Nuclear power station supply system

Abstract

The invention belongs to the technical field of nuclear power generation, and discloses a nuclear power station supply system which comprises a steam generator, a steam turbine, a power generator and an electrolytic hydrogen device, the steam generator is communicated with the steam turbine through a main pipeline and drives the power generator to generate power, and generated power is supplied to a power grid and / or the electrolytic hydrogen device. A main pipeline is connected with a water-water heat exchanger, a first steam-water heat exchanger, a second steam-water heat exchanger and a water-heat simultaneous production device through a main loop, and the water-water heat exchanger heats a fresh water source into high-temperature and high-pressure saturated water; the first steam-water heat exchanger is used for producing high-quality industrial steam; the second steam-water heat exchanger generates steam, the electrolytic hydrogen device is externally connected with a photovoltaic panel and a battery for energy storage, the battery is also connected with the generator, the water-heat simultaneous generation device heats seawater, heat exchange is carried out through a heat exchange loop and a user loop, and the temperature of the loop is kept stable through a heat storage reservoir; the problems that in the prior art, electric energy provided by a nuclear power station is single, and the service field is narrow are solved.

Description

Technical Field

[0001] This invention relates to the field of nuclear power generation technology, and in particular to a nuclear power plant supply system. Background Technology

[0002] Existing nuclear power plants rely solely on electricity as their primary energy source, resulting in a limited power supply and a narrow service area. Furthermore, the current peak and trough periods in electricity consumption create significant pressure for peak regulation. While nuclear power plants can output large quantities of stable, clean, and efficient nuclear electricity, losses can occur. Wind and solar power are increasingly becoming new options, but they are also competing for market share. Moreover, the processes of wind and solar power generation are not stable and cannot complement nuclear power plants. Nuclear power plants generate large amounts of high-temperature steam during power generation, which loses energy during long-distance transportation, making it unsuitable for long-distance transport.

[0003] Lithium bromide absorption chillers use lithium bromide as the absorbent and water as the refrigerant. They are very suitable for use as a cooling source in places where there is available waste heat. By setting up hot water type lithium bromide absorption heat pump units, the waste heat after the industrial steam heating process is completed by nuclear energy can be used to provide heating and cooling to the air-conditioned rooms in the industrial base on-site, making nuclear energy cooling truly feasible. However, currently, high-temperature steam or hot water generated by nuclear energy is often directly sent to absorption chillers for cooling. This is a process of converting high-grade energy into low-grade energy, which does not conform to the principle of energy cascade utilization, has no economic benefits, and causes a lot of energy waste. Summary of the Invention

[0004] The purpose of this invention is to provide a nuclear power plant supply system that solves the problem that the electrical energy provided by existing nuclear power plants is relatively singular and the areas they can serve are relatively narrow.

[0005] To achieve this objective, the present invention adopts the following technical solution: The present invention provides a nuclear power plant supply system, including a steam generator, wherein the steam generator is connected to a steam turbine via a main pipeline, the steam turbine is driven to a generator, the generator is electrically connected to a power grid and / or an electrolysis hydrogen unit, the main pipeline is connected to a water-to-water heat exchanger via a main loop, the main pipeline is connected to a first steam-to-water heat exchanger via the main loop, the main pipeline is connected to a second steam-to-water heat exchanger via the main loop, and the main pipeline is also connected to a hydrothermal co-production unit via the main loop; The water-to-water heat exchanger is equipped with a first loop, one end of which is connected to a fresh water source. The water-to-water heat exchanger can heat the fresh water source to high temperature and high pressure saturated water and then send it out. The first steam-water heat exchanger is equipped with a second loop, one end of which is connected to a fresh water source. The first steam-water heat exchanger heats the fresh water source to high-quality industrial steam and then sends it out. The second steam-water heat exchanger is equipped with a third loop, one end of which is connected to a fresh water source. The second steam-water heat exchanger heats the fresh water source to produce steam and sends it out. The hydrogen electrolysis device is also externally connected to a photovoltaic panel, which is electrically connected to a battery. The battery is also electrically connected to a generator. The hydrothermal co-production device is equipped with a fourth loop, which is connected to seawater. The hydrothermal co-production device heats the seawater. The fourth loop exchanges heat with the heat exchange loop, and the heat exchange loop exchanges heat with the user loop. A heat storage tank is installed on the heat exchange loop, and the heat storage tank can maintain the water temperature in the heat exchange loop.

