CN111834026B - Industrial steam production system for pressurized water reactor nuclear power unit - 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, and the pressurized water reactor nuclear power unit provides heat source steam for the industrial steam production device while generating electricity ; The industrial steam production device, its inlet is connected with the outlet of the nuclear steam supply device, the heat source steam exchanges heat with the feed water fed 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 to transport to the heat source user. Relying on the PWR nuclear power unit, the present invention uses the main steam of the secondary circuit of the PWR nuclear power unit to produce industrial steam through the industrial steam production device, and transports it to the user through the steam pipe network, realizing the application of the nuclear power plant to supply clean industrial steam to the outside world. It has opened up a new way of comprehensive utilization of nuclear energy, effectively solved the environmental pollution caused by coal-burning and other traditional energy sources, 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 used for pressurized water reactor nuclear power units.

Background technique

At present, my country's industrial steam supply is mainly based on thermal power plants and boiler rooms, and the fuel that can be used is still mainly coal, while coal-fired emissions of dust, sulfide, nitrogen oxides and carbon dioxide are responsible for air pollution, smog and greenhouses. main reason for the effect. With the increasing number of nuclear power units in my country and the continuous development of nuclear energy application technology, the multi-purpose application of nuclear energy, especially nuclear energy heating technology, has become relatively mature. Many nuclear power units at home and abroad have adopted cogeneration to provide heat for regional residents. However, At present, there is no nuclear power plant in my country that supplies industrial steam to the outside world.

Contents of the invention

The technical problem to be solved by the present invention is to provide an industrial steam production system for pressurized water reactor nuclear power units in view of the above-mentioned deficiencies in the prior art, and propose a reasonable and feasible design scheme, which realizes the clean supply of nuclear power plants 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 problems described in the present invention is to provide a kind of industrial steam production system for pressurized water reactor nuclear power unit, comprising:

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

The industrial steam production device, its inlet is connected with the outlet of the nuclear steam supply device, the heat source steam exchanges heat with the feed water fed into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for delivery to heat users .

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

Preferably, 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 device from the nuclear steam supply device, and after the 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 the coolant;

The steam generator is connected to the nuclear reactor, and the steam generator is used to produce nuclear steam by using the coolant heated by the nuclear reactor. The steam generator is also connected to 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 heat energy of the nuclear steam into the rotational kinetic energy of the steam turbine;

The generator is connected with 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 exhaust steam that has done work in the steam turbine into water. The condenser is also connected with the steam generator. Flow back to the steam generator.

Preferably, the industrial steam production plant comprises:

The preheater group is connected with the evaporator group. The heat source steam and drain flowing out of the evaporator group flow into the preheater group to exchange heat with the feed water passing into the preheater group, so that the water passing into the preheater group The temperature of the feed water rises;

The evaporator group is connected to the nuclear steam supply device. 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, and the industrial steam.

Preferably, the industrial steam production device also includes:

The superheater is connected to the outlet of the industrial steam output by the evaporator group, and the superheater is used to further heat the industrial steam output by the evaporator group to a preset superheating temperature for delivery to heat users.

Preferably, the superheater includes: a superheater cold room and a superheater hot room exchanging 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 primary evaporator, including the primary evaporator cold room and the primary evaporator hot room that exchange heat with each other, the inlet of the primary evaporator hot room is connected with the outlet of the superheater hot room, and the outlet of the primary evaporator cold room Inlet connection to the cold chamber of the superheater;

Secondary evaporator, including mutual heat exchange secondary evaporator cold room, secondary evaporator hot room, the inlet of the second evaporator hot room is connected with the outlet of the first evaporator hot room, the second evaporator cold room The outlet is connected to the inlet of the cold chamber of the superheater;

The preheater group includes:

The first-stage preheater includes the first-stage preheater cold chamber and the first-stage preheater hot chamber that exchange heat with each other. The inlet of the first-stage preheater hot chamber is connected to the outlet of the second-stage evaporator hot chamber. 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, including the secondary preheater cold chamber and the secondary preheater hot chamber that exchange heat with each other, the inlet of the secondary preheater hot chamber is connected with the outlet of the primary preheater hot chamber, and the secondary The outlet of the cold chamber of the preheater is connected to the inlet of the cold chamber of the primary preheater, and the inlet of the cold chamber of the secondary preheater is used for inputting feed water.

