purified liquid can be totally or partially returned to be used as a part of the water inlet of the reverse osmosis unit 6, so that the concentration of the radioactive nuclide in the water inlet of the reverse osmosis unit 6 can be reduced, and the decontamination effect of the complete device on the radioactive nuclide is further improved. At this time, referring to fig. 2, the purified liquid outlet of the first ion exchange unit 7 is connected to the inlet of the reverse osmosis unit 6 so that the third purified liquid can be returned to the reverse osmosis unit 6 as a part of the intake water for circulation treatment. As an example, as shown in fig. 3, the purified liquid outlet of the ion exchanger 71 is connected to the inlet of the reverse osmosis apparatus 67; as also shown in fig. 4, the purified liquid outlet of the ion exchanger 71 is connected to the inlet of the first stage reverse osmosis unit 64. Through to the third scavenging solution through reverse osmosis unit 6 circulation processing, improved the decontamination effect of device to the radionuclide.
When the radioactivity of the second purified liquid produced by the reverse osmosis unit 6 is more than 10Bq/L, or when the discharged purified liquid is required to have a lower radioactivity, the second purified liquid may be further sent to the second continuous electric desalting apparatus 81 for further fine treatment. With continued reference to FIG. 2, the purified liquid outlet of the reverse osmosis unit 6 is connected to the inlet of a second continuous electrodeionization device 81. At this time, the concentrate outlet of the second continuous electric desalting device 81 can be connected with the inlet of the reverse osmosis unit 6. The second purified liquid produced by the reverse osmosis unit 6 enters the second continuous electric desalting device 81 for further separation treatment to obtain a fourth purified liquid and a third concentrated liquid, and the third concentrated liquid is further returned to be used as a part of the water inlet of the reverse osmosis unit 6 for circulation treatment.
As an example, when the reverse osmosis unit 6 employs a one-stage reverse osmosis apparatus, as shown in fig. 3, the purified liquid outlet of the reverse osmosis apparatus 67 is connected to the purified liquid inlet of the second continuous electric desalting apparatus 81, and the concentrated liquid outlet of the second continuous electric desalting apparatus 81 is connected to the inlet of the reverse osmosis apparatus 67; when the reverse osmosis unit 6 employs a two-stage reverse osmosis unit, it is also possible that the purified liquid outlet of the second stage reverse osmosis unit 65 is connected to the purified liquid inlet of the second continuous electric desalting device 81 and the concentrated liquid outlet of the second continuous electric desalting device 81 is connected to the inlet of the first stage reverse osmosis device 64, as shown in fig. 4.
The second purified liquid is further purified through the continuous electric desalting treatment of the second continuous electric desalting device 81, the obtained fourth purified liquid meets the requirements of emission standards through detection, even reaches a natural background level, and the fourth purified liquid and other purified liquids can be respectively discharged or mixed to be discharged according to actual conditions and requirements. The second continuous electric desalting device 81 continuously carries out electric desalting treatment on the second purified liquid to obtain a third concentrated liquid, and the third concentrated liquid returns to the reverse osmosis unit 6 for circular treatment, so that concentrated waste liquid is not generated, and the recovery rate of the device to water can be improved.
If the radioactivity of the fourth purified liquid produced by the second continuous electric desalting device 81 is still greater than 10Bq/L, or if the discharged purified liquid can reach lower radioactivity, as shown in FIGS. 2 to 4, the purified liquid outlet of the second continuous electric desalting device 81 is connected with the inlet of the first continuous electric desalting device 31 to form a two-stage continuous electric desalting device series arrangement. And sending the fourth purified liquid into the first continuous electric desalting equipment 31 for deep purification treatment to obtain the first purified liquid, wherein the first purified liquid meets the requirements of the emission standard, even reaches the natural background level, and the first purified liquid meets the strictest emission requirements.
The treatment of the process waste liquid and the chemical waste liquid share two-stage continuous electric desalting equipment, so that the process device is simplified, and the occupied area and the cost of the device are reduced while the purification level of the radioactive waste liquid is improved and the small amount of the radioactive waste is realized.
