CN113436771A - Nuclear power station radioactive waste liquid treatment system - Google Patents
Nuclear power station radioactive waste liquid treatment system Download PDFInfo
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- CN113436771A CN113436771A CN202110688283.3A CN202110688283A CN113436771A CN 113436771 A CN113436771 A CN 113436771A CN 202110688283 A CN202110688283 A CN 202110688283A CN 113436771 A CN113436771 A CN 113436771A
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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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Abstract
The invention discloses a radioactive waste liquid treatment system of a nuclear power station, wherein an outlet at the top of a secondary side of a steam generator is communicated with an inlet of a condenser, an outlet at the bottom of the secondary side of the steam generator is communicated with an inlet of a secondary side of a residual steam liquid collecting tank, an outlet of the secondary side of the residual steam liquid collecting tank is communicated with a compression packing machine, an outlet of the condenser is respectively communicated with an inlet of a waste liquid collecting tank and an inlet of a radioactive waste liquid tank, an outlet of the waste liquid collecting tank is communicated with a primary side inlet of the steam generator through a primary heater, a primary side outlet of the steam generator is communicated with a primary side inlet of a primary heat exchanger, and a primary side outlet of the primary heat exchanger is communicated with an inlet of the condenser; the outlet of the circulating fan is communicated with the inlet of the circulating fan through the secondary heater, the primary side of the residual steam liquid collecting tank and the primary side of the secondary heat exchanger; the system can solve the problems of large steam pressure fluctuation and frequent temperature regulation in the waste liquid evaporation process.
Description
Technical Field
The invention belongs to the technical field of nuclear power, and relates to a radioactive waste liquid treatment system for a nuclear power station.
Background
The nuclear power plant waste liquid treatment system is used for collecting radioactive waste liquid generated by a nuclear power plant during normal operation including expected operation events, treating the radioactive waste liquid to enable the radioactivity level of the radioactive waste liquid to be lower than the allowable value of environmental emission, and then taking part in a system for recycling or discharging the radioactive waste liquid to the environment as a supplementary liquid. The waste liquid treatment system is generally a selected combination of five process units of storage, filtration, chemical precipitation, ion exchange and evaporation. Among them, the evaporation technology has been widely used in various domestic nuclear power stations due to the advantages of high decontamination factor, good volume reduction effect, etc.
In the existing liquid waste treatment process of the nuclear power station, steam sources of evaporators are all supplied by an auxiliary steam system, and the residual steam liquid after waste liquid evaporation treatment adopts the traditional cement solidification process, i.e. waste and cement are mixed, and a hard cement solidified body is formed after hydration reaction, so that the aim of reducing leaching of dangerous components in the waste is fulfilled. The liquid waste of the nuclear power station has certain radioactivity, the radioactive waste liquid needs to be subjected to cyclic evaporation treatment, and as the number of auxiliary steam system steam supply downstream users is large during the operation of the nuclear power station, the problems of large steam pressure fluctuation and frequent temperature adjustment often exist in the waste liquid evaporation process, and the cyclic heating treatment effect needs to be further optimized; meanwhile, the existing cement curing is sensitive to certain pollutants, the curing time can be delayed due to the existence of certain pollutants, and even the final hardening effect is influenced.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a radioactive waste liquid treatment system for a nuclear power station, which can solve the problems of large steam pressure fluctuation and frequent temperature regulation in the waste liquid evaporation process and has low treatment cost.
In order to achieve the purpose, the radioactive waste liquid treatment system of the nuclear power station comprises a steam generator, a condenser, a waste liquid collecting tank, a primary heater, a primary heat exchanger, a circulating fan, a secondary heater, a residual steam liquid collecting tank, a secondary heat exchanger, a cement mixer, a radioactive waste liquid tank and a compression packer;
an outlet at the top of the secondary side of the steam generator is communicated with an inlet of a condenser, an outlet at the bottom of the secondary side of the steam generator is communicated with an inlet of the secondary side of a residual steam liquid collecting tank, an outlet of the secondary side of the residual steam liquid collecting tank is communicated with a compression packing machine, an outlet of the condenser is respectively communicated with an inlet of a waste liquid collecting tank and an inlet of a radioactive waste liquid tank, an outlet of the waste liquid collecting tank is communicated with a primary side inlet of the steam generator through a primary heater, a primary side outlet of the steam generator is communicated with a primary side inlet of a primary heat exchanger, and a primary side outlet of the primary heat exchanger is communicated with an inlet of the condenser;
the outlet of the circulating fan is communicated with the inlet of the circulating fan through the secondary heater, the primary side of the residual steam liquid collecting tank and the primary side of the secondary heat exchanger;
and an outlet of the radioactive waste liquid tank is communicated with a secondary side inlet of the steam generator through a secondary side of the secondary heat exchanger and a secondary side of the primary heat exchanger.
