A nuclear power generation system

Abstract

This application provides a nuclear power generation system, including a nuclear power unit, a pool-type cryogenic heating reactor, and a steam supply system. A primary heat exchanger of the pool-type cryogenic heating reactor is connected between the condenser and the condensate pump in the nuclear power unit. The steam supply system includes, in sequence, a seawater desalination and demineralized water unit, a feedwater tank, a feedwater regulating valve, a preheater, an evaporator, a superheater, and an industrial steam supply pipeline. A second primary heat exchanger of the pool-type cryogenic heating reactor is connected between the feedwater regulating valve and the preheater. The hot-side inlet of the superheater is connected to the main steam outlet pipeline of the reactor in the nuclear power unit, and the hot-side outlet of the preheater is connected to a branch pipeline of the pipeline connecting the pool-type cryogenic heating reactor and the condensate pump. This application utilizes the pool-type cryogenic heating reactor to heat the condensate after the condenser and the demineralized water after the feedwater tank, increasing the total power generation of the nuclear power generation system and also realizing the reprocessing and recycling of spent fuel.

Description

Technical Field

[0001] The present application belongs to the technical field of nuclear power generation, and specifically relates to a nuclear power generation system. Background Art

[0002] With the acceleration of industrialization, the situation of air pollution in my country is becoming increasingly serious. Nuclear energy is a clean, zero-carbon, stable energy source that can replace traditional fossil fuels. Its application in power generation, heat and steam supply is an important research direction and component of the future development of nuclear energy.

[0003] The pressurized water reactor has a compact structure, and the steam outlet temperature is usually around 330℃. It has a small volume, high power density and good power self-stabilization and self-regulation characteristics; the steam temperature of the heavy water reactor nuclear power plant is between 250℃ and 300℃, and the operating temperature of the sodium-cooled fast reactor exceeds 500℃; the high temperature gas-cooled reactor, as a new type of nuclear power generation technology, uses helium as a coolant. Compared with the traditional water-cooled reactor, the operating temperature can reach above 900℃. The higher temperature can improve the power density and thermal efficiency, and enhance the ability of nuclear energy to convert into electrical energy. Promoting the development of nuclear energy in a timely manner to meet the needs of power generation, industrial steam supply, heating, seawater desalination, hydrogen production, etc. is of practical significance for low-carbon transformation and the direct replacement of terminal energy such as coal.

[0004] However, existing nuclear power plants such as pressurized water reactors or heavy water reactors usually include reactors and steam turbine generator sets. The steam turbine generator sets are usually equipped with multiple low-pressure heaters to heat the condensate after the condenser. This causes the existing nuclear power units to have a large amount of steam turbine extraction due to their own structural design, and also seriously affects the total power generation of the nuclear power units. Summary of the invention

[0005] In view of this, the embodiments of the present application are committed to providing a nuclear power generation system. By utilizing a swimming pool-type low-temperature heating reactor to heat the condensate after the condenser and the desalted water after the feed water tank, the problem of large steam turbine extraction volume in existing nuclear power units due to structural design reasons can be solved, which seriously affects the total power generation of the nuclear power units.

[0006] The present application provides a nuclear power generation system, which includes a nuclear power unit 10, a swimming pool type low temperature heating reactor 20 and a steam supply system 30. The primary heat exchanger 250 of the swimming pool type low temperature heating reactor 20 is connected between the condenser 113 and the condensate pump 114 in the nuclear power unit 10. The steam supply system 30 includes a seawater desalination and desalination device 310, a feed water tank 320, a feed water regulating valve 380, a preheater 340, an evaporator 350, a superheater 360 and an industrial steam supply pipeline 370 which are connected in sequence. The primary heat exchanger 251 of the swimming pool type low temperature heating reactor 20 is connected between the feed water regulating valve 380 and the preheater 340, the hot side inlet of the superheater 360 is connected to the main steam outlet pipeline of the reactor 100 in the nuclear power unit 10, and the hot side outlet of the preheater 340 is connected to the branch pipeline of the pipeline connecting the swimming pool type low temperature heating reactor 20 and the condensate pump 114.