[0006] Preferably, the first loop passes through the water-to-water heat exchanger, a water pump is installed on the first loop, and a flash evaporation device is installed on the first loop near the user side. The flash evaporation device heats the water in the first loop into high-pressure steam, and the high-pressure steam is delivered to the steam user.

[0007] Preferably, a return water pump is connected to the lower side of the flash evaporator, and the return water pump draws water back into the water-to-water heat exchanger.

[0008] Preferably, a steam compression device is installed between the flash evaporator and the steam user, which can increase the steam pressure in the pipeline.

[0009] Preferably, the steam after passing through the steam user condenses into water and enters the lithium bromide absorption heat pump unit. The lithium bromide absorption heat pump unit is equipped with a delivery pipe, which is filled with water. The lithium bromide absorption heat pump unit can heat or cool the water in the delivery pipe.

[0010] Preferably, the water in the second circuit is heated by the first steam-water heat exchanger and becomes high-quality industrial steam, which is then delivered to the steam user.

[0011] Preferably, the freshwater source in the third loop is heated by the second steam-water heat exchanger and becomes steam to be processed. The steam to be processed is then transported to the hydrogen electrolysis device for direct electrolysis.

[0012] Preferably, the fourth circuit is directly delivered to the user side after passing through the heat exchange circuit.

[0013] Preferably, the heat storage tank in the heat exchange circuit generates electricity through a wind power device, and the heat storage tank maintains its internal heat through electrical energy.

[0014] Preferably, a condenser is installed in the nuclear power plant supply system. The condenser receives water from the main circuit in the water-to-water heat exchanger, the first steam-to-water heat exchanger, the second steam-to-water heat exchanger, and the hydrothermal co-production device. The condenser is connected to the recovery port of the steam generator.

[0015] Beneficial effects: During the process of generating steam to drive a steam turbine for power generation, a portion of the steam is drawn out through the main loop. A portion of this drawn-out steam then heats freshwater through the first steam-water exchanger, converting it into steam and carrying heat as it is transported to the vicinity of the nuclear power plant. The steam drawn from the main loop can also heat seawater into steam through the second steam-water exchanger, facilitating hydrogen production in the hydrogen electrolysis unit. The power for the hydrogen electrolysis unit can be derived from electricity generated by photovoltaic power generation and the steam generator. The steam from the main loop also heats freshwater and other water sources into hot water through a water-to-water heat exchanger. This hot water is then transported over long distances and flash-evaporated into steam, which is then delivered to users requiring steam. The hydrothermal co-production unit heats seawater and transports it to the user side, transferring heat through a heat exchange loop to the user's circuit. The heat is then stored in a thermal storage facility using wind power generation. The nuclear power plant's power supply system can integrate wind and solar power to provide steam and water at different temperatures to users with varying needs. It can also utilize steam for hydrogen production, expanding the scope of the nuclear power plant's power supply system and maximizing the utilization of nuclear energy. Attached Figure Description

[0016] Figure 1 This is a schematic diagram of the operation of the nuclear power plant supply system of the present invention.