In order to improve the purification level of the continuous electric desalting process, as shown in fig. 3 and 4, the apparatus may further include an intermediate water tank 93 and an activator tank 94, the intermediate water tank 93 being connected to the activator tank 94; wherein the purified liquid outlet of the second continuous electric desalting device 81 is connected to the inlet of the first continuous electric desalting device 31 through an intermediate water tank 93. The activator tank 94 contains an activator, which may be prepared from pure water having a resistivity of greater than 0.5M Ω & cm and various inorganic salts, and contains ionic Ca2+、Na+、Sr2+、Zn2+、Mg2+、Fe2+And K+The anion species are not limited, the concentration of the original solution of the activator is related to the adding dosage, and the ion concentration contained in the radioactive wastewater is ensured to be as follows after the activator is added into the radioactive wastewater and uniformly mixed: ca2+0.1mg/L～0.2mg/L、Na+0.2mg/L～0.3mg/L、Sr2+8mg/L～9mg/L、Zn2+18mg/L～20mg/L、Mg2+0.2mg/L～0.25mg/L、Fe2+0.04 mg/L-0.05 mg/L and K+100mg/L to 150 mg/L. The adding amount of the activating agent is controlled by the dosing pump 95, the activating agent is added into the fourth purified liquid output by the second continuous electric desalting equipment 81, then the fourth purified liquid is sent to the first continuous electric desalting equipment 31 for deep purification treatment, and the obtained first purified liquid meets the requirements of the emission standard and even reaches the natural background level.
Generally, the process waste liquid contains substantially no or very low content of non-radioactive salts other than boric acid, and therefore, the process waste liquid may be subjected to an ion exchange treatment and then to a deep purification treatment by the first continuous electric desalting apparatus 31. Thus, the radioactive waste liquid treatment apparatus for a nuclear power plant may further include a second ion exchange unit 2, wherein, referring to fig. 2, a liquid supply port of the process waste liquid is connected to an inlet of the first continuous electric desalting device 31 through the second ion exchange unit 2.
According to some embodiments of the present invention, the second ion exchange unit 2 may employ one-stage ion exchanger, or may employ more than two-stage ion exchangers.
As shown in fig. 3 and 4, the second ion exchange unit 2 adopts a primary ion exchanger, a liquid supply interface of the process waste liquid is connected with an inlet of the ion exchanger 22, and an outlet of the ion exchanger 22 is connected with the first continuous electric desalting device 31.
When the second ion exchange unit 2 employs more than two stages of ion exchangers, the more than two stages of ion exchangers may be connected in series, and the process waste liquid passes through the more than two stages of ion exchangers in sequence to perform more than two stages of ion exchange treatment.
Most of radioactive nuclides in the process waste liquid are removed through ion exchange treatment of the second ion exchange unit 2, and then the process waste liquid enters the first continuous electric desalting equipment 31 to be subjected to continuous electric desalting treatment, so that the load of the first continuous electric desalting equipment 31 is reduced, the deep purification level of the first continuous electric desalting equipment 31 is improved, and the obtained first purified liquid meets the strictest discharge requirement.
When the radioactive waste liquid treatment device of the nuclear power station adopts the second ion exchange unit 2, the radionuclide purification efficiency of the process waste liquid depends on the ion exchange treatment of the second ion exchange unit 2, the radionuclide purification efficiency of the chemical waste liquid mainly depends on the reverse osmosis unit 6 or the purification treatment of the reverse osmosis unit 6 and the continuous electric desalting equipment, and the first ion exchange unit 7 mainly plays a role in desalting, so that new ion exchange resin can be used for the second ion exchange unit 2 to purify the process waste liquid, and when the radionuclide starts to penetrate through the ion exchange bed, the ion exchange resin is further used for the first ion exchange unit 7 to further reduce the generation amount of the radioactive waste ion exchange resin and further reduce the radioactive waste.
Before the process waste liquid is treated to remove radionuclides, the process waste liquid may be pretreated, as shown in fig. 2, a first pretreatment unit 1 may be disposed between a liquid supply interface of the process waste liquid and the first continuous electric desalting device 31, and one or more of oil, colloid, particulate matter, strontium, and cesium in the process waste liquid is removed by the first pretreatment unit 1, which is not a necessary process. If necessary, the first pretreatment unit 1 can be one or a combination of several of an oil-water separator, an activated carbon filter, an inorganic membrane filter, a cartridge filter, a paper core filter, a self-cleaning filter, an ultrafilter and an inorganic adsorption column. If the nuclear power plant radioactive liquid waste treatment apparatus employs the second ion exchange unit 2, the first pretreatment unit 1 should be disposed before the second ion exchange unit 2.