[0007] In a specific embodiment of the present application, the steam supply system 30 further includes a first regulating valve 390 and a second regulating valve 400. The first regulating valve 390 is located between the feed water regulating valve 380 and the preheater 340, and the pipeline where the first regulating valve 390 is located is connected in parallel with the pipeline in which the swimming pool type low temperature heating reactor 20 and the second regulating valve 400 are connected in series, and the second regulating valve 400 is located between the swimming pool type low temperature heating reactor 20 and the feed water regulating valve 380.

[0008] In a specific embodiment of the present application, the steam supply system 30 further includes a pressurized water pump 330 , which is used to control the pressure of the steam supply loop. The pressurized water pump 330 is connected between the second primary heat exchanger 251 and the preheater 340 .

[0009] In a specific embodiment of the present application, the swimming pool type low temperature heating reactor 20 includes a secondary circuit inlet pipe 261 and a secondary circuit outlet pipe 271. The outlet of the feed water tank 320 is connected to the cold side inlet of the primary heat exchanger 251 through the secondary circuit inlet pipe 261, and the cold side outlet of the primary heat exchanger 251 is connected to the pressurized water pump 330 through the secondary circuit outlet pipe 271.

[0010] In a specific embodiment of the present application, a temperature control module is provided on the swimming pool type low temperature heating reactor 20. The temperature control module is used to control the swimming pool type low temperature heating reactor 20 to heat the condensed water after the condenser 113 and the demineralized water after the feed water tank 320 to a preset temperature range.

[0011] In a specific embodiment of the present application, the nuclear power unit 10 includes a reactor 100 and a steam turbine generator set 110, and the steam turbine generator set 110 includes a steam turbine 111, a generator 112, and a feed water pump 117. The main steam outlet of the reactor 100 and the inlet of the steam turbine 111, the exhaust port of the steam turbine 111 and the hot side inlet of the condenser 113, the secondary circuit inlet of the swimming pool type low temperature heating reactor 20 and the hot side outlet of the condenser 113, the secondary circuit outlet of the swimming pool type low temperature heating reactor 20 and the inlet of the condensate pump 114, the outlet of the condensate pump 114 and the inlet of the feed water pump 117, and the outlet of the feed water pump 117 and the return inlet of the reactor 100 are connected by pipelines.

[0012] In a specific embodiment of the present application, the steam turbine generator set 110 further includes a low-pressure heater 115 , which is connected between the condensate pump 114 and the feed water pump 117 , and the low-pressure heater 115 is connected to the steam turbine 111 through a pipeline.

[0013] In a specific embodiment of the present application, the steam turbine generator set 110 further includes a deaerator 116 , which is connected between the low-pressure heater 115 and the feed water pump 117 , and the deaerator 116 is connected to the steam turbine 111 through a pipeline.

[0014] In a specific embodiment of the present application, the nuclear power unit 10 further includes a condensate polishing device 119 . The condensate polishing device 119 is connected between the swimming pool type low temperature heating reactor 20 and the condensate pump 114 .

[0015] In a specific embodiment of the present application, the swimming pool type low temperature heating reactor 20 also includes a swimming pool type low temperature heating reactor core 210, a primary circuit water inlet pipe 220, a primary circuit water outlet pipe 230, a primary circuit pump 240, a secondary circuit inlet pipe 260, a secondary circuit outlet pipe 270, a primary circuit water inlet pipe 221, a primary circuit water outlet pipe 231, and a primary circuit pump 241. The core 210 of the swimming pool type low temperature heating reactor is located at the bottom of the pool. The pool water enters the core 210 of the swimming pool type low temperature heating reactor from below. After being heated in the core 210 of the swimming pool type low temperature heating reactor, the pool water enters the primary circuit pump 240 along the primary circuit outlet pipe 230. After heat exchange in the primary heat exchanger 250, the water is sent back to the pool through the primary circuit inlet pipe 220. The hot side outlet of the condenser 113 is connected to the cold side inlet of the primary heat exchanger 250 through the secondary circuit inlet pipe 260 of the swimming pool type low temperature heating reactor 20, and the cold side outlet of the primary heat exchanger 250 is connected to the condensate pump 114 through the secondary circuit outlet pipe 270 of the swimming pool type low temperature heating reactor 20.