Preferably, the industrial steam production device also includes:

A deaerator used for deaeration of feed water, the inlet of the deaerator is connected to the outlet of the cold room of the secondary preheater, and the outlet of the deaerator is connected to the inlet of the cold room of the first preheater.

Preferably, the outlet of the cold room of the superheater is connected to the 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 also includes:

The radiation monitoring instrument is connected with the outlet of the industrial steam output by the superheater, 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 present invention uses the main steam of the secondary circuit of the pressurized water reactor nuclear power unit to produce industrial steam through the industrial steam production device, and transports it to the user through the steam pipe network, and proposes a complete, reasonable and feasible design scheme. It has realized the application of nuclear power plants to supply clean industrial steam to the outside world, and opened 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. The industrial steam production system in the present invention supplies industrial steam to the outside world, which can solve the problem of traditional energy sources such as coal burning while providing clean and efficient electric energy and industrial steam. The environmental pollution problems brought about by it can improve the energy structure, ensure the steam demand of 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 figure: 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-backup heat source ;2- industrial steam production device, 201- pressure lift pump, 202- secondary preheater, 203- deaerator, 204- feed water pump, 205- primary preheater, 206- secondary evaporator, 207- Primary evaporator, 208-superheater, 209-radiation monitoring instrument, 210-regulating valve; 81-inlet of superheater heat chamber; 82-exit of superheater heat chamber; 83-inlet of superheater cold chamber; 84- Outlet of superheater cold chamber; 71-inlet of primary evaporator hot chamber; 72-outlet of primary evaporator hot chamber; 73-inlet of primary evaporator cold chamber; 74-outlet of primary evaporator cold chamber ; 61-inlet of the heat chamber of the secondary evaporator; 62-outlet of the heat chamber of the secondary evaporator; 63-inlet of the cold chamber of the secondary evaporator; 64-outlet of the cold chamber of the secondary evaporator; The inlet of the heat chamber of the heater; 52-the outlet of the heat chamber of the first-stage preheater; 53-the inlet of the cold chamber of the first-stage preheater; 54-the outlet of the cold chamber of the first-stage preheater; 21-the outlet of the second-stage preheater Inlet of hot chamber; 22-outlet of hot chamber of secondary preheater; 23-inlet of cold chamber of secondary preheater; 24-outlet of cold chamber of secondary preheater; 11-main pipe; 12-first Branch pipe; 13-the second branch pipe.

Detailed ways

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

Embodiments of the present patent are described in detail below, examples of which are shown in the drawings, wherein the same or similar reference numerals designate the same or similar elements or elements having the same or similar functions throughout. The embodiments described below by referring to the figures are exemplary and are only used for explaining the patent, and should not be construed as limiting the patent.

Example 1

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

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

The industrial steam production device, its inlet is connected with the outlet of the nuclear steam supply device, the heat source steam exchanges heat with the feed water fed into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for delivery to heat users .

This example relies on the PWR nuclear power unit, uses the main steam of the secondary circuit of the PWR nuclear power unit to produce industrial steam through the industrial steam production device, and transports it to the user through the steam pipe network, and proposes a complete, reasonable and feasible design scheme , realized the application of clean industrial steam supplied by nuclear power plants, and opened 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. The industrial steam production system in this embodiment supplies industrial steam to the outside world, while providing clean and efficient electric energy and industrial steam, it can solve traditional problems such as coal burning. Environmental pollution problems caused by energy, improving the energy structure, ensuring the steam demand for industrial development, and also helping to improve the economic benefits of nuclear power plants.

Example 2

As shown in Figure 1, the present embodiment provides a kind of industrial steam production system for the pressurized water reactor nuclear power unit, comprising:

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 device 2 while generating electricity;

Industrial steam production device 2, the inlet of which is connected to the outlet of nuclear steam supply device 1, the heat source steam exchanges heat with the feed water fed 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 for transportation To heat users, to realize the supply of industrial steam for nuclear power units.