Also comprises a medicine adding tank; the medicine feeding tank is communicated with the secondary side inlet of the steam generator.
An outlet at the top of the secondary side of the steam generator is communicated with an inlet of the condenser through a cyclone separator.
The sampling device is also included, and the sampling port of the condenser is communicated with the inlet of the sampling device.
The outlet of the waste liquid collecting tank is communicated with the primary side inlet of the steam generator through a water feeding pump and a primary heater.
And an outlet of the radioactive waste liquid tank is communicated with a secondary side inlet of the steam generator through a waste liquid delivery pump, a secondary side of the secondary heat exchanger and a secondary side of the primary heat exchanger.
A first valve is arranged between the outlet of the condenser and the inlet of the waste liquid collecting tank.
A second valve is arranged between the outlet of the condenser and the inlet of the radioactive waste liquid tank.
The secondary side outlet of the residual distillation liquid collecting tank is communicated with a compression packer through a cement mixer.
The invention has the following beneficial effects:
when the radioactive waste liquid treatment system for the nuclear power station is specifically operated, waste liquid in the waste liquid collecting tank is heated by the primary heater and then is introduced into the steam generator for heat release, and the waste liquid is preheated by the primary heat exchanger, so that the problems of large steam pressure fluctuation and frequent temperature adjustment in the waste liquid heating process are solved, and the reliability and the safety of the waste liquid treatment system are greatly improved; meanwhile, residual steam liquid discharged by the steam generator is heated and concentrated by hot air, so that the volume reduction treatment in the cement curing process is realized, and the treatment cost is saved; in addition, the invention respectively uses the heated steam and hot air as the heating steam sources of the primary heat exchanger and the secondary heat exchanger so as to realize the recycling of energy.
Drawings
Fig. 1 is a schematic diagram of the present invention.
Wherein, 1 is a dosing tank, 2 is a steam generator, 3 is a cyclone separator, 4 is a condenser, 5 is a sampling device, 6 is a waste liquid collecting tank, 7 is a water feeding pump, 8 is a primary heater, 9 is a primary heat exchanger, 10 is a circulating fan, 11 is a secondary heater, 12 is a raffinate collecting tank, 13 is a secondary heat exchanger, 14 is a cement mixer, 15 is a radioactive waste liquid tank, 16 is a waste liquid delivery pump, and 17 is a compression packer.
Detailed Description
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, not all of the embodiments, and are not intended to limit the scope of the present disclosure. Moreover, in the following description, descriptions of well-known structures and techniques are omitted so as to not unnecessarily obscure the concepts of the present disclosure. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
There is shown in the drawings a schematic block diagram of a disclosed embodiment in accordance with the invention. The figures are not drawn to scale, wherein certain details are exaggerated and possibly omitted for clarity of presentation. The shapes of various regions, layers and their relative sizes and positional relationships shown in the drawings are merely exemplary, and deviations may occur in practice due to manufacturing tolerances or technical limitations, and a person skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions, according to actual needs.