[0016] The beneficial effect of the technical solution of the present application is that by connecting the swimming pool type low temperature heating reactor 20 between the condenser 113 and the condensate pump 114, the heat generated by nuclear fission in the swimming pool type low temperature heating reactor 20 is used to heat the condensate after the condenser 113, thereby, on the one hand, replacing the last stage low pressure heater in the original steam turbine generator set with the swimming pool type low temperature heating reactor 20 to heat the condensate after the condenser, and continuously providing a heat source to the secondary circuit of the nuclear power unit 10, and also reducing the steam extraction amount of the steam turbine, and finally increasing the total power generation of the nuclear power generation system; on the other hand, the nuclear fuel in the swimming pool type low temperature heating reactor 20 uses the spent fuel in the reactor 100, and realizes the post-processing and recycling of the spent fuel. In addition, by connecting the swimming pool type low temperature heating reactor 20 between the feed water regulating valve 380 and the preheater 340 of the steam supply system 30, the swimming pool type low temperature heating reactor 20 is coupled to the preheating section of the steam supply system 30 at the same time, and the swimming pool type low temperature heating reactor 20 is used to perform the first stage heating of the desalted water, and the desalted water is heated to the specified first stage preheating temperature. The swimming pool type low temperature heating reactor 20 replaces the first stage desalted water preheater, and the primary loop system of the swimming pool type low temperature heating reactor 20 continuously extracts the heat of its core and transfers the heat to the desalted water through the primary heat exchanger 251. The nuclear fuel in the swimming pool type low temperature heating reactor 20 uses the spent fuel in the reactor 100, which can realize the post-processing and recycling of the spent fuel, realize the energy cascade utilization, further reduce the exergy loss caused by incomplete utilization of nuclear fuel, and improve the energy utilization rate. BRIEF DESCRIPTION OF THE DRAWINGS

[0017] Figure 1 Shown is a schematic structural diagram of a nuclear power generation system provided in one embodiment of the present application.

[0018] Figure 2 Shown is a schematic structural diagram of a swimming pool-type low-temperature heating reactor provided in one embodiment of the present application. DETAILED DESCRIPTION

[0019] The following will be combined with the drawings in the embodiments of the present application to clearly and completely describe the technical solutions in the embodiments of the present application. Obviously, the described embodiments are only part of the embodiments of the present application, not all of the embodiments. Based on the embodiments in the present application, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of this application.

[0020] At least one embodiment of the present application provides a nuclear power generation system, referring to Figure 1 and Figure 2The nuclear power generation system includes a nuclear power unit 10, a swimming pool type low temperature heating reactor 20 and a steam supply system 30. The primary heat exchanger 1 250 of the swimming pool type low temperature heating reactor 20 is connected between the condenser 113 and the condensate pump 114 in the nuclear power unit 10. The steam supply system 30 includes a seawater desalination and desalination device 310, a feed water tank 320, a feed water regulating valve 380, a preheater 340, an evaporator 350, a superheater 360 and an industrial steam supply pipeline 370 which are connected in sequence. The primary heat exchanger 2 251 of the swimming pool type low temperature heating reactor 20 is connected between the feed water regulating valve 380 and the preheater 340, the hot side inlet of the superheater 360 is connected to the main steam outlet pipeline of the reactor 100 in the nuclear power unit 10, and the hot side outlet of the preheater 340 is connected to the branch pipeline of the pipeline connecting the swimming pool type low temperature heating reactor 20 and the condensate pump 114.

[0021] It should be noted that the fresh water provided by the seawater desalination and desalination device 310 flows sequentially through the feed water tank 320, the feed water regulating valve 380, the swimming pool type low temperature heating reactor 20, the preheater 340, the evaporator 350 and the cold side of the superheater 360, and the industrial steam at the cold side outlet of the superheater 360 is provided to industrial users by the industrial steam supply pipeline 370. The steam supply system 30 can be located in the steam supply plant.