Before the radionuclide removal treatment is performed on the chemical waste liquid, the chemical waste liquid may be pretreated, as shown in fig. 2, a second pretreatment unit 5 is disposed between a liquid supply port of the chemical waste liquid and the reverse osmosis unit 6, and one or more of oil, colloid, particulate matter, strontium, and cesium in the chemical waste liquid are removed by the second pretreatment unit 5, which is not a necessary process. If necessary, the second pretreatment unit 5 can be one or a combination of several of an oil-water separator, an activated carbon filter, an inorganic membrane filter, a cartridge filter, a paper core filter, a self-cleaning filter, an ultrafilter and an inorganic adsorption column.
Considering that strontium and cesium (especially cesium) in radioactive waste water most easily penetrate through an ion exchange bed, the radioactive nuclide which easily penetrates through the ion exchange bed is specifically adsorbed by utilizing the selectivity characteristic of inorganic adsorption, so that the service cycle of the ion exchange resin is prolonged, and the generation amount of the radioactive waste ion exchange resin is further reduced. Based on the above consideration, any one of the radioactivity of strontium, the radioactivity of cesium, and the total radioactivity of strontium and cesium in the process waste liquid is 105Bq/L, preferably carrying out pretreatment for removing strontium and/or cesium on the process waste liquid; and the chemical waste liquid contains 10 of the radioactivity of strontium, the radioactivity of cesium, and the total radioactivity of strontium and cesium5When Bq/L is not less than this, it is preferable to preliminarily remove strontium and/or cesium from the chemical waste liquidAnd (6) processing. As shown in fig. 3 and 4, the process waste liquid and the chemical waste liquid are pretreated by removing strontium and/or cesium by using an inorganic adsorption column 12, and the inorganic adsorption column 12 may be an inorganic adsorption column for strontium, an inorganic adsorption column for cesium, or an inorganic adsorption column for strontium and cesium.
The process waste liquid can also contain radioactive substances in a colloidal state and a granular state, which can affect inorganic adsorbents, reverse osmosis membranes, ion exchange resins and the like, and the pretreatment can remove the substances, prolong the service life of the inorganic adsorbents, the reverse osmosis membranes and the ion exchange resins, reduce the replacement of the inorganic adsorbents and the ion exchange resins, and further reduce the generation amount of radioactive waste ion exchange resins and the generation amount of radioactive waste inorganic adsorbents. Because the activated carbon has a good adsorption capacity for colloids, particles and the like due to its unique surface properties, as shown in fig. 3 and 4, the first pretreatment unit 1 can remove radioactive substances in a colloidal state and a particle state by using the activated carbon filter 11, thereby simplifying pretreatment process equipment and procedures. It is understood that the removal of the radioactive substances in the colloidal state and the particulate state is not limited to the active carbon filtration process, and may be a fine filtration process such as microfiltration, ultrafiltration, nanofiltration, or a combination process of two or more of active carbon filtration, microfiltration, ultrafiltration, nanofiltration, or the like.
In addition to radionuclides and inorganic salts, the chemical waste liquid may contain impurities such as oils, organic matters, colloids, and particles, which are mostly non-radioactive, but affect inorganic adsorbents, reverse osmosis membranes, ion exchange resins, and the like, and in order to prolong the service life of the inorganic adsorbents, reverse osmosis membranes, and ion exchange resins, reduce the replacement of the inorganic adsorbents and ion exchange resins, and further reduce the generation amount of radioactive waste ion exchange resins and the generation amount of radioactive waste inorganic adsorbents, it is necessary to remove these impurities by pretreatment. The second pretreatment unit 5 may also adopt one or a combination of two or more of filtration processes of activated carbon filtration, microfiltration, ultrafiltration, nanofiltration and the like.