[0017] In the diagram: 1. Steam generator; 2. Steam turbine; 3. Generator; 4. Hydrogen electrolysis unit; 5. Main pipeline; 6. Main circuit; 7. Power grid; 8. Water-to-water heat exchanger; 9. First steam-water heat exchanger; 10. Second steam-water heat exchanger; 11. Hydro-thermal co-production unit; 12. First circuit; 13. Second circuit; 14. Third circuit; 15. Fourth circuit; 16. Photovoltaic panel; 17. Battery; 18. Heat exchange circuit; 19. User circuit; 20. Thermal storage tank; 21. Flash evaporator; 22. Water pump; 23. Return water pump; 24. Steam compressor; 25. Steam user; 26. Lithium bromide absorption heat pump unit; 27. Condenser; 28. Wind power unit. Detailed Implementation

[0018] The present invention will now be described in further detail 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 not intended to limit it. Furthermore, it should be noted that, for ease of description, the accompanying drawings show only the parts relevant to the present invention, and not all of the structures.

[0019] In the description of this invention, unless otherwise explicitly specified and limited, the terms "connected," "linked," and "fixed" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components. Those skilled in the art can understand the specific meaning of the above terms in this invention based on the specific circumstances.

[0020] In this invention, unless otherwise explicitly specified and limited, "above" or "below" the second feature can include direct contact between the first and second features, or contact between the first and second features through another feature between them. Furthermore, "above," "over," and "on top" of the second feature includes the first feature directly above or diagonally above the second feature, or simply indicates that the first feature is at a higher horizontal level than the second feature. "Below," "below," and "under" the second feature includes the first feature directly below or diagonally below the second feature, or simply indicates that the first feature is at a lower horizontal level than the second feature.

[0021] In the description of this embodiment, the terms "upper," "lower," "right," etc., refer to the orientation or positional relationship shown in the accompanying drawings. They are used only for ease of description and simplification of operation, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on the present invention. In addition, the terms "first" and "second" are used only for distinction in description and have no special meaning.

[0022] Existing nuclear power plants typically rely solely on electricity supply, resulting in a limited and singular energy source and service area. Meanwhile, the power grid experiences peak-valley fluctuations, placing significant pressure on peak regulation. The clean electricity output from nuclear power plants is easily wasted during off-peak hours. Although wind and solar power are emerging, their output is unstable and cannot effectively complement nuclear power. Furthermore, the large amount of high-temperature steam generated during nuclear power generation suffers significant heat loss during long-distance transport, making direct external utilization difficult.

[0023] Regarding waste heat utilization, although lithium bromide absorption refrigeration technology can utilize industrial steam waste heat to provide cooling for surrounding areas, the current common practice is to directly connect high-temperature steam or hot water to the refrigeration unit. In essence, this converts high-grade heat energy into low-grade cold energy, which violates the principle of energy cascade utilization, has poor economic efficiency, and causes serious energy waste.

[0024] To solve the above problems, such as Figure 1As shown, the present invention provides a nuclear power plant supply system, including a steam generator 1, which is connected to a steam turbine 2 via a main pipeline 5. The steam turbine 2 is driven to a generator 3, which is electrically connected to a power grid 7 and / or a hydrogen electrolysis device 4. Through the above-described process, power generation can be carried out, enabling the nuclear power plant to complete its basic tasks and supply power to the user's power grid 7. Alternatively, power can be supplied first from the hydrogen electrolysis device 4.

[0025] The nuclear power plant supply system of the present invention generates a large amount of steam during daily operation. In order to maximize the utilization of the steam generated by the nuclear power plant, while some of the steam drives the turbine 2 to rotate, the other steam can transfer heat in other ways. This allows the energy generated by the continuous operation of the nuclear power plant to be effectively utilized when the demand of the power grid 7 is not high, thus avoiding the waste of energy produced by the nuclear power plant and preventing high-grade energy from being directly sent to low-grade processes before being converted into low-grade energy, which would result in energy waste and unusable energy.