[0022] According to the technical solution provided in the embodiment of the present application, by connecting the swimming pool type low temperature heating reactor 20 between the condenser 113 and the condensate pump 114, the heat generated by nuclear fission in the swimming pool type low temperature heating reactor 20 is used to heat the condensate after the condenser 113, so that on the one hand, the swimming pool type low temperature heating reactor 20 replaces the final low pressure heater in the original steam turbine generator set to heat the condensate after the condenser, which can continuously provide heat source to the secondary circuit of the nuclear power unit 10, and can also reduce the steam extraction of the steam turbine, and finally increase the total power generation of the nuclear power generation system. On the other hand, the nuclear fuel in the swimming pool type low temperature heating reactor 20 uses the spent fuel in the reactor 100, and the post-processing and recycling of the spent fuel is realized. In the embodiment of the present application, by coupling the swimming pool type low temperature heating reactor 20 to the nuclear power generation system, the swimming pool type low temperature heating reactor 20 is fully utilized. The good inherent safety and reliability of the operation under low parameters and the simple reactor structure are characteristics.

[0023] In addition, the embodiment of the present application connects the swimming pool type low temperature heating reactor 20 between the feed water regulating valve 380 and the preheater 340 of the steam supply system 30, thereby realizing the simultaneous coupling of the swimming pool type low temperature heating reactor 20 to the preheating section of the steam supply system 30, utilizing the swimming pool type low temperature heating reactor 20 to perform the first stage heating of the desalted water, heating the desalted water to the specified first stage preheating temperature, and replacing the first stage desalted water preheater with the swimming pool type low temperature heating reactor 20. The primary loop system of the swimming pool type low temperature heating reactor 20 continuously extracts the heat of its core and transfers the heat to the desalted water through the primary heat exchanger 251. The nuclear fuel in the swimming pool type low temperature heating reactor 20 uses the spent fuel in the reactor 100, and the spent fuel can be post-processed and recycled, realizing the cascade utilization of energy, further reducing the exergy loss caused by incomplete utilization of nuclear fuel, and improving the energy utilization rate.

[0024] In at least one embodiment of the present application, reference Figure 1 The steam supply system 30 further includes a first regulating valve 390 and a second regulating valve 400. The first regulating valve 390 is located between the feedwater regulating valve 380 and the preheater 340. The pipeline where the first regulating valve 390 is located is connected in parallel with the pipeline in which the swimming pool type low temperature heating reactor 20 and the second regulating valve 400 are connected in series. The second regulating valve 400 is located between the swimming pool type low temperature heating reactor 20 and the feedwater regulating valve 380.

[0025] In the embodiment of the present application, by adding a first regulating valve 390 and a second regulating valve 400 to the steam supply system 30, the nuclear power generation system can have two steam supply processes. In the first steam supply process, the first regulating valve 390 is in an open state, the second regulating valve 400 is in a closed state, and the desalted water flows through the feed water tank 320, the feed water regulating valve 380, the first regulating valve 390, the preheater 340, the evaporator 350 and the cold side of the superheater 360 in sequence, and the industrial steam at the cold side outlet of the superheater 360 is provided to industrial users by the industrial steam supply pipeline 370. The first steam supply process uses nuclear energy to supply green, clean, zero-carbon high-quality steam heat to provide heat for the three-circuit steam supply system 30, so that the produced steam products are physically separated from the first and second circuits of the nuclear power unit 10, and industrial steam supply is realized while generating electricity. In the second steam supply process, the first regulating valve 390 is in a closed state, the second regulating valve 400 is in an open state, and fresh water flows through the feed water tank 320, the feed water regulating valve 380, the second regulating valve 400, the swimming pool type low temperature heating reactor 20, the preheater 340, the evaporator 350 and the cold side of the superheater 360 in sequence, and the industrial steam at the cold side outlet of the superheater 360 is provided to industrial users by the industrial steam supply pipeline 370. The condensed water at the hot side outlet of the condenser 113 and the desalted water in the second steam supply process enter the swimming pool type low temperature heating reactor 20 to absorb the heat generated by nuclear fission.

[0026] In at least one embodiment of the present application, the steam supply system 30 further includes a pressurized water pump 330, which is used to control the pressure of the steam supply circuit. The pressurized water pump 330 is connected between the primary heat exchanger 251 and the preheater 340. In this way, by adding the pressurized water pump 330, the pressure can be adjusted by the pressurized water pump 330, and then a steam product of corresponding pressure can be obtained.