As an example, referring to fig. 3 and 4, the second pretreatment unit 5 may employ a water separator 51, an inorganic adsorption column 12, a paper core filter 53, a self-cleaning filter 54, and an ultrafilter 55, which are connected in sequence. The oil-water separator 51 is used for removing oil impurities in the radioactive wastewater and reducing the influence of the oil impurities on the subsequent process; the inorganic adsorption column 12 is used for removing radioactive nuclides which easily penetrate through the ion exchange bed, prolonging the service cycle of the ion exchange resin and reducing the generation amount of radioactive waste ion exchange resin; a cartridge filter 52 is optionally arranged between the oil-water separator 51 and the inorganic adsorption column 12 to remove particles, protect the inorganic adsorption column 12 and prevent the particles from blocking the adsorption column; the paper core filter 53 is used for removing the particulate matters in the radioactive wastewater, and the filter core containing the particulate matters is convenient for subsequent treatment and disposal; the self-cleaning filter 54 directly intercepts impurities in the radioactive wastewater by using a filter screen, so that suspended matters and particulate matters are further removed, the self-cleaning filter 54 can automatically discharge sewage, the intellectualization is improved, and the process is more efficient; the ultrafilter 55 can deeply remove impurities, proteins, microorganisms and macromolecular organic substances existing in a colloidal form in radioactive wastewater. By adopting the device, impurities in the radioactive wastewater can be deeply removed, so that the water quality meets the water inlet requirement of the subsequent process, the influence of the impurities on the reverse osmosis treatment process and the ion exchange process is greatly reduced, and the operation period of the reverse osmosis unit 6 and the first ion exchange unit 7 is prolonged. A buffer water tank 56 may be connected between the inorganic adsorption column 12 and the paper core filter 53 to buffer the radioactive wastewater after the inorganic adsorption treatment.
The pH value of the inlet water of the reverse osmosis unit 6 can be adjusted to 6-8 in advance, so that the treatment effect of the reverse osmosis process is better, and the reverse osmosis membrane has a longer service life.
The reverse osmosis unit 6 may further comprise a buffer tank 61 to buffer the radioactive wastewater from the second pretreatment unit 5. A cartridge filter 62 may be further connected between the buffer water tank 61 and the reverse osmosis apparatus for protecting the reverse osmosis apparatus of the subsequent process.
The second ion exchange unit 2 may further comprise a buffer tank 21 to buffer the radioactive waste water from the first pretreatment unit 1.
The nuclear power plant radioactive liquid waste treatment apparatus further includes a suitable water supply pump 10, a circulation pump 66 and a high pressure pump 63, which may be various pumps commonly used in the art, such as a plunger pump, a centrifugal pump, etc.; a monitoring drain tank 41 may be further included to monitor the drain for post-drain.
By adopting the radioactive waste water treatment device provided by the embodiment of the invention, higher radioactive waste liquid purification level can be realized, the generation amount of radioactive waste can be obviously reduced, and the small amount of the radioactive waste is realized.
The invention is illustrated below by means of examples, which however do not constitute a limitation of the invention.
Cs in the following examples+、Sr2+、Co2+The concentration of (A) is measured by adopting an American thermoelectric Sammer Fei ICAP Q type inductively coupled plasma-mass spectrometry ICP-MS instrument.
The "decontamination factor" is calculated as (radioactivity of the feed water)/(radioactivity of the purified liquid).
Example 1
The radioactive waste water treatment apparatus for a nuclear power plant used in this embodiment is different from the radioactive waste water treatment apparatus for a nuclear power plant shown in fig. 3 in that the first pretreatment unit 1, the second pretreatment unit 5, and the cartridge filter 62 are not provided, the intermediate water tank 93, the activator tank 94, and the chemical feed pump 95 are not provided, and other components are the same as those of the radioactive waste water treatment apparatus for a nuclear power plant shown in fig. 3. The reverse osmosis equipment 67 adopts three reverse osmosis membranes connected in series, and each reverse osmosis membrane component is provided with a reverse osmosis membrane element Dow BW 30-4040. The equipment, elements and materials adopted by the device are shown in the following table:
| name (R) | Parameter(s) |
| Water supply pump 10 | 1m3/h～4m3/h |
| High- |
Glan centrifugal pump, pressure 2MPa |
| Reverse osmosis membrane element | Dow BW30-4040 |
| Ion exchange bed | Nuclear-grade mixed bed resin IRN160 and ion exchange bed volume of 60L |
| First continuous |
Throughput 1.1m3/h |
| Second continuous |
Throughput 1.2m3/h |
The process waste liquid treated by the embodiment is simulated radioactive process waste liquid containing Cs+1501μg/L，Co2+776μg/L，Sr2+985 mu g/L; the chemical waste liquid is simulated radioactive chemical waste liquid containing Cs+2018μg/L，Co2+895μg/L，Sr2+1238μg/L。
The design treatment capacity of the process waste liquid of the device is 1m3The designed treatment capacity of the chemical waste liquid is 1m3/h。
The radioactive waste water treatment device of the nuclear power station used in the embodiment does not cancel the ion exchanger 22 of the original process waste liquid of the nuclear power station, and only arranges the first continuous electric desalting equipment 31 at the downstream of the device to deeply purify the produced water of the ion exchange purification liquid. In this example, the process effluent is first ion-exchanged for decontamination by an ion-exchange bed that carries out the treatment of three species of nuclides Cs+、Sr2+、Co2+The decontamination factors of the water-saving sewage treatment system are respectively 80, 100 and 110, and Cs in the produced water of the ion exchange bed+、Sr2+、Co2+Respectively has the concentration of 18.7 mu g/L, 7.8 mu g/L and 8.1 mu g/L, the water produced by the ion exchange bed is continuously and deeply purified by the first continuous electric desalting device 31, the water recovery rate of the first continuous electric desalting device 31 is 90 percent, and the obtained Cs in the first purified liquid+、Sr2+、Co2+The concentrations of (A) were 1.2. mu.g/L, 0.7. mu.g/L and 0.8. mu.g/L, respectively.