[0026] In this invention, the steam entering the turbine 2 of the nuclear power plant can be drawn out in advance, and excess steam can be drawn out during the off-peak period of the power grid 7, so that the heat energy output by the nuclear power plant can be utilized in a timely manner and avoid waste. The main pipe 5 is connected to the water-to-water heat exchanger 8 through the main circuit 6, the main pipe 5 is connected to the first steam-to-water heat exchanger 9 through the main circuit 6, the main pipe 5 is connected to the second steam-to-water heat exchanger 10 through the main circuit 6, and the main pipe 5 is also connected to the hydrothermal co-generation device 11 through the main circuit 6.

[0027] By utilizing the main loop 6 to extract the high-pressure steam generated by the nuclear power plant from the main pipeline 5 and introduce it into different types of heat exchange equipment, the utilization of nuclear energy is maximized.

[0028] The water-to-water heat exchanger 8 is equipped with a first loop 12, one end of which is connected to a fresh water source. The water-to-water heat exchanger 8 can heat the fresh water source to high temperature and high pressure saturated water and then send it out. High pressure steam heats the water source in the first loop 12 through the water-to-water heat exchanger 8.

[0029] The first steam-water heat exchanger 9 is equipped with a second loop 13. One end of the second loop 13 is connected to a fresh water source. The high-temperature and high-pressure steam drawn from the nuclear power plant heats the fresh water source to high-quality industrial steam through the first steam-water heat exchanger 9 before being sent out.

[0030] The second steam-water heat exchanger 10 is equipped with a third loop 14. One end of the third loop 14 is connected to a fresh water source. The high-temperature and high-pressure steam drawn from the nuclear power plant heats the fresh water source into steam through the second steam-water heat exchanger 10 and sends it out. The hydrogen electrolysis device 4 is also externally connected to a photovoltaic panel 16. The photovoltaic panel 16 is electrically connected to a battery 17, and the battery 17 is also electrically connected to a generator 3. Combined with the photovoltaic panel 16 to generate electricity, it can supplement the power supply during the peak electricity consumption period of the power grid 7 through the photovoltaic panel 16 and the battery 17 supplemented by the photovoltaic panel 16, so that the hydrogen electrolysis device 4 can operate stably, make up for the power shortage, and achieve maximum energy output.

[0031] The hydrothermal co-production device 11 is equipped with a fourth loop 15, which is connected to seawater. The hydrothermal co-production device 11 heats the seawater. The fourth loop 15 exchanges heat with the heat exchange loop 18, and the heat exchange loop 18 exchanges heat with the user loop 19. A heat storage tank 20 is installed on the heat exchange loop 18, which can maintain the water temperature in the heat exchange loop 18.

[0032] Through the above four sets of circuits, different forms of energy can be provided to users in different fields, enabling the nuclear power plant to serve more people. At the same time, it can make up for the excess electricity generated by the nuclear power plant during off-peak hours, which can be effectively utilized by other fields and avoid energy waste.

[0033] The first loop 12 of this invention passes through a water-to-water heat exchanger 8. A water pump 22 is installed on the first loop 12, which delivers freshwater (seawater) to the water-to-water heat exchanger 8. The hot water is then heated by high-temperature steam in the main loop 6 within the water-to-water heat exchanger 8, enabling long-distance transport and reducing pipeline laying costs. A flash evaporator 21 is installed near the user side of the first loop 12. The flash evaporator 21 heats the hot water in the first loop 12 into steam, which is then delivered to the steam user 25. The flash evaporator 21 first delivers hot water, converting it into low-pressure steam as it approaches the steam user 25. Then, a steam compressor 24 converts the low-pressure steam into high-pressure steam, providing it to the corresponding, more distant steam user 25. This achieves long-distance high-pressure steam transport, and using hot water for transport reduces pipeline laying costs.

[0034] A return water pump 23 is connected to the lower side of the flash evaporator 21. The return water pump 23 draws water back into the water-to-water heat exchanger 8. The heat generated by the power plant in the water-to-water heat exchanger 8 can be reheated and transported, which can be recycled and reduce water consumption.

