Simulation control system for circulating cooling water of nuclear power station
By designing a nuclear power plant circulating cooling water simulation control system, the cooling system failure problem caused by marine biological blockage is solved, and the automatic operation of the multi-circulation cooling system is realized, ensuring the stability and efficiency of the nuclear power plant cooling system.
Patent Information
- Application Number
- CN202421168315.2
- Authority / Receiving Office
- CN · China
- Patent Type
- Utility models(China)
- Current Assignee / Owner
- Filing Date
- 2024-05-27
- Publication Date
- 2025-01-10
- Estimated Expiration
- 2034-05-27
AI Technical Summary
Problems such as marine organisms blocking water intake pipes or filters have caused the nuclear power plant circulation cooling water system to fail to operate normally, and automatic circulation cooling cannot be achieved when simulating the sea cooling.
A simulation control system for circulating cooling water in nuclear power plants was designed. Through the combination of cooling equipment, circulating water pumps, steam turbines, condensers, steam generators, reactor pressure vessels and other components, a multi-circulation cooling system is formed to ensure the circulating flow of cooling water. , to avoid system failure.
It realizes automatic cyclic cooling when marine organisms are blocked or simulated sea cooling cannot be used, ensuring the stable operation and cooling effect of the cooling system of the nuclear power plant.
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Figure CN222337489U_ABST
Abstract
Description
Technical Field
[0001] The utility model relates to the technical field of nuclear power plant cooling water circulation, in particular to a nuclear power plant circulating cooling water simulation control system. Background Art
[0002] Circulating cooling water in a nuclear power plant refers to an important technology used to ensure the stable operation of a nuclear reactor during the operation of the nuclear power plant. Circulating cooling is the most critical part of a nuclear power plant. It is responsible for transferring heat from the nuclear reactor and transferring it to the secondary side through a heat exchanger, thereby generating steam to drive the turbine to generate electricity. The cooling water source of a nuclear power plant's circulating cooling system is usually natural water bodies, such as rivers, lakes, and seas. In addition, possible pollutants in the circulating cooling water include organic matter, impurities, microorganisms, etc. In order to ensure the stability and safety of the operation of the nuclear power plant, appropriate measures must be taken to effectively prevent and treat pollutants.
[0003] The circulating cooling water systems on the market now mainly use the sea for single cooling. After the seawater exchanges heat through the heat exchanger, the heat is brought into the sea. Its cooling efficiency is relatively high. However, because the ocean is easily affected by environmental changes, there have been many problems such as marine organisms blocking water intake pipes or filters. This simulation system will simulate the equipment for automatic circulation of circulating cooling water when sea cooling cannot be used to run the workflow.
[0004] In view of the above problems, a circulating cooling water simulation control system for a nuclear power plant is proposed. Utility Model Content
[0005] The purpose of the utility model is to provide a circulating cooling water simulation control system for a nuclear power plant, which solves the problem in the background technology that because the ocean is easily affected by environmental changes, marine organisms have repeatedly blocked water intake pipes or filters, and the simulation system simulates the problem of automatic circulation of circulating cooling water when sea cooling cannot be used, and runs the work flow.
[0006] To achieve the above-mentioned purpose, the utility model provides the following technical solutions: a nuclear power plant circulating cooling water simulation control system, including cooling equipment, the cooling equipment is provided with an upper water pipe, a circulating water pump is provided on the upper water pipe, the other end of the circulating water pump is fixedly connected to the circulating water pipe, the upper water pipe passes through the first steam turbine and the second steam turbine is fixedly connected to the third steam turbine, the bottom of the third steam turbine is provided with, and the other end passes through and is fixedly connected to the cooling equipment, the first steam turbine is provided with a condensing pipe, the outer diameter of the condensing pipe is provided with a steam-water separator, the other end of the condensing pipe passes through and is fixedly connected A condenser is fixedly connected to the condenser, a steam pipe is arranged on the condenser, the other end of the steam pipe penetrates and is fixedly connected to the steam generator, a guide tube is penetrated and fixedly connected to the left side of the steam generator, the other end of the guide tube penetrates and is fixedly connected to the reactor pressure vessel, a return water pipe is arranged on the reactor pressure vessel, and the return water pipe penetrates and is fixedly connected to the steam generator, a main pump is arranged on the return water pipe, a feed water pipe is arranged on the steam generator, the other end of the feed water pipe is fixedly connected to a condensate water pipe, and the condensate water pipe penetrates and is fixedly connected to the third steam turbine, the second steam turbine and the first steam turbine;
[0007] As a further description of the above technical solution: a supply pipe is provided on the catheter, and a pressure stabilizer is provided on the supply pipe;
[0008] As a further description of the above technical solution: control rods are arranged inside the reactor pressure vessel;
[0009] As a further description of the above technical solution: the outer diameter of the water supply pipe is provided with a high-pressure heater, and the lower part of the high-pressure heater is provided with a main water supply pump;
[0010] As a further description of the above technical solution: a low-pressure heater is provided on the condensate pipe, and a condensate pump is provided on the condensate pipe;
[0011] As a further description of the above technical solution: a spray port is provided inside the cooling device;
[0012] As a further description of the above technical solution: a valve is provided on the right side of the cooling device;
[0013] As a further description of the above technical solution: a cooling water pipe is provided at the bottom of the third steam turbine, and a cooling device is passed through and fixedly connected to the other end of the cooling water pipe;
[0014] Compared with the prior art, the beneficial effects of the utility model are as follows:
[0015] 1. The utility model provides a nuclear power plant circulating cooling water simulation control system, which connects the inlet end of the cooling device with the outlet end of the circulating water pump, and connects it with the inlet end of the main feed water pump through the outlet end of the steam generator; the inlet end of the condenser is connected with the outlet end of the condensate pump, and the inlet end of the reactor is connected with the outlet end of the main pump. Compared with the single cooling water system in the prior art, there is an empty cooling device for circulation, which can make the circulating water cooling system circulate normally, avoid failure of the cooling system and ensure the cooling effect of the system. BRIEF DESCRIPTION OF THE DRAWINGS
[0016] Figure 1 It is a three-dimensional structural schematic diagram of the utility model;
[0017] Figure 2 It is a schematic diagram of the workflow of the utility model;
[0018] Figure 3 This is a schematic diagram of the cooling system structure of the utility model.
