CN111834026A - An industrial steam production system for pressurized water reactor nuclear power units - Google Patents

Abstract

The invention discloses an industrial steam production system for a pressurized water reactor nuclear power unit, comprising: a nuclear steam supply device, which is a pressurized water reactor nuclear power unit. ;Industrial steam production device, the inlet of which is connected to the outlet of the nuclear steam supply device, the heat source steam exchanges heat with the feed water introduced into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters, which is used for transmission to the heat source. user. The invention relies on the pressurized water reactor nuclear power unit, utilizes the secondary circuit main steam of the pressurized water reactor nuclear power unit to produce industrial steam through an industrial steam production device, and transports it to users through a steam pipe network, so as to realize the application of the nuclear power station to supply clean industrial steam to the outside world. It has opened up new ways of comprehensive utilization of nuclear energy, effectively solved the environmental pollution caused by traditional energy such as coal combustion, improved the energy structure, guaranteed the steam demand for industrial development, and improved the economic benefits of nuclear power plants.

Description

An industrial steam production system for pressurized water reactor nuclear power units

technical field

The invention belongs to the technical field of comprehensive utilization of nuclear energy, and in particular relates to an industrial steam production system for a pressurized water reactor nuclear power unit.

Background technique

At present, my country's industrial steam supply is dominated by thermal power plants and boiler rooms, and the fuel that can be used is still mainly coal. main cause of the effect. With the increasing number of nuclear power plants in my country and the continuous development of nuclear energy application technology, the multi-purpose application of nuclear energy, especially the nuclear energy heating technology, has become relatively mature. Many nuclear power plants at home and abroad have adopted the cogeneration method to provide heat for regional residents. However, At present, there are no nuclear power plants in my country that supply industrial steam to the outside world.

SUMMARY OF THE INVENTION

The technical problem to be solved by the present invention is to provide an industrial steam production system for a pressurized water reactor nuclear power unit, and propose a reasonable and feasible design scheme for the above-mentioned deficiencies in the prior art, so as to realize the clean external supply of the nuclear power plant. The application of industrial steam has opened up a new way of comprehensive utilization of nuclear energy.

The technical solution adopted to solve the technical problem of the present invention is to provide an industrial steam production system for a pressurized water reactor nuclear power unit, including:

Nuclear steam supply units, including pressurized water reactor nuclear power units, which provide heat source steam for industrial steam production units while generating electricity;

The inlet of the industrial steam production device is connected to the outlet of the nuclear steam supply device, and the heat source steam exchanges heat with the feed water introduced into the industrial steam production device. .

Preferably, the nuclear steam supply device further includes a backup heat source, and the industrial steam production device is further connected to the backup heat source, and the backup heat source is used to continuously supply the industrial steam production device with the backup heat source steam when the nuclear reactor of the nuclear steam supply device is out of operation.

Preferably, the outlet of the industrial steam production device is connected to the nuclear steam supply device, the heat source steam flows from the nuclear steam supply device into the industrial steam production device, and after heat exchange is completed, it becomes nuclear steam drain and flows back to the nuclear steam supply device.

Preferably, the pressurized water reactor nuclear power unit includes:

nuclear reactors, for heating coolant;

The steam generator is connected with the nuclear reactor. The steam generator is used to produce nuclear steam by using the coolant heated by the nuclear reactor. The steam generator is also connected with the industrial steam production device, and the heat source steam in the steam generator flows to the industrial steam production device;

The steam turbine is connected with the steam generator, and the steam turbine is used to convert part of the thermal energy of the nuclear steam into the rotational kinetic energy of the steam turbine;

The generator is connected to the steam turbine, and the generator generates electricity under the drive of the steam turbine;

The condenser, connected with the steam turbine, is used to condense the exhausted steam in the steam turbine into water, and the condenser is also connected with the steam generator. back to the steam generator.

Preferably, the industrial steam production plant comprises:

The preheater group is connected to the evaporator group, and the heat source steam and drain water flowing from the evaporator group flow into the preheater group to exchange heat with the feed water flowing into the preheater group, so that the heat flowing into the preheater group is heated. an increase in the temperature of the feed water;

The evaporator group is connected to the nuclear steam supply device, and the heat source steam flowing out of the nuclear steam supply device and the feed water flowing out of the preheater group exchange heat in the evaporator group, so that the temperature of the feed water flowing into the evaporator group is increased, and the industrial steam.