[0035] A steam compression device 24 is installed between the flash evaporator 21 and the steam user 25. The steam compression device 24 can increase the steam pressure in the pipeline, thereby providing different steam pressures to different steam users 25.

[0036] The high-pressure steam in the first loop 12 passes through the steam user 25 and condenses into hot water at about 90°C, which then enters the lithium bromide absorption heat pump unit 26. The lithium bromide absorption heat pump unit 26 is equipped with a delivery pipe filled with water. The lithium bromide absorption heat pump unit 26 can heat or cool the water in the delivery pipe. Through the lithium bromide absorption heat pump, cooling water or hot water can be provided to users, providing local heating and cooling to the air-conditioned rooms of the industrial base, making nuclear power cooling truly feasible.

[0037] It should be noted that the flash evaporation device 21, the vapor compression device 24, and the lithium bromide absorption heat pump unit 26 are all existing technologies, and their structural and technical principles have been disclosed, so they will not be described in detail here.

[0038] The water in the second loop 13 is heated by the first steam-water heat exchanger 9 to become high-quality industrial steam. This high-quality industrial steam is then delivered to the steam user 25. The steam user 25 served by the second loop 13 is closer than that served by the first loop 12, typically within a distance of more than ten kilometers. After being used by the steam user 25, the industrial steam delivered by the second loop 13 is condensed into condensate at a temperature of ≥90°C. This condensate has a high thermal quality and can continue to provide winter heating and summer cooling for various buildings within the industrial base after passing through the lithium bromide absorption heat pump unit 26. The condensate at ≥90°C delivered by the first loop 12 and the second loop 13 is converted into low-temperature, low-quality condensate after heat exchange by the lithium bromide absorption heat pump unit 26. This condensate can be returned to the nuclear power plant or used locally for other purposes. The lithium bromide absorption heat pump unit 26 utilizes the waste heat in the condensate to produce 75°C hot water for heating in winter and 7°C cold water for cooling in summer, meeting the indoor temperature requirements of various buildings.

[0039] The fresh water source in the third loop 14 is heated by the second steam-water heat exchanger 10 and becomes steam to be processed. The steam to be processed is then transported to the hydrogen electrolysis unit 4 for direct electrolysis.

[0040] Seawater is pumped to the second steam-water heat exchanger 10, where it is heated to generate steam (around 200°C) required for high-temperature electrolysis hydrogen production. The hydrogen electrolysis unit uses this steam as its water source, powered by direct power from the nuclear power plant, electricity generated by photovoltaic panels 16, and energy stored in battery 17. When the power grid 7 requires peak shaving, excess peak-shaving power from the nuclear power plant is directly used to produce hydrogen and stored in battery 17. When the power grid 7 does not require peak shaving, the electricity stored in battery 17 is used for hydrogen production. It should be noted that photovoltaic power generation serves as a beneficial supplement to this subsystem, providing power to a portion of the hydrogen electrolysis unit and supplementing battery 17 when its power is insufficient. Notably, battery 17 can even be used as an emergency power source for the nuclear power plant.

[0041] When the electrolytic hydrogen production unit is running stably, it can generate a very considerable and stable hydrogen source. The hydrogen source generated by the electrolytic hydrogen production unit can be stored in hydrogen storage and refueling facilities, transported over long distances via long-distance hydrogen pipelines, liquefied by liquefaction units, and used for combined heat and power supply by hydrogen fuel cell 17. Under special circumstances, it can also be used to produce higher quality green industrial steam by burning hydrogen in a hydrogen boiler.

[0042] The fourth circuit 15 is directly delivered to the user side after passing through the heat exchange circuit 18, which can provide the user with water at about 30°C. In addition, the heat storage tank 20 in the heat exchange circuit 18 generates electricity through the wind power unit 28. The heat storage tank 20 maintains its internal heat through electricity, so that the user can continuously receive hot water for use.