[0027] The nuclear power plant 10 may also be referred to as a nuclear power generating unit. The types of reactors 100 include, but are not limited to, high temperature gas-cooled reactors, pressurized water reactors, heavy water reactors, or sodium-cooled fast reactors. The structure of the nuclear power plant 10 is described below with reference to specific embodiments.

[0028] In at least one embodiment of the present application, the nuclear power unit 10 includes a reactor 100 and a steam turbine generator set 110. The steam turbine generator set 110 includes a steam turbine 111, a generator 112, and a feed water pump 117. The main steam outlet of the reactor 100 and the inlet of the steam turbine 111, the exhaust port of the steam turbine 111 and the hot side inlet of the condenser 113, the secondary circuit inlet of the swimming pool type low temperature heating reactor 20 and the hot side outlet of the condenser 113, the secondary circuit outlet of the swimming pool type low temperature heating reactor 20 and the inlet of the condensate pump 114, the outlet of the condensate pump 114 and the inlet of the feed water pump 117, and the outlet of the feed water pump 117 and the return inlet of the reactor 100 are connected by pipelines.

[0029] Specifically, the main steam of the reactor 100 is transmitted to the inlet of the steam turbine 111 through the main steam outlet of the reactor 100. After the main steam performs work in the steam turbine 111, it is transmitted to the hot side inlet of the condenser 113 through the exhaust port of the steam turbine 111, and condensed in the condenser 113 to form condensed water. The condensed water at the hot side outlet of the condenser 113 enters the swimming pool type low temperature heating reactor 20. After the condensed water at the hot side outlet of the condenser 113 absorbs the heat generated by nuclear fission in the swimming pool type low temperature heating reactor 20 and heats up, it flows through the condensate pump 114 and the feed water pump 117 in sequence and then returns to the reactor 100 to complete the secondary circuit steam-water cycle.

[0030] It should be noted that the steam turbine generator set 110 may also include other equipment and pipelines. If the reactor 100 is a high temperature gas-cooled reactor, the steam turbine generator set 110 may also include a high pressure heater 118. The high pressure heater 118 is connected between the feed water pump 117 and the reactor 100. The high pressure heater 118 is connected to the steam turbine 111.

[0031] The main steam outlet pipe of the reactor 100 is connected to the hot side inlet of the superheater 360. The hot side outlet of the preheater 340 is connected to the branch pipe of the pipe connecting the swimming pool type low temperature heating reactor 20 and the condensate pump 114. In this way, the main steam outlet pipe of the reactor 100 is connected to the inlet of the turbine 111 and the hot side inlet of the superheater 360 in the steam supply system 30. A part of the main steam enters the hot side of the condenser 113 after doing work in the turbine 111, and the condensate at the hot side outlet of the condenser 113 enters the swimming pool-type low-temperature heating reactor 20 to absorb the heat generated by nuclear fission; the other part of the main steam enters the steam supply system 30, flows through the hot sides of the superheater 360, the evaporator 350 and the preheater 340 in sequence, and the working fluid at the hot side outlet of the preheater 340 merges with the condensate after the temperature is increased at the outlet of the swimming pool-type low-temperature heating reactor 20, and then flows through the condensate pump 114 and the feed water pump 117 in sequence and returns to the reactor 100 to complete the secondary steam-water cycle.

[0032] The core of the reactor 100 in the nuclear power unit 10 generates huge heat energy due to the fission of nuclear fuel. The circuit that exchanges heat with the core of the reactor 100 is called the primary circuit of the nuclear power unit 10. The circuit that exchanges heat with the primary circuit of the nuclear power unit 10 is called the secondary circuit of the nuclear power unit 10. The reactor 100 may include a core, a reactor vessel, and a steam generator. The steam generator can isolate the primary circuit and the secondary circuit, ensure that the heat released by the reactor 100 is transferred from the primary circuit to the secondary circuit under various operating conditions, and drive the steam turbine 111 to do work.

[0033] In at least one embodiment of the present application, the steam turbine generator set 110 further includes a low-pressure heater 115. The low-pressure heater 115 is connected between the condensate pump 114 and the feedwater pump 117. The low-pressure heater 115 is connected to the steam turbine 111. For example, the low-pressure heater 115 may be a single-stage low-pressure heater.