Preferably, the industrial steam production device further comprises:

The superheater is connected to the outlet of the industrial steam output from the evaporator group, and the superheater is used to further heat the industrial steam output from the evaporator group to a preset superheated temperature for transporting to the heat user.

Preferably, the superheater comprises: a superheater cold room and a superheater hot room that exchange heat with each other, the inlet of the superheater hot room is connected to the nuclear steam supply device, and the outlet of the superheater cold room is used for conveying industrial steam to the heat user;

The evaporator group includes:

The first-stage evaporator includes the first-stage evaporator cold room and the first-stage evaporator hot room that exchange heat with each other. Inlet connection of superheater cold room;

The secondary evaporator includes a secondary evaporator cold chamber and a secondary evaporator hot chamber that exchange heat with each other. The inlet of the secondary evaporator hot chamber is connected to the outlet of the primary evaporator hot chamber. The outlet is connected to the inlet of the cold room of the superheater;

The preheater group includes:

The first-stage preheater includes a first-stage preheater cold room and a first-stage preheater hot room that exchange heat with each other. The outlet of the cold chamber of the heater is connected with the inlet of the cold chamber of the secondary evaporator, and the outlet of the cold chamber of the primary preheater is also connected with the inlet of the cold chamber of the primary evaporator;

The secondary preheater includes a secondary preheater cold chamber and a secondary preheater hot chamber that exchange heat with each other. The inlet of the secondary preheater hot chamber is connected to the outlet of the primary preheater hot chamber. The outlet of the cold chamber of the preheater is connected with the inlet of the cold chamber of the primary preheater, and the inlet of the cold chamber of the secondary preheater is used to input feed water.

Preferably, the industrial steam production device further comprises:

For the deaerator used for deoxygenation of water supply, the inlet of the deaerator is connected with the outlet of the cold chamber of the secondary preheater, and the outlet of the deaerator is connected with the inlet of the cold chamber of the primary preheater.

Preferably, the outlet of the cold chamber of the superheater is connected to a deaerator for sending industrial steam into the deaerator, and the deaerator utilizes the industrial steam to deoxygenate the feed water.

Preferably, the industrial steam production device further comprises:

The radiation monitoring instrument is connected to the outlet of the superheater outputting the industrial steam, and the radiation monitoring instrument is used to monitor the radiation of the industrial steam.

Based on the pressurized water reactor nuclear power unit, the invention utilizes the secondary circuit main steam of the pressurized water reactor nuclear power unit to produce industrial steam through an industrial steam production device, and transports it to users through a steam pipe network, and proposes a complete, reasonable and feasible design scheme. The application of clean industrial steam supplied by nuclear power plants to the outside world has been realized, and a new way of comprehensive utilization of nuclear energy has been opened up. The pressurized water reactor nuclear power unit has the characteristics of stable operation and large heat production capacity. The industrial steam production system in the present invention supplies industrial steam to the outside, which can provide clean and efficient electric power and industrial steam while solving traditional energy sources such as coal combustion. It will bring about environmental pollution problems, improve the energy structure, ensure the steam demand for industrial development, and also help to improve the economic benefits of nuclear power plants.

Description of drawings

FIG. 1 is a schematic structural diagram of an industrial steam production system in Example 2 of the present invention.