[0043] In the fourth loop 15, seawater is desalinated and heated by the hydrothermal co-production unit 11 to become seawater at a temperature of not less than 120°C. After being pumped by the hot water transfer pump in the plant, it is transported to the outside of the nuclear power plant. After exchanging heat through the primary heat exchanger on the heat exchange loop 18, it becomes domestic water at a temperature of about 30°C that meets the standard requirements. Finally, it is pumped to users at different distances to meet the users' domestic water needs and complete the nuclear power water supply.

[0044] The thermal storage tank 20 is located on the heat exchange loop 18. Its main heat is provided by 120°C seawater produced by the hydrothermal co-generation unit 11. The water stored in the thermal storage tank 20 is pumped to the primary side heat exchanger for heating by the primary side circulating water pump, and then returned to complete the cycle. When the thermal storage tank 20 needs additional heating or other heating needs, it can be supplemented by electrical energy provided by the wind power unit 28.

[0045] To ensure water quality safety, users do not directly exchange heat with the fourth circuit 15. Instead, heat exchange is completed through a heat exchange circuit 18. The 90°C hot water in the thermal storage tank 20 is pumped through the heat exchange circuit 18 to the heat exchanger on the heat exchange circuit 18 near the user circuit 19. After heat exchange, the temperature drops to 30°C and returns to the thermal storage tank 20. The user circuit 19 is equipped with a circulating water pump. After being heated by the heat exchanger on the user circuit 19, the water is pumped to each user for heating by the user-side circulating water pump, thus completing the heating process.

[0046] A condenser 27 is installed in the nuclear power plant's supply system. The condenser 27 receives water from the main loop 6, which passes through the water-to-water heat exchanger, the first steam-to-water heat exchanger 9, the second steam-to-water heat exchanger 10, and the hydro-thermal co-production device 11. The condenser 27 is connected to the recovery port of the steam generator 1. This prevents the radioactive steam in the main loop 6 from flowing out to the outside. The steam is then circulated internally through the water-to-water heat exchanger 8, the first steam-to-water heat exchanger 9, the second steam-to-water heat exchanger 10, and the hydro-thermal co-production device 11, thus avoiding the problem of radioactive material leakage.

[0047] This invention couples nuclear energy, wind energy, photovoltaic energy, electricity storage, and thermal energy storage to stably deliver multiple clean energy sources in various ways, improving the overall system's energy supply stability and resilience. Furthermore, the first loop 12, second loop 13, third loop 14, and fourth loop 15 all utilize exhaust heat exchange, preventing radioactive spillage. The installation of a water-heat co-production device 11 reduces pipeline construction costs and water pump energy consumption. The economical distance for water-heat co-production can reach hundreds of kilometers, enabling ultra-long-distance transmission. Simultaneously, by setting up a thermal storage tank 20 on the heat exchange loop 18 and coupling it with wind power, wind energy is rationally utilized, enhancing the system's heating reliability and safety. Additionally, the large freshwater stored in the large reservoir can meet the needs of certain emergency situations along the route.

[0048] Obviously, the above embodiments of the present invention are merely examples for clearly illustrating the present invention, and are not intended to limit the implementation of the present invention. Those skilled in the art will be able to make various obvious changes, readjustments, and substitutions without departing from the scope of protection of the present invention. It is neither necessary nor possible to exhaustively describe all embodiments here. Any modifications, equivalent substitutions, and improvements made within the spirit and principles of the present invention should be included within the scope of protection of the claims of the present invention.