The first concentrated solution obtained by the first continuous electric desalting apparatus 31 is merged with the chemical waste liquid to be used as the inlet water of the reverse osmosis apparatus 67, and the inlet water amount is 1.1m3H, Cs in the influent+、Sr2+、Co2+The concentrations of (A) were 2004. mu.g/L, 884. mu.g/L and 1199. mu.g/L, respectively, and separation treatment was performed by reverse osmosis. In order to utilize the ion exchange bed to the maximum extent, improve the utilization efficiency of the ion exchange resin and reduce the yield of the waste radioactive ion exchange resin, the reverse osmosis unit should not be set to have too high or too low water recovery rate, and the reverse osmosis unit 6 preferably has a water recovery rate of 60% -80%. This example designed the reverse osmosis unit 67 to recover 60% of water and deliver 3m3The second concentrated solution returns to the reverse osmosis equipment 67 for circular treatment, 0.67m3The second concentrate is passed to an ion exchanger 71, which is ion-exchanged by an ion exchange bed. When the ion exchanger 71 is just put into use, the decontamination factor of the ion exchange bed is high, and the produced water of the ion exchange bed is totally returned to be used as a part of the inlet water of the reverse osmosis equipment 67, so that the concentration of the radioactive nuclide in the inlet water of the reverse osmosis equipment 67 can be reduced, and the decontamination effect of the complete set of equipment on the radioactive nuclide is improved. The water produced by the purified liquid of the reverse osmosis equipment 67 is further purified by the second continuous electric desalting equipment 81, the recovery rate of the water by the second continuous electric desalting equipment 81 is 90 percent, and Cs in the obtained fourth purified liquid+、Sr2+、Co2+The concentration of the total decontamination factor is respectively 0.81 mu g/L, 0.17 mu g/L and 0.21 mu g/L, and the total decontamination factor of the whole device is more than 103。
When the apparatus has been in operation for a certain period of time, the ion exchange bed in the ion exchanger 71 starts to be filledWhen the decontamination factor of the radioactive nuclide by the ion exchange bed is reduced to 1.5, the decontamination effect of the radioactive nuclide by the whole set of device is correspondingly reduced, and Cs is contained in the produced water of the second continuous electric desalting equipment 81+、Sr2+、Co2+The concentration of (2) was 14.7. mu.g/L, 7.6. mu.g/L, and 9.7. mu.g/L. In order to further reduce the concentration of the radionuclide, the water produced by the second continuous electric desalting device 81 is sent to the first continuous electric desalting device 31 for further deep purification treatment, so that the Cs can be treated+、Sr2+、Co2+The concentration of the active components is reduced to 1.1 mug/L, 0.7 mug/L and 0.8 mug/L, and the total decontamination factor of the whole set of device is still more than 103。
In the conventional process, if reverse osmosis is not adopted as a separation means and continuous electric desalting is adopted as a fine treatment means, only ion exchange resin is relied on, and the radionuclide 10 is difficult to achieve3The decontamination effect of (2) and the need to replace the ion exchange resin when the ion exchange bed begins to be penetrated in order to obtain a good water production quality, a large amount of radioactive waste ion exchange resin is produced. By adopting the device, the fixing capacity of the ion exchange resin to the radioactive nuclide can be utilized to the maximum extent, so that the radioactive wastes are reduced by 5-10 times.