In the picture: 1-nuclear steam supply device, 101-nuclear reactor, 102-steam generator, 103-main pump, 104-steam turbine, 105-condenser, 106-main feed water pump, 107-generator, 108-standby heat source ;2-Industrial steam production unit, 201-Pressure lift pump, 202-Secondary preheater, 203-Deaerator, 204-Feed water pump, 205-First-stage preheater, 206-Secondary evaporator, 207- Primary evaporator, 208-superheater, 209-radiation monitoring instrument, 210-regulating valve; 81-inlet of superheater hot room; 82-outlet of superheater hot room; 83-inlet of superheater cold room; 84- The outlet of the superheater cold room; 71- the inlet of the first-stage evaporator hot room; 72- the outlet of the first-stage evaporator hot room; 73- the inlet of the first-stage evaporator cold room; 74- the outlet of the first-stage evaporator cold room ; 61- the inlet of the hot chamber of the secondary evaporator; 62- the outlet of the hot chamber of the secondary evaporator; 63- the inlet of the cold chamber of the secondary evaporator; 64- the outlet of the cold chamber of the secondary evaporator; The inlet of the hot chamber of the heater; 52- the outlet of the hot chamber of the primary preheater; 53- the inlet of the cold chamber of the primary preheater; 54- the outlet of the cold chamber of the primary preheater; 21- the secondary preheater The inlet of the hot chamber; 22- the outlet of the hot chamber of the secondary preheater; 23- the inlet of the cold chamber of the secondary preheater; 24- the outlet of the cold chamber of the secondary preheater; 11- the main pipe; 12- the first Branch pipe; 13-Second branch pipe.

Detailed ways

In order to make those skilled in the art better understand the technical solutions of the present invention, the present invention will be further described in detail below with reference to the accompanying drawings and specific embodiments.

Embodiments of the present patent are described in detail below, examples of which are illustrated in the accompanying drawings, wherein the same or similar reference numerals refer to the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain the present patent, but should not be construed as a limitation on the present patent.

Example 1

This embodiment provides an industrial steam production system for a pressurized water reactor nuclear power unit, including:

Nuclear steam supply units, including pressurized water reactor nuclear power units, which provide heat source steam for industrial steam production units while generating electricity;

The inlet of the industrial steam production device is connected to the outlet of the nuclear steam supply device, and the heat source steam exchanges heat with the feed water introduced into the industrial steam production device. .

This embodiment is based on the pressurized water reactor nuclear power unit, and uses the secondary circuit main steam of the pressurized water reactor nuclear power unit to produce industrial steam through the industrial steam production device, and transport it to the user through the steam pipe network. A complete, reasonable and feasible design scheme is proposed , realizing the application of clean industrial steam supplied by nuclear power plants to the outside world, and opening up a new way of comprehensive utilization of nuclear energy. The pressurized water reactor nuclear power unit has the characteristics of stable operation and large heat production capacity. By supplying industrial steam to the outside through the industrial steam production system in this embodiment, it can provide clean and efficient electric power and industrial steam while solving the traditional problems such as coal burning. The problem of environmental pollution caused by energy, improving the energy structure and ensuring the steam demand for industrial development will also help to improve the economic benefits of nuclear power plants.

Example 2

As shown in FIG. 1 , this embodiment provides an industrial steam production system for a pressurized water reactor nuclear power unit, including:

The nuclear steam supply device 1 includes a pressurized water reactor nuclear power unit, and the pressurized water reactor nuclear power unit provides heat source steam for the industrial steam production unit 2 while generating electricity;

The industrial steam production device 2, the inlet of which is connected to the outlet of the nuclear steam supply device 1, the heat source steam exchanges heat with the feed water introduced into the industrial steam production device 2, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters, which is used for transportation To heat users, the nuclear power unit can supply industrial steam.

Preferably, the nuclear steam supply device 1 further includes a backup heat source 108, and the industrial steam production device 2 is also connected to the backup heat source 108, and the backup heat source 108 is used to supply the industrial steam production device to the industrial steam production device when the nuclear reactor 101 of the nuclear steam supply device 1 is out of operation. 2. Continuously supply the standby heat source 108 steam to ensure the continuous supply of industrial steam.

Preferably, the outlet of the industrial steam production device 2 is connected to the nuclear steam supply device 1, and the heat source steam flows from the nuclear steam supply device 1 into the industrial steam production device 2. After the heat exchange is completed, it becomes a nuclear steam drain and flows back to the nuclear steam supply device. 1. The heat source steam circulates between the nuclear steam supply device 1 and the industrial steam production device 2 .