Claims

1. A nuclear power plant supply system, characterized in that, The system includes a steam generator (1), which is connected to a steam turbine (2) via a main pipeline (5). The steam turbine (2) is driven to a generator (3). The generator (3) is electrically connected to a power grid (7) and / or an electrolysis hydrogen device (4). The main pipeline (5) is connected to a water-to-water heat exchanger (8) via a main circuit (6). The main pipeline (5) is connected to a first steam-to-water heat exchanger (9) via the main circuit (6). The main pipeline (5) is connected to a second steam-to-water heat exchanger (10) via the main circuit (6). The main pipeline (5) is also connected to a hydrothermal co-production device (11) via the main circuit (6). The water-to-water heat exchanger (8) is equipped with a first circuit (12), one end of which is connected to a fresh water source. The water-to-water heat exchanger (8) can heat the fresh water source to high temperature and high pressure saturated water and then send it out. The first steam-water heat exchanger (9) is equipped with a second circuit (13), one end of which is connected to a fresh water source. The first steam-water heat exchanger (9) heats the fresh water source to high-quality industrial steam and then sends it out. The second steam-water heat exchanger (10) is equipped with a third loop (14), one end of which is connected to a fresh water source. The second steam-water heat exchanger (10) heats the fresh water source to produce steam and sends it out. The electrolysis hydrogen device (4) is also externally connected to a photovoltaic panel (16). The photovoltaic panel (16) is electrically connected to a battery (17), and the battery (17) is also electrically connected to a generator (3). The hydrothermal co-production device (11) is equipped with a fourth loop (15), which is connected to seawater. The hydrothermal co-production device (11) heats the seawater. The fourth loop (15) exchanges heat with the heat exchange loop (18). The heat exchange loop (18) exchanges heat with the user loop (19). A heat storage tank (20) is installed on the heat exchange loop (18). The heat storage tank (20) can maintain the water temperature in the heat exchange loop (18).

2. The nuclear power plant supply system according to claim 1, characterized in that, The first circuit (12) passes through the water heat exchanger (8). A water pump (22) is installed on the first circuit (12). A flash evaporator (21) is installed on the first circuit (12) near the user side. The flash evaporator (21) heats the water in the first circuit (12) into high-pressure steam. The high-pressure steam is delivered to the steam user (25).

3. The nuclear power plant supply system according to claim 2, characterized in that, The flash evaporator (21) is connected to a return water pump (23) on its lower side, which draws water back into the water-to-water heat exchanger (8).

4. The nuclear power plant supply system according to claim 3, characterized in that, A steam compression device (24) is installed between the flash evaporator (21) and the steam user (25), which can increase the steam pressure in the pipeline.

5. The nuclear power plant supply system according to claim 2, characterized in that, The steam passing through the steam user (25) condenses into water and enters the lithium bromide absorption heat pump unit (26). The lithium bromide absorption heat pump unit (26) is equipped with a delivery pipe, which is filled with water. The lithium bromide absorption heat pump unit (26) can heat or cool the water in the delivery pipe.

6. The nuclear power plant supply system according to claim 2, characterized in that, The water in the second circuit (13) is heated by the first steam-water heat exchanger (9) and becomes high-quality industrial steam, which is then delivered to the steam user (25).

7. The nuclear power plant supply system according to claim 1, characterized in that, The fresh water source in the third circuit (14) is heated by the second steam-water heat exchanger (10) and becomes steam to be processed. The steam to be processed is then transported to the hydrogen electrolysis device (4) for direct electrolysis.

8. The nuclear power plant supply system according to claim 1, characterized in that, The fourth circuit (15) is directly delivered to the user side after passing through the heat exchange circuit (18).

9. The nuclear power plant supply system according to claim 1, characterized in that, The heat storage tank (20) in the heat exchange circuit (18) generates electricity through a wind power device (28), and the heat storage tank (20) maintains its internal heat through electrical energy.

10. The nuclear power plant supply system according to claim 1, characterized in that, A condenser (27) is installed in the nuclear power plant supply system. The condenser (27) receives water from the main circuit (6) in the water-water heat exchanger (8), the first steam-water heat exchanger (9), the second steam-water heat exchanger (10), and the water-heat co-production device (11). The condenser (27) is connected to the recovery port of the steam generator (1).

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