While the invention has been described with reference to specific embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (14)
1. A nuclear power station radioactive waste liquid treatment device is characterized by comprising a first continuous electric desalting device, a reverse osmosis unit and a first ion exchange unit;
a concentrated solution outlet of the first continuous electric desalting equipment is connected with an inlet of the reverse osmosis unit, and a concentrated solution outlet of the reverse osmosis unit is connected with an inlet of the first ion exchange unit; the device also comprises a second continuous electric desalting device, wherein a purified liquid outlet of the reverse osmosis unit is connected with an inlet of the second continuous electric desalting device, and a concentrated liquid outlet of the second continuous electric desalting device is connected with an inlet of the reverse osmosis unit;
separating the process waste liquid by the first continuous electric desalting equipment to obtain a first purified liquid and a first concentrated liquid;
separating the chemical waste liquid and the first concentrated solution through the reverse osmosis unit to obtain a second purified liquid and a second concentrated solution, wherein the concentration multiple of the reverse osmosis unit is 2-5 times;
and carrying out ion exchange treatment on the second concentrated solution through the first ion exchange unit to obtain a third purified solution.
2. The apparatus of claim 1 wherein the purified liquid outlet of the first ion exchange unit is connected to the inlet of the reverse osmosis unit;
wherein all or part of the third purified liquid is returned as part of the feed water to the reverse osmosis unit.
3. The apparatus of claim 1, wherein the purified liquid outlet of the second continuous electrodeionization device is connected to the inlet of the first continuous electrodeionization device.
4. The apparatus of claim 3, further comprising an intermediate water tank and an activator tank, the intermediate water tank being connected to the activator tank;
wherein, the purified liquid outlet of the second continuous electric desalting equipment is connected with the inlet of the first continuous electric desalting equipment through the intermediate water tank.
5. The apparatus of claim 1 wherein the reverse osmosis unit comprises one or two stages of reverse osmosis membrane equipment.
6. The apparatus according to claim 5, wherein the reverse osmosis device employs one reverse osmosis membrane module or more than two reverse osmosis membrane modules connected in series, and when more than two reverse osmosis membrane modules are employed, the concentrate outlet of the previous reverse osmosis membrane module is connected to the inlet of the next reverse osmosis membrane module.
7. The apparatus of claim 5 wherein the reverse osmosis unit comprises a primary reverse osmosis unit, the concentrate outlet of the reverse osmosis unit being piped to two branches, one branch being connected to the inlet of the reverse osmosis unit and the other branch being connected to the inlet of the first ion exchange unit.
8. The apparatus of claim 5 wherein the reverse osmosis unit comprises two stages of reverse osmosis units, wherein the purified liquor outlet of a first stage of reverse osmosis unit is connected to the inlet of a second stage of reverse osmosis unit, the concentrate outlet of the second stage of reverse osmosis unit is connected to the inlet of the first stage of reverse osmosis unit, and the concentrate outlet of the first stage of reverse osmosis unit is connected to the inlet of the first ion exchange unit.
9. The apparatus of claim 8 wherein the concentrate outlet of the first stage reverse osmosis unit is piped to two branches, one branch being connected to the inlet of the first stage reverse osmosis unit and the other branch being connected to the inlet of the first ion exchange unit.
10. The apparatus of claim 1, wherein the first ion exchange unit comprises one or more stages of ion exchangers.
11. The apparatus of claim 1, further comprising a second ion exchange unit, wherein the purified liquid outlet of the second ion exchange unit is connected to the inlet of the first continuous electric desalination device;
and the process waste liquid is subjected to ion exchange treatment through the second ion exchange unit and then is subjected to separation treatment through the first continuous electric desalting equipment.
12. The apparatus of claim 11, wherein the second ion exchange unit comprises one or more stages of ion exchangers.
13. The apparatus of claim 1, further comprising:
the first pretreatment unit is connected with an inlet of the first continuous electric desalting equipment and is used for pretreating the process waste liquid so as to remove more than one of oil, colloid, particulate matters, strontium and cesium in the process waste liquid; and/or the presence of a gas in the gas,
and the second pretreatment unit is connected with an inlet of the reverse osmosis unit and is used for pretreating the chemical waste liquid so as to remove more than one of oil, colloid, particulate matters, strontium and cesium in the chemical waste liquid.
14. The device of claim 1, wherein the reverse osmosis unit has a concentration factor of 2-3.
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