[0034] In at least one embodiment of the present application, the steam turbine generator set 110 further includes a deaerator 116. The deaerator 116 is connected between the low-pressure heater 115 and the feedwater pump 117. The deaerator 116 is connected to the steam turbine 111 through a pipeline. In this way, the deaerator 116 is used to effectively remove oxygen from the water, protect the internal structure of the steam turbine 111 from damage, and improve the operating efficiency and safety of the steam turbine 111.

[0035] In at least one embodiment of the present application, the nuclear power unit 10 further includes a condensate polishing device 119. The condensate polishing device 119 is connected between the swimming pool type low temperature heating reactor 20 and the condensate pump 114. If the swimming pool type low temperature heating reactor 20 has a primary heat exchanger 250, the cold side outlet of the primary heat exchanger 250 is connected to the condensate polishing device 119 through the secondary circuit outlet pipe 270 of the swimming pool type low temperature heating reactor 20. In this way, by adding the condensate polishing device 119, the condensate polishing device 119 is used to perform polishing on the feed water heated by the swimming pool type low temperature heating reactor 20, thereby improving the water quality before entering the condensate pump 114.

[0036] For example, the feed water at the outlet of the condensate polishing device 119 flows through the condensate pump 114, the cold side of the low-pressure heater 115, the cold side of the deaerator 116, the feed water pump 117 and the cold side of the high-pressure heater 118 in sequence, and the feed water at the cold side outlet of the high-pressure heater 118 returns to the reactor 100 to complete the secondary loop steam-water cycle. In this way, by coupling the swimming pool type low-temperature heating reactor 20 with the nuclear power unit 10, the coupling position 1 is the last stage low-pressure heater in the conventional island of the nuclear power unit, and the swimming pool type low-temperature heating reactor 20 replaces the last stage low-pressure heater, the condensate is heated, the low-pressure heater 115 before the deaerator 116 is retained, and the condensate polishing device 119 is added, so that the parameters of the secondary loop working medium before entering the deaerator 116 meet the requirements.

[0037] If the steam turbine generator set 110 includes a low-pressure heater 115, a deaerator 116, a high-pressure heater 118 and a condensate polishing device 119, the working fluid at the hot side outlet of the preheater 340 and the condensate after heating at the outlet of the swimming pool-type low-temperature heating reactor 20 are combined into the condensate polishing device 119, and the feed water at the outlet of the condensate polishing device 119 flows through the condensate pump 114, the cold side of the low-pressure heater 115, the cold side of the deaerator 116, the feed water pump 117 and the cold side of the high-pressure heater 118 in sequence, and the feed water at the cold side outlet of the high-pressure heater 118 returns to the reactor 100, completing the secondary steam-water circulation.

[0038] The primary circuit system of the swimming pool type low temperature heating reactor 20 can continuously extract the heat from its core, and transfer the heat to the secondary circuit of the nuclear power unit through the primary heat exchanger 250 of the swimming pool type low temperature heating reactor 20. Compared with the pressure shell reactor, the swimming pool type low temperature heating reactor 20 omits structures such as pressure vessels and containment shells, and has the advantages of low operating costs, convenient maintenance, simple structure, and long service life. The swimming pool type low temperature heating reactor operates under low parameters, has good inherent safety and reliability, has a simple reactor structure, and low investment. It can provide hot water at about 90°C for the heating network. It is currently mainly used in small and medium-sized heating networks. Below, refer to Figure 2, the structural composition of the swimming pool type low temperature heating reactor 20 is illustrated with examples in combination with specific embodiments.

[0039] In at least one embodiment of the present application, a temperature control module is provided on the swimming pool type low temperature heating reactor 20. The temperature control module is used to control the swimming pool type low temperature heating reactor 20 to heat the condensed water after the condenser 113 and the demineralized water after the feed water tank 320 to a preset temperature range.

[0040] The swimming pool type low temperature heating reactor 20 can heat the condensed water after the condenser 113 to a preset temperature range according to actual needs. For example, in some embodiments, the preset temperature range is 90±5 degrees. In this way, the swimming pool type low temperature heating reactor 20 can heat the condensed water after the condenser 113 to about 90 degrees.