Referring to fig. 1, the nuclear power plant waste liquid treatment system of the present invention includes a chemical feeding tank 1, a steam generator 2, a cyclone separator 3, a condenser 4, a sampling device 5, a waste liquid collecting tank 6, a water feeding pump 7, a primary heater 8, a primary heat exchanger 9, a circulating fan 10, a secondary heater 11, a raffinate collecting tank 12, a secondary heat exchanger 13, a cement mixer 14, a radioactive waste liquid tank 15, a waste liquid delivery pump 16, and a compression packer 17;
the chemical adding tank 1 is communicated with a secondary side inlet of a steam generator 2, an outlet at the top of the secondary side of the steam generator 2 is communicated with an inlet of a cyclone separator 3, an outlet at the bottom of the secondary side of the steam generator 2 is communicated with an inlet of a residual steam liquid collecting tank 12, an outlet of the cyclone separator 3 is communicated with an inlet of a condenser 4, a sampling port of the condenser 4 is communicated with an inlet of a sampling device 5, an outlet of the condenser 4 is respectively communicated with an inlet of a waste liquid collecting tank 6 and an inlet of a radioactive waste liquid tank 15, an outlet of the waste liquid collecting tank 6 is communicated with a primary side inlet of the steam generator 2 through a water feeding pump 7 and a primary heater 8, a primary side outlet of the steam generator 2 is communicated with a primary side inlet of a primary heat exchanger 9, and a primary side outlet of the primary heat exchanger 9 is communicated with an inlet of the condenser 4;
the outlet of the circulation fan 10 is connected to the inlet of the circulation fan 10 via a secondary heater 11, the primary side of a raffinate collecting tank 12 and the primary side of a secondary heat exchanger 13.
The outlet of the radioactive waste liquid tank 15 is communicated with the secondary inlet of the steam generator 2 through a waste liquid delivery pump 16, the secondary side of the secondary heat exchanger 13 and the secondary side of the primary heat exchanger 9.
The specific working process of the invention is as follows:
scheme 1: the radioactive waste liquid tank 15 → the waste liquid transfer pump 16 → the secondary side of the secondary heat exchanger 13 → the secondary side of the primary heat exchanger 9 → the secondary side of the steam generator 2;
And (2) a flow scheme: the waste liquid collection tank 6 → the feed water pump 7 → the primary heater 8 → the primary side of the steam generator 2 → the primary side of the primary heat exchanger 9 → the condenser 4;
And (3) a flow path: the secondary side of the steam generator 2 → the cyclone 3 → the condenser 4 → the waste liquid collection tank 6 or the radioactive waste liquid tank 15;
the flow 3 is the condensation process after the evaporation of the waste liquid, and the process is introduced into a waste liquid collecting tank 6 or a radioactive waste liquid tank 15 according to the water quality test standard after the sampling of the condensate liquid.
And (4) a flow chart: the circulation fan 10 → the secondary heater 11 → the primary side of the distilled liquid collecting tank 12 → the secondary heat exchanger 13 → the circulation fan 10;
and (5) a flow chart: the secondary side of the residue collecting tank 12 → the cement mixer 14 → the compression packer 17;
the flow 4 and the flow 5 are raffinate drying and solidifying processes, heated air is introduced into a raffinate collecting tank 12 and then introduced into a secondary heat exchanger 13 to preheat waste liquid, and the dried raffinate enters a cement mixer 14 to be mixed and stirred with cement and then is sent to a compression packer 17 to be compressed and barreled.
Example one
Taking the fourth generation nuclear power plant of the high temperature gas cooled reactor which is researched and developed at home as an example, the nuclear power plant consists of two reactors, two steam generators 2 and a steam turbine generator unit. The thermal power of the nuclear power station is 500MW, and the installed capacity is 200 MW. The radioactive waste liquid of the nuclear power station is obtained by maintenance equipment and valve decontamination, ground decontamination, maintenance personnel bathing, cleaning and draining of contaminated work clothes and the like. The radioactive waste liquid is heated by a steam generator 2 to generate steam, then passes through a cyclone separator 3 and a condenser 4 to generate condensate, and is tested by a sampling device 5, when the quality of the condensate water still has radioactivity (the radioactive concentration exceeds 500Bq/L), the condensate is introduced into a radioactive waste liquid tank 15 and is conveyed into the steam generator 2 by a waste liquid conveying pump 16 to be heated until the quality of the condensate water is qualified (the radioactive concentration is less than 300Bq/L), the condensate is introduced into a waste liquid collecting tank 6, and then the condensate is conveyed into a primary heater 8 by a water feeding pump 7 to generate heating steam.