[0019] In the figure: 1. Cooling equipment; 2. Water supply pipe; 3. Circulating water pump; 4. First steam turbine; 5. Second steam turbine; 6. Third steam turbine; 7. Circulating water pipe; 8. Condensate pipe; 9. Condensate pump; 10. Low-pressure heater; 11. Main feed water pump; 12. High-pressure heater; 13. Steam generator; 14. Conduit; 15. Supply pipe; 16. Stabilizer; 17. Reactor pressure vessel; 18. Control rod; 19. Return pipe; 20. Main pump; 21. Steam pipe; 22. Condenser; 23. Condensate pipe; 24. Steam-water separator; 25. Supply pipe; 26. Spray port; 27. Valve; 28. Cooling water pipe. DETAILED DESCRIPTION
[0020] The following will be combined with the drawings in the embodiments of the utility model to clearly and completely describe the technical solutions in the embodiments of the utility model. Obviously, the described embodiments are only part of the embodiments of the utility model, not all of the embodiments. Based on the embodiments in the utility model, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the utility model.
[0021] In order to further understand the content of the utility model, the utility model is described in detail in conjunction with the accompanying drawings.
[0022] Combination Figure 1, including a cooling device 1, the cooling device 1 is provided with an upper water pipe 2, the upper water pipe 2 is provided with a circulating water pump 3, the other end of the circulating water pump 3 is fixedly connected to a circulating water pipe 7, the upper water pipe 2 passes through the first steam turbine 4, the second steam turbine 5 and the third steam turbine 6 are all fixedly connected, a cooling water pipe 28 is provided at the bottom of the third steam turbine 6, and the other end of the cooling water pipe 28 passes through and is fixedly connected to the cooling device 1, the first steam turbine 4 is provided with a condensing pipe 23, the outer diameter of the condensing pipe 23 is provided with a steam-water separator 24, and at the same time, steam is heated inside the steam generator 13 to generate steam, which is transported to the condenser 22 through the steam pipe 21, and then transported from the condenser 22 to the condensing pipe 23, and separated by the steam-water separator 24, the other end of the condensing pipe 23 passes through and is fixedly connected to the condenser 22, the condenser 22 is provided with a steam pipe 21, and the other end of the steam pipe 21 passes through and is fixedly connected to the steam generator The reactor 13 is provided with a control rod 18, when the reactor pressure vessel 17 starts to work, the control rod 18 is lifted upward to start the reaction, the main pump 20 drives the cooling water in the return pipe 19 to form a circulation through the reactor pressure vessel 17 and the steam generator 13, the left side of the steam generator 13 is penetrated and fixedly connected with a guide tube 14, the other end of the guide tube 14 is penetrated and fixedly connected with the reactor pressure vessel 17, the reactor pressure vessel 17 is provided with a return pipe 19, and the return pipe 19 is penetrated and fixedly connected with the steam generator 13, the main pump 20 is provided on the return pipe 19, the steam generator 13 is provided with a make-up water pipe 25, the other end of the make-up water pipe 25 is fixedly connected with a condensate water pipe 8, and the condensate water pipe 8 is penetrated and fixedly connected with the third steam turbine 6, the second steam turbine 5 and the first steam turbine 4, the steam enters the first steam turbine 4, the second steam turbine 5 and the third steam turbine 6 to generate a motor and is transported to the generator.