[0041] In at least one embodiment of the present application, the swimming pool-type low-temperature heating reactor 20 includes a secondary circuit inlet pipe 261 and a secondary circuit outlet pipe 271, the outlet of the feed water tank 320 is connected to the cold side inlet of the primary heat exchanger 251 through the secondary circuit inlet pipe 261, and the cold side outlet of the primary heat exchanger 251 is connected to the pressurized water pump 330 through the secondary circuit outlet pipe 271.

[0042] In at least one embodiment of the present application, the swimming pool type low temperature heating reactor 20 also includes a swimming pool type low temperature heating reactor core 210, a primary circuit water inlet pipe 220, a primary circuit water outlet pipe 230, a primary circuit pump 240, a secondary circuit inlet pipe 260, a secondary circuit outlet pipe 270, a primary circuit water inlet pipe 221, a primary circuit water outlet pipe 231, and a primary circuit pump 241. The core 210 of the swimming pool type low temperature heating reactor is located at the bottom of the pool. The pool water enters the core 210 of the swimming pool type low temperature heating reactor from below. After being heated in the core 210 of the swimming pool type low temperature heating reactor, the pool water enters the primary circuit pump 240 along the primary circuit outlet pipe 230. After heat exchange in the primary heat exchanger 250, the water is sent back to the pool through the primary circuit inlet pipe 220. The hot side outlet of the condenser 113 is connected to the cold side inlet of the primary heat exchanger 250 through the secondary circuit inlet pipe 260 of the swimming pool type low temperature heating reactor 20, and the cold side outlet of the primary heat exchanger 250 is connected to the condensate pump 114 through the secondary circuit outlet pipe 270 of the swimming pool type low temperature heating reactor 20.

[0043] It should be noted that the pool-type low-temperature heating reactor core 210 is immersed in a deep water pool and is located at the bottom of the pool. The pool contains sufficient water and uses the static pressure of the water layer to increase the core outlet water temperature to meet the temperature requirements of low-temperature heating.

[0044] It should also be noted that the combination of the various technical features in the embodiments of the present application is not limited to the combination described in the embodiments of the present application or the combination described in the specific embodiments, and all technical features described in the present application can be freely combined or combined in any way unless there is a contradiction between them.

[0045] As shown in this application and claims, unless the context clearly indicates an exception, the words "a", "an" and / or "the" do not refer to the singular and may also include the plural. Generally speaking, the term "comprising" only indicates that the steps and elements that have been clearly identified are included, and these steps and elements do not constitute an exclusive list. The method or device may also include other steps or elements.

[0046] The terms "one" and "two" are used for descriptive purposes only and should not be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, features such as primary heat exchanger one 250, primary heat exchanger two 251, etc., which are defined as "one" or "two", may explicitly or implicitly include one or more of the features.

[0047] The above are only preferred embodiments of the present application and are not intended to limit the present application. Any modifications, equivalent substitutions, etc. made within the spirit and principles of the present application should be included in the protection scope of the present application.

Claims

1. A nuclear power generation system, characterized in that: It comprises a nuclear power unit (10), a swimming pool type low temperature heating reactor (20) and a steam supply system (30), The first primary heat exchanger (250) of the swimming pool-type low-temperature heating reactor (20) is connected between the condenser (113) and the condensate pump (114) in the nuclear power unit (10). The steam supply system (30) comprises a seawater desalination and desalination device (310), a water supply tank (320), a water supply regulating valve (380), a preheater (340), an evaporator (350), a superheater (360), and an industrial steam supply pipeline (370) which are connected in sequence. The second primary heat exchanger (251) of the swimming pool type low temperature heating reactor (20) is connected between the feed water regulating valve (380) and the preheater (340), the hot side inlet of the superheater (360) is connected to the main steam outlet pipeline of the reactor (100) in the nuclear power unit (10), and the hot side outlet of the preheater (340) is connected to the branch pipeline of the pipeline connecting the swimming pool type low temperature heating reactor (20) and the condensate pump (114).

2. The nuclear power generation system according to claim 1, characterized in that: The steam supply system (30) further comprises a first regulating valve (390) and a second regulating valve (400), wherein the first regulating valve (390) is located between the feed water regulating valve (380) and the preheater (340), and the pipeline where the first regulating valve (390) is located is arranged in parallel with the pipeline connected in series with the swimming pool type low temperature heating reactor (20) and the second regulating valve (400), and the second regulating valve (400) is located between the swimming pool type low temperature heating reactor (20) and the feed water regulating valve (380).