The specific working process of this embodiment is as follows:
1) the radioactive waste liquid tank 15 → the waste liquid transfer pump 16 → the secondary side of the secondary heat exchanger 13 → the secondary side of the primary heat exchanger 9 → the secondary side of the steam generator 2;
wherein, when the total amount of the waste liquid in the radioactive waste liquid tank 15 reaches 30m3When the method is used, the waste liquid conveying pump 16 is started to convey the radioactive waste liquid to flow through the secondary heat exchanger 13 and the primary heat exchanger 9 in sequence, then the radioactive waste liquid enters the secondary side of the steam generator 2, and the outlet flow of the waste liquid conveying pump 16 is adjusted to 500L/h. When the evaporator is operated by evaporation, and foam is found in the evaporator, the flow rate of the generated steam is reduced to reduce the foam productionAnd (4) adding a defoaming agent for defoaming when the flow of the raw steam is reduced to 70% of the normal operation flow and foaming is still continuously generated. The defoaming agent is polyoxypropylene glycerol ether, and is added into the secondary side of the steam generator 2 through the chemical adding tank 1.
2) The waste liquid collection tank 6 → the feed water pump 7 → the primary heater 8 → the primary side of the steam generator 2 → the primary side of the primary heat exchanger 9 → the condenser 4;
the flow is a heating steam operation process of the steam generator 2, and 10m is injected into the waste liquid collecting tank 63The desalted water is conveyed to a primary heater 8 by a water feeding pump 7, the raw steam which is heated to 0.5MPa and 100L/h by the primary heater 8 is introduced into a steam generator 2 to heat the waste liquid, the steam waste heat is introduced into a primary heat exchanger 9 to preheat the waste liquid at 30 ℃ to 50 ℃, and the steam-water mixture generated after heat exchange is introduced into a condenser 4 to be recycled.
3) The secondary side of the steam generator 2 → the cyclone 3 → the condenser 4 → the waste liquid collection tank 6 or the radioactive waste liquid tank 15;
the process is a condensation process after the evaporation of the waste liquid, wet steam generated after the waste liquid is heated by a steam generator 2 is cooled and condensed in a condenser 4 after passing through a cyclone separator 3, and when the temperature in the steam generator 2 is higher than 90 ℃, the outflow of condensate from an outlet of a sampling device 5 is confirmed; when the temperature in the steam generator 2 is higher than 150 ℃, the flow rate of the condensed water is 500L/h. And the sampling device 5 carries out condensed water quality test, when the total beta concentration except tritium is monitored to be more than 500Bq/L, the condensed liquid is discharged into the radioactive waste liquid tank 15 to continue evaporation treatment until the radioactive concentration of the sampling test is less than 300Bq/L, and then the condensed liquid is discharged into the waste liquid collecting tank 6.
4) The circulation fan 10 → the secondary heater 11 → the primary side of the distilled liquid collecting tank 12 → the secondary heat exchanger 13 → the circulation fan 10;
the secondary side of the residue collecting tank 12 → the cement mixer 14 → the compression packer 17;
the raffinate that radioactive waste liquid produced after evaporating is collected in raffinate collecting vessel 12, and outside air is carried to secondary heater 11 through circulating fan 10 and is heated to the hot air, and the hot air is introduced in raffinate collecting vessel 12 and is heated raffinate, and the hot air waste heat is introduced in secondary heat exchanger 13 and is used for preheating 20 ℃ waste liquid to 30 ℃, and the raffinate after drying enters cement blendor 14 and carries out cement mixing stirring, then sends to baling press 17 and carries out the compression barreled and handles. The compression baler 17 was set to a pressure of 200kN and compressed and baled the cured cement into a 200L standard trash can.