Preferably, the pressurized water reactor nuclear power unit includes:

nuclear reactor 101 for heating coolant;

The steam generator 102 is connected to the nuclear reactor 101. The steam generator 102 is used for producing nuclear steam by using the coolant heated by the nuclear reactor 101. The steam generator 102 is also connected to the industrial steam production device 2. The heat source steam in the steam generator 102 flows to the Industrial steam production device 2; the pressurized water reactor nuclear power unit further includes a main pump 103, and the main pump 103 is provided on the pipeline between the nuclear reactor 101 and the steam generator 102, and the main pump 103 is used to provide power for the closed circulation of the coolant . The high-temperature coolant heated by the nuclear reactor 101 is sent into the steam generator 102 through the pipeline, flows out from the steam generator 102 after heat exchange, and flows into the main pump 103 through the pipeline to increase the kinetic energy, and then flows back to the nuclear reactor 101 through the pipeline to form a closed cycle loop.

The steam turbine 104 is connected to the steam generator 102, and the steam turbine 104 is used to convert a part of the thermal energy of the nuclear steam into the rotational kinetic energy of the steam turbine 104; another part of the nuclear steam is sent to the industrial steam production device 2 through a pipeline to provide heat source steam for steam conversion .

The generator 107 is connected to the steam turbine 104. The generator 107 generates electricity under the driving of the steam turbine 104, converts kinetic energy into electrical energy, and the nuclear steam becomes spent steam after performing work in the steam turbine 104;

The condenser 105 is connected to the steam turbine 104, and the condenser 105 is also connected to the steam generator 102. The condenser 105 is used to condense the exhausted steam that has completed the work in the steam turbine 104 into water, and the condensed water of the exhausted steam is pumped through the steam turbine 104. The steam is heated and boosted by the main feed pump 106 before flowing back to the steam generator 102 . The condenser 105 is also connected with the industrial steam production device 2, and is used for collecting the nuclear steam draining after heat exchange in the industrial steam production device 2. The pressurized water reactor nuclear power plant also includes a main feed water pump 106, which is provided on the pipeline between the condenser 105 and the steam generator 102, and the main feed water pump 106 is a nuclear steam generator in the nuclear steam supply device 1. The mass circulation provides kinetic energy to form a closed loop.

Preferably, the industrial steam production device 2 includes:

The preheater group is connected to the evaporator group, and the heat source steam and drain water flowing from the evaporator group flow into the preheater group to exchange heat with the feed water flowing into the preheater group, so that the heat flowing into the preheater group is heated. an increase in the temperature of the feed water;

The evaporator group is connected to the nuclear steam supply device 1, and the heat source steam flowing out of the nuclear steam supply device 1 exchanges heat with the feed water flowing out of the preheater group in the evaporator group, so that the temperature of the feed water flowing into the evaporator group increases , get industrial steam.

Preferably, the industrial steam production device 2 further comprises:

The superheater 208 is connected to the outlet of the industrial steam output from the evaporator group, and the superheater 208 is used to further heat the industrial steam output from the evaporator group to a preset superheated temperature for delivery to the heat user.

Preferably, the superheater 208 includes: a superheater cold room and a superheater hot room that exchange heat with each other, the inlet 81 of the superheater hot room is connected to the nuclear steam supply device 1, and the outlet 84 of the superheater cold room is used for conveying industrial steam to hot users;

The evaporator group includes:

The primary evaporator 207 includes a primary evaporator cold room and a primary evaporator hot room that exchange heat with each other, the inlet 71 of the primary evaporator hot room is connected to the outlet 82 of the superheater hot room, and the primary evaporator cold room The outlet 74 of the superheater is connected to the inlet 83 of the cold chamber of the superheater; the primary evaporator 207 produces industrial steam for nuclear steam. The heat source steam flows from the superheater 208 into the primary evaporator 207 .

The secondary evaporator 206 includes a secondary evaporator cold chamber and a secondary evaporator hot chamber that exchange heat with each other. The inlet 61 of the secondary evaporator hot chamber is connected to the outlet 72 of the primary evaporator hot chamber. The secondary evaporator The outlet 64 of the cold chamber is connected to the inlet 83 of the cold chamber of the superheater; the secondary evaporator 206 produces industrial steam for nuclear steam drainage.