3. The nuclear power generation system according to claim 1, characterized in that: The steam supply system (30) further comprises a pressurized water pump (330), wherein the pressurized water pump (330) is used to control the pressure of the steam supply circuit, and the pressurized water pump (330) is connected between the second primary heat exchanger (251) and the preheater (340).

4. The nuclear power generation system according to claim 3, characterized in that: The swimming pool type low temperature heating reactor (20) comprises a second secondary circuit inlet pipe (261) and a second secondary circuit outlet pipe (271), wherein the outlet of the feed water tank (320) is connected to the cold side inlet of the second primary heat exchanger (251) via the second secondary circuit inlet pipe (261), and the cold side outlet of the second primary heat exchanger (251) is connected to the pressurized water pump (330) via the second secondary circuit outlet pipe (271).

5. The nuclear power generation system according to claim 1, characterized in that: The swimming pool type low temperature heating reactor (20) is provided with a temperature control module, and the temperature control module is used to control the swimming pool type low temperature heating reactor (20) to heat the condensed water after the condenser (113) and the desalted water after the water supply tank (320) to within a preset temperature range.

6. The nuclear power generation system according to claim 1, characterized in that: The nuclear power unit (10) comprises a reactor (100) and a steam turbine generator unit (110); the steam turbine generator unit (110) comprises a steam turbine (111), a generator (112) and a feed water pump (117). The main steam outlet of the reactor (100) and the inlet of the steam turbine (111), the exhaust port of the steam turbine (111) and the hot side inlet of the condenser (113), the secondary circuit inlet of the swimming pool type low temperature heating reactor (20) and the hot side outlet of the condenser (113), the secondary circuit outlet of the swimming pool type low temperature heating reactor (20) and the inlet of the condensate pump (114), the outlet of the condensate pump (114) and the inlet of the feed water pump (117), and the outlet of the feed water pump (117) and the return inlet of the reactor (100) are connected respectively by pipelines.

7. The nuclear power generation system according to claim 6, characterized in that: The steam turbine generator set (110) further comprises a low-pressure heater (115), wherein the low-pressure heater (115) is connected between the condensate pump (114) and the feed water pump (117), and the low-pressure heater (115) is connected to the steam turbine (111) via a pipeline.

8. The nuclear power generation system according to claim 7, characterized in that: The steam turbine generator set (110) further comprises a deaerator (116), wherein the deaerator (116) is connected between the low-pressure heater (115) and the feedwater pump (117), and the deaerator (116) is connected to the steam turbine (111) via a pipeline.

9. The nuclear power generation system according to claim 1, characterized in that: The nuclear power unit (10) further comprises a condensate polishing device (119), wherein the condensate polishing device (119) is connected between the swimming pool type low temperature heating reactor (20) and the condensate pump (114).

10. The nuclear power generation system according to any one of claims 1 to 9, characterized in that: The swimming pool type low temperature heating reactor (20) further comprises a swimming pool type low temperature heating reactor core (210), a first circuit water inlet pipe (220), a first circuit water outlet pipe (230), a first circuit pump (240), a second circuit inlet pipe (260), a second circuit outlet pipe (270), a second first circuit water inlet pipe (221), a second first circuit water outlet pipe (231), and a second first circuit pump (241). The swimming pool type low temperature heating reactor core (210) is located at the bottom of the pool. Pool water enters the swimming pool type low temperature heating reactor core (210) from below. After being heated in the swimming pool type low temperature heating reactor core (210), the pool water enters the primary circuit pump (240) along the primary circuit outlet pipe (230). After heat exchange in the primary heat exchanger (250), the pool water is sent back to the pool through the primary circuit inlet pipe (220). The hot side outlet of the condenser (113) is connected to the cold side inlet of the primary heat exchanger (250) through the secondary circuit inlet pipe (260) of the swimming pool type low temperature heating reactor (20). The cold side outlet of the primary heat exchanger (250) is connected to the condensate pump (114) through the secondary circuit outlet pipe (270) of the swimming pool type low temperature heating reactor (20).

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