Claims (9)
1. A nuclear power station radioactive waste liquid treatment system is characterized by comprising a steam generator (2), a condenser (4), a waste liquid collecting tank (6), a primary heater (8), a primary heat exchanger (9), a circulating fan (10), a secondary heater (11), a residual steam liquid collecting tank (12), a secondary heat exchanger (13), a cement mixer (14), a radioactive waste liquid tank (15) and a compression packer (17);
an outlet at the top of the secondary side of the steam generator (2) is communicated with an inlet of a condenser (4), an outlet at the bottom of the secondary side of the steam generator (2) is communicated with a secondary side inlet of a raffinate steaming tank (12), a secondary side outlet of the raffinate steaming tank (12) is communicated with a compression packer (17), an outlet of the condenser (4) is respectively communicated with an inlet of a waste liquid collecting tank (6) and an inlet of a radioactive waste liquid tank (15), an outlet of the waste liquid collecting tank (6) is communicated with a primary side inlet of the steam generator (2) through a primary heater (8), a primary side outlet of the steam generator (2) is communicated with a primary side inlet of a primary heat exchanger (9), and a primary side outlet of the primary heat exchanger (9) is communicated with an inlet of the condenser (4);
the outlet of the circulating fan (10) is communicated with the inlet of the circulating fan (10) through a secondary heater (11), the primary side of a raffinate collecting tank (12) and the primary side of a secondary heat exchanger (13);
the outlet of the radioactive waste liquid tank (15) is communicated with the inlet of the secondary side of the steam generator (2) through the secondary side of the secondary heat exchanger (13) and the secondary side of the primary heat exchanger (9).
2. The nuclear power plant radioactive liquid waste treatment system according to claim 1, further comprising a dosing tank (1); the dosing tank (1) is communicated with the secondary side inlet of the steam generator (2).
3. The nuclear power plant radioactive liquid waste treatment system according to claim 1, wherein an outlet of a secondary side top of the steam generator (2) communicates with an inlet of the condenser (4) through the cyclone (3).
4. The nuclear power plant radioactive liquid waste treatment system according to claim 1, further comprising a sampling device (5), wherein a sampling port of the condenser (4) is communicated with an inlet of the sampling device (5).
5. The nuclear power plant radioactive liquid waste treatment system according to claim 1, wherein an outlet of the liquid waste collection tank (6) is communicated with a primary side inlet of the steam generator (2) through a feed water pump (7) and a primary heater (8).
6. The nuclear power plant radioactive liquid waste treatment system according to claim 1, wherein an outlet of the radioactive liquid waste tank (15) is communicated with a secondary side inlet of the steam generator (2) through a liquid waste delivery pump (16), a secondary side of the secondary heat exchanger (13) and a secondary side of the primary heat exchanger (9).
7. Nuclear power plant radioactive liquid waste treatment system according to claim 1, characterized in that a first valve is provided between the outlet of the condenser (4) and the inlet of the liquid waste collection tank (6).
8. Nuclear power plant radioactive liquid waste treatment system according to claim 7, wherein a second valve is provided between the outlet of the condenser (4) and the inlet of the radioactive liquid waste tank (15).
9. The nuclear power plant radioactive liquid waste treatment system according to claim 1, wherein a secondary side outlet of the raffinate collecting tank (12) is communicated with the compression-packing machine (17) through a cement mixer (14).
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110688283.3A CN113436771B (en) | 2021-06-21 | 2021-06-21 | Nuclear power station radioactive waste liquid treatment system |
| PCT/CN2021/115651 WO2022267223A1 (en) | 2021-06-21 | 2021-08-31 | Radioactive waste liquid treatment system for nuclear power plant |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110688283.3A CN113436771B (en) | 2021-06-21 | 2021-06-21 | Nuclear power station radioactive waste liquid treatment system |
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| CN113436771A true CN113436771A (en) | 2021-09-24 |
| CN113436771B CN113436771B (en) | 2022-05-24 |
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| CN202110688283.3A Active CN113436771B (en) | 2021-06-21 | 2021-06-21 | Nuclear power station radioactive waste liquid treatment system |
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| CN (1) | CN113436771B (en) |
| WO (1) | WO2022267223A1 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115798768A (en) * | 2023-01-04 | 2023-03-14 | 中国原子能科学研究院 | Radioactive waste liquid treatment method and system |
| CN115810435A (en) * | 2023-01-04 | 2023-03-17 | 中国原子能科学研究院 | Radioactive waste liquid treatment method and system |
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Also Published As
| Publication number | Publication date |
|---|---|
| WO2022267223A1 (en) | 2022-12-29 |
| CN113436771B (en) | 2022-05-24 |
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