The preheater group includes:

The primary preheater 205 includes a primary preheater cold room and a primary preheater hot room that exchange heat with each other, the inlet 51 of the primary preheater hot room is connected to the outlet 62 of the secondary evaporator hot room, The outlet 54 of the cold chamber of the primary preheater is connected to the inlet 63 of the cold chamber of the secondary evaporator, and the outlet 54 of the cold chamber of the primary preheater is also connected to the inlet 73 of the cold chamber of the primary evaporator;

The secondary preheater 202 includes a secondary preheater cold chamber and a secondary preheater hot chamber that exchange heat with each other. The inlet 21 of the secondary preheater hot chamber is connected to the outlet 52 of the primary preheater hot chamber. , the outlet 24 of the cold chamber of the secondary preheater is connected to the inlet 53 of the cold chamber of the primary preheater, and the inlet 23 of the cold chamber of the secondary preheater is used to input feed water.

The steam generator 102 is connected to the inlet 81 of the superheater hot chamber, and the backup heat source 108 is connected to the inlet 81 of the superheater hot chamber. Specifically, the inlet 81 of the heat chamber of the superheater is connected to the output end of the main pipe 11, and the input end of the main pipe 11 is respectively connected to the first branch pipe 12 and the second branch pipe 13, the first branch pipe 12 is connected to the steam generator 102, and the second branch pipe 13 is connected to a backup heat source 108 . The industrial steam production device 2 further includes a regulating valve 210 , which is provided on the main pipe 11 . The regulating valve 210 adjusts the amount of heat source steam extracted from the nuclear steam supply device 1 according to the required industrial steam parameters and flow requirements.

The superheater 208 utilizes the heat of the heat source steam to superheat the saturated industrial steam to meet the heat grid delivery requirements.

Specifically, the industrial steam production device 2 further includes: a pressure lift pump 201, and a pressure lift pump 201 is further provided on the pipeline connected to the inlet 23 of the cold chamber of the secondary preheater. The pressure lift pump 201 is used to transport the demineralized water to the industrial steam production device 2, and continuously provide the feed water required for the production of industrial steam.

Specifically, the condenser 105 in this embodiment is connected to the outlet 22 of the hot chamber of the secondary preheater. The nuclear steam after heat exchange in the industrial steam production device 2 flows into the condenser 105 through the outlet 22 of the heat chamber of the secondary preheater.

Preferably, the industrial steam production device 2 further comprises:

The deaerator 203 for deoxygenation, the inlet of the deaerator 203 is connected to the outlet 24 of the cold chamber of the secondary preheater, and the outlet of the deaerator 203 is connected to the inlet 53 of the cold chamber of the primary preheater.

Preferably, the outlet 84 of the cold room of the superheater is connected to the deaerator 203, the industrial steam flows into the deaerator 203 from the outlet 84 of the cold room of the superheater, and the deaerator 203 uses the industrial steam produced by the industrial steam production device 2. Deoxygenate the water. The water tank of the deaerator 203 can ensure the feed water consumption of the primary evaporator 207 and the secondary evaporator 206 for a certain period of time.

Specifically, the industrial steam production device 2 further includes: a feed water pump 204 , and a feed water pump 204 is provided on the pipeline between the inlet 53 of the cold chamber of the primary preheater and the deaerator 203 . The feed water pump 204 is used to deliver the feed water to the primary preheater 205 to provide kinetic energy for the feed water.

Preferably, the industrial steam production device 2 further comprises:

The radiation monitoring instrument 209 is connected to the outlet of the superheater 208 for outputting the industrial steam, and the radiation monitoring instrument 209 is used for monitoring the radiation of the industrial steam. The radiation monitoring instrument 209 is arranged on the pipe connected to the outlet of the superheater 208 for outputting industrial steam. The industrial steam flows out from the industrial steam outlet of the superheater 208, and first flows through the radiation monitoring instrument 209, and then is sent to the user's heat network after monitoring that there is no radioactivity. Prevent radioactive material from being released to the user side.

The primary evaporator 207 uses the heat of the heat source steam to heat part of the feed water from the primary preheater 205 to generate the required industrial steam. The secondary evaporator 206 uses the heat of the heat source steam drain to heat another part of the feed water from the primary preheater 205 to generate the required industrial steam. The industrial steam generated by the primary evaporator 207 and the secondary evaporator 206 is collected and transported to the superheater 208 through a pipeline.