[0023] Combination Figure 2 A feed pipe 15 is provided on the conduit 14, and a pressurizer 16 is provided on the feed pipe 15. A control rod 18 is provided inside the reactor pressure vessel 17. A high-pressure heater 12 is provided on the outer diameter of the feed pipe 25, and a main feed water pump 11 is provided at the lower part of the high-pressure heater 12. A low-pressure heater 10 is provided on the condensate pipe 8, and a condensate pump 9 is provided on the condensate pipe 8. A spray port 26 is provided inside the cooling device 1, and a valve 27 is provided on the right side of the cooling device 1. The cooling water is transported to the inside of the steam turbine for uninterrupted cooling through the circulating water pump 3 on the cooling device 1, and at the same time enters the low-pressure heater 10 through the condensate pump 9, enters the high-pressure heater 12 through the main feed water pump 11, and finally enters the steam generator 13 for circulating cooling. The hot water then returns to the inside of the cooling device 1 through the cooling water pipe 28 and dissipates heat through the spray port 26.
[0024] Working principle: when the reactor pressure vessel 17 starts to work, the control rod 18 is lifted up to start the reaction. The main pump 20 drives the cooling water in the return pipe 19 to form a circulation through the reactor pressure vessel 17 and the steam generator 13. At the same time, it is heated inside the steam generator 13 to generate steam, which is transported to the condenser 22 through the steam pipe 21, and then transported from the condenser 22 to the condensation pipe 23. At the same time, it is separated by the steam-water separator 24, and the steam enters the first steam turbine 4, the second steam turbine 5 and the third steam turbine 6 to generate electricity and is transported to the generator. At the same time, the circulating water pump 3 on the cooling device 1 transports the cooling water to the turbine for uninterrupted cooling, and at the same time enters the low-pressure heater 10 through the condensate pump 9, enters the high-pressure heater 12 through the main feed water pump 11, and finally enters the steam generator 13 for circulating cooling. The hot water then returns to the cooling device 1 through the cooling water pipe 28 and dissipates heat through the spray port 26.
[0025] It should be noted that, in this article, relational terms such as first and second, etc. are only used to distinguish one entity or operation from another entity or operation, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Moreover, the terms "include", "comprises" or any other variations thereof are intended to cover non-exclusive inclusion, so that a process, method, article or device including a series of elements includes not only those elements, but also other elements not explicitly listed, or also includes elements inherent to such process, method, article or device.
[0026] Although embodiments of the present invention have been shown and described, it will be appreciated by those skilled in the art that various changes, modifications, substitutions and variations may be made to the embodiments without departing from the principles and spirit of the present invention, and that the scope of the present invention is defined by the appended claims and their equivalents.
Claims
1. A nuclear power plant circulating cooling water simulation control system, comprising a cooling device (1), characterized in that: The cooling device (1) is provided with an upper water pipe (2), a circulating water pump (3) is provided on the upper water pipe (2), the other end of the circulating water pump (3) is fixedly connected to a circulating water pipe (7), the upper water pipe (2) passes through the first steam turbine (4) and the second steam turbine (5) and the third steam turbine (6) are all fixedly connected, the first steam turbine (4) is provided with a condensing pipe (23), the outer diameter of the condensing pipe (23) is provided with a steam-water separator (24), the other end of the condensing pipe (23) passes through and is fixedly connected to a condenser (22), the condenser (22) is provided with a steam pipe (21), the other end of the steam pipe (21) passes through and is fixedly connected to a steam generator (1 3), a conduit (14) is passed through and fixedly connected to the left side of the steam generator (13), the other end of the conduit (14) is passed through and fixedly connected to the reactor pressure vessel (17), a return pipe (19) is provided on the reactor pressure vessel (17), and the return pipe (19) passes through and is fixedly connected to the steam generator (13), a main pump (20) is provided on the return pipe (19), a make-up water pipe (25) is provided on the steam generator (13), the other end of the make-up water pipe (25) is fixedly connected to a condensate pipe (8), and the condensate pipe (8) passes through and is fixedly connected to the third steam turbine (6), the second steam turbine (5) and the first steam turbine (4).
2. A nuclear power plant circulating cooling water simulation control system according to claim 1, characterized in that: The conduit (14) is provided with a supply pipe (15), and the supply pipe (15) is provided with a pressure stabilizer (16).
3. A nuclear power plant circulating cooling water simulation control system according to claim 1, characterized in that: A control rod (18) is arranged inside the reactor pressure vessel (17).
4. A nuclear power plant circulating cooling water simulation control system according to claim 1, characterized in that: The outer diameter of the water supply pipe (25) is provided with a high-pressure heater (12), and the lower part of the high-pressure heater (12) is provided with a main water supply pump (11).
5. A nuclear power plant circulating cooling water simulation control system according to claim 1, characterized in that: The condensate water pipe (8) is provided with a low-pressure heater (10), and the condensate water pipe (8) is provided with a condensate water pump (9).
6. A nuclear power plant circulating cooling water simulation control system according to claim 1, characterized in that: A spray port (26) is provided inside the cooling device (1).
7. A nuclear power plant circulating cooling water simulation control system according to claim 6, characterized in that: A valve (27) is provided on the right side of the cooling device (1).
8. A nuclear power plant circulating cooling water simulation control system according to claim 7, characterized in that: A cooling water pipe (28) is provided at the bottom of the third steam turbine (6), and the other end of the cooling water pipe (28) passes through and is fixedly connected to a cooling device (1).