The primary preheater 205 utilizes the drain of the heat source steam to heat the feed water provided by the feed water pump 204 to meet the requirements of the primary evaporator 207 and the secondary evaporator 206 for the feed water temperature; the heat source steam drain is replaced by the primary preheater 205 After it is heated, it continues to enter the secondary preheater 202, and the secondary preheater 202 uses the hydrophobicity of the heat source steam to preheat the feed water again, so as to realize the step-by-step utilization of the heat of the heat source steam.

The primary evaporator 207 and the secondary evaporator 206 use the heat source steam and the heat of the drain to heat the feed water from the primary preheater 205 to generate the required saturated industrial steam; the primary evaporator 207 produces industrial steam for nuclear steam, and the secondary evaporator 207 produces industrial steam for nuclear steam. The evaporator 206 is used for nuclear steam drainage to produce industrial steam, making full use of the heat of the high-parameter heat source steam, so that the dewatering temperature of the heat source steam after passing through the primary preheater 205 and the secondary preheater 202 is effectively reduced, and the efficiency of the industrial steam production system is improved. Thermal efficiency.

The industrial steam production system for the pressurized water reactor nuclear power unit in this embodiment satisfies the relevant requirements for preventing the migration of radionuclides from the nuclear power plant to the heating device in the "Nuclear Power Plant Design Safety Regulations" (HAF102).

The industrial steam production system for the pressurized water reactor nuclear power unit in this embodiment utilizes the power generation of the nuclear power unit to produce clean industrial steam at the same time, thereby realizing the comprehensive utilization of nuclear energy.

The beneficial effects of the industrial steam production system for the pressurized water reactor nuclear power unit of this embodiment are:

(1) In this embodiment, the main steam of the secondary circuit of the pressurized water reactor nuclear power unit is used to produce and supply industrial steam through the steam conversion equipment, and the steam conversion technology is used to transfer heat from the radioactive primary circuit of the pressurized water reactor nuclear power unit to the secondary circuit of the pressurized water reactor nuclear power unit. The heat is transferred from the secondary circuit to the industrial steam tertiary circuit, which realizes the double isolation of the circuit, and through the reasonable setting of the radioactivity monitoring device, prevents the radionuclide from the nuclear power plant from migrating to the outside of the nuclear power plant.

(2) This embodiment provides a design scheme for the production and supply of industrial steam for the pressurized water reactor nuclear power unit, which solves the problem of environmental pollution caused by traditional energy sources such as coal and gas, improves my country's energy structure, and guarantees clean energy required for industrial development. efficient way of supply.

It can be understood that the above embodiments are only exemplary embodiments adopted to illustrate the principle of the present invention, but the present invention is not limited thereto. For those skilled in the art, without departing from the spirit and essence of the present invention, various modifications and improvements can be made, and these modifications and improvements are also regarded as the protection scope of the present invention.

Claims (10)

1. an industrial steam production system for pressurized water reactor nuclear power unit, is characterized in that, comprises: Nuclear steam supply units, including pressurized water reactor nuclear power units, which provide heat source steam for industrial steam production units while generating electricity; The inlet of the industrial steam production device is connected to the outlet of the nuclear steam supply device, and the heat source steam exchanges heat with the feed water introduced into the industrial steam production device. . 2. The industrial steam production system for a pressurized water reactor nuclear power unit according to claim 1, wherein the nuclear steam supply device further comprises a backup heat source, and the industrial steam production device is also connected with the backup heat source, and the backup heat source is used in the When the nuclear reactor of the nuclear steam supply unit is out of operation, the standby heat source steam is continuously supplied to the industrial steam production unit. 3. The industrial steam production system for a pressurized water reactor nuclear power unit according to claim 1, wherein the outlet of the industrial steam production device is connected to the nuclear steam supply device, and the heat source steam flows into the industrial steam production from the nuclear steam supply device After the heat exchange is completed, it becomes the nuclear steam drain and flows back to the nuclear steam supply device. 4. The industrial steam production system for a pressurized water reactor nuclear power unit according to claim 1, wherein the pressurized water reactor nuclear power unit comprises: nuclear reactors, for heating coolant; The steam generator is connected with the nuclear reactor. The steam generator is used to produce nuclear steam by using the coolant heated by the nuclear reactor. The steam generator is also connected with the industrial steam production device, and the heat source steam in the steam generator flows to the industrial steam production device; The steam turbine is connected with the steam generator, and the steam turbine is used to convert part of the thermal energy of the nuclear steam into the rotational kinetic energy of the steam turbine; The generator is connected to the steam turbine, and the generator generates electricity under the drive of the steam turbine; The condenser, connected with the steam turbine, is used to condense the exhausted steam in the steam turbine into water, and the condenser is also connected with the steam generator. back to the steam generator. 5. The industrial steam production system for a pressurized water reactor nuclear power unit according to any one of claims 1 to 4, wherein the industrial steam production device comprises: The preheater group is connected to the evaporator group, and the heat source steam flowing out of the evaporator group drains into the preheater group and exchanges heat with the feed water passed into the preheater group, so that the feed water passed into the preheater group temperature rise; The evaporator group is connected to the nuclear steam supply device, and the heat source steam flowing out of the nuclear steam supply device and the feed water flowing out of the preheater group exchange heat in the evaporator group, so that the temperature of the feed water flowing into the evaporator group increases, obtaining industrial steam. 6. The industrial steam production system for a pressurized water reactor nuclear power unit according to claim 5, wherein the industrial steam production device further comprises: The superheater is connected to the outlet of the industrial steam output from the evaporator group, and the superheater is used to further heat the industrial steam output from the evaporator group to a preset superheated temperature for transporting to the heat user. 7. The industrial steam production system for a pressurized water reactor nuclear power plant according to claim 6, wherein, The superheater includes: a superheater cold room and a superheater hot room that exchange heat with each other, the inlet of the superheater hot room is connected to the nuclear steam supply device, and the outlet of the superheater cold room is used to transport industrial steam to heat users; The evaporator group includes: The first-stage evaporator includes the first-stage evaporator cold room and the first-stage evaporator hot room that exchange heat with each other. Inlet connection of superheater cold room; The secondary evaporator includes a secondary evaporator cold chamber and a secondary evaporator hot chamber that exchange heat with each other. The inlet of the secondary evaporator hot chamber is connected to the outlet of the primary evaporator hot chamber. The outlet is connected to the inlet of the cold room of the superheater; The preheater group includes: The first-stage preheater includes a first-stage preheater cold room and a first-stage preheater hot room that exchange heat with each other. The outlet of the cold chamber of the heater is connected with the inlet of the cold chamber of the secondary evaporator, and the outlet of the cold chamber of the primary preheater is also connected with the inlet of the cold chamber of the primary evaporator; The secondary preheater includes a secondary preheater cold chamber and a secondary preheater hot chamber that exchange heat with each other. The inlet of the secondary preheater hot chamber is connected to the outlet of the primary preheater hot chamber. The outlet of the cold chamber of the preheater is connected with the inlet of the cold chamber of the primary preheater, and the inlet of the cold chamber of the secondary preheater is used to input feed water. 8. The industrial steam production system for a pressurized water reactor nuclear power unit according to claim 7, wherein the industrial steam production device further comprises: For the deaerator used for deoxygenation of water supply, the inlet of the deaerator is connected with the outlet of the cold chamber of the secondary preheater, and the outlet of the deaerator is connected with the inlet of the cold chamber of the primary preheater. 9. The industrial steam production system for a pressurized water reactor nuclear power unit according to claim 8, wherein the outlet of the cold chamber of the superheater is connected to the deaerator, and is used for sending the industrial steam into the deaerator, The deaerator utilizes industrial steam to deoxygenate the feed water. 10. The industrial steam production system for a pressurized water reactor nuclear power plant according to claim 6, wherein the industrial steam production device further comprises: The radiation monitoring instrument is connected to the outlet of the superheater outputting the industrial steam, and the radiation monitoring instrument is used to monitor the radiation of the industrial steam.

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