Preferably, nuclear steam supply device 1 also includes backup heat source 108, and industrial steam production device 2 is also connected with backup heat source 108, and backup heat source 108 is used for when the nuclear reactor 101 of nuclear steam supply device 1 shuts down, to industrial steam production device 2 Continuous supply of steam from backup heat source 108 to ensure 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 into the industrial steam production device 2 from the nuclear steam supply device 1, and after the heat exchange is completed, the nuclear steam becomes hydrophobic and flows back to the nuclear steam supply device 1. The heat source steam circulates between the nuclear steam supply unit 1 and the industrial steam production unit 2 .

Preferably, the pressurized water reactor nuclear power unit includes:

nuclear reactor 101 for heating the coolant;

Steam generator 102, is connected with nuclear reactor 101, and steam generator 102 is used for utilizing the coolant that nuclear reactor 101 has been heated to produce nuclear steam, and steam generator 102 is also connected with industrial steam production device 2, and the heat source steam in steam generator 102 flows to Industrial steam production device 2; the pressurized water reactor nuclear power unit also includes a main pump 103, which is provided with a main pump 103 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 cycle 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, flows into the main pump 103 through the pipeline to increase kinetic energy, and flows back to the nuclear reactor 101 through the pipeline to form a closed cycle circuit.

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

Generator 107 is connected with steam turbine 104, and generator 107 generates electricity under the drive of steam turbine 104, and kinetic energy is converted into electric energy, and nuclear steam becomes exhausted steam after doing work in steam turbine 104;

The condenser 105 is connected with the steam turbine 104, and the condenser 105 is also connected with the steam generator 102. The condenser 105 is used to condense the exhausted steam in the steam turbine 104 into water, and the exhausted steam condensed water is extracted by the steam turbine 104. The steam is heated and pressurized by the main feed water pump 106 and then flows back to the steam generator 102 . The condenser 105 is also connected with the industrial steam production device 2, and is used for collecting nuclear steam drained after heat exchange in the industrial steam production device 2. The pressurized water reactor nuclear power unit also includes a main feed water pump 106, which is provided with a main feed water pump 106 on the pipeline between the condenser 105 and the steam generator 102. The mass circulation provides kinetic energy to form a closed loop.

Preferably, the industrial steam production device 2 includes:

The preheater group is connected with the evaporator group. The heat source steam and drain flowing out of the evaporator group flow into the preheater group to exchange heat with the feed water passing into the preheater group, so that the water passing into the preheater group The temperature of the feed water rises;

The evaporator group is connected to the nuclear steam supply device 1. The heat source steam flowing out of the nuclear steam supply device 1 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 , get industrial steam.

Preferably, the industrial steam production device 2 also includes:

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

Preferably, the superheater 208 includes: a superheater cold room and a superheater hot room exchanging 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 to transport industrial steam to hot users;

The evaporator group includes:

The primary evaporator 207 includes a primary evaporator cold chamber and a primary evaporator hot chamber that exchange heat with each other. The inlet 71 of the primary evaporator thermal chamber is connected to the outlet 82 of the superheater thermal chamber. The primary evaporator cold chamber 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 into the primary evaporator 207 from the superheater 208 .

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

The preheater group includes:

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

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

The steam generator 102 is connected to the inlet 81 of the superheater chamber, and the backup heat source 108 is connected to the inlet 81 of the superheater chamber. Specifically, the inlet 81 of the hot 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 with standby heat source 108. The industrial steam production device 2 also includes: a regulating valve 210. The regulating valve 210 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 transmission demand of the heat network.

Specifically, the industrial steam production device 2 further includes: a pressure lift pump 201, and a pressure lift pump 201 is also 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 deliver the desalted water to the industrial steam production device 2 to continuously provide the feed water required for generating industrial steam.

Specifically, the condenser 105 in this embodiment is connected to the outlet 22 of the heat chamber of the secondary preheater. The nuclear steam drained 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 also includes:

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

Preferably, the outlet 84 of the cold chamber of the superheater is connected to the deaerator 203, and industrial steam flows into the deaerator 203 by the outlet 84 of the cold chamber of the superheater, and the deaerator 203 utilizes the industrial steam produced by the industrial steam production device 2 Deoxygenate feed water. The water tank of the deaerator 203 can guarantee 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 the 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 also includes:

The radiation monitoring instrument 209 is connected with the outlet of the superheater 208 outputting the industrial steam, and the radiation monitoring instrument 209 is used to monitor the radiation of the industrial steam. The radiation monitoring instrument 209 is set on the pipeline connected to the outlet of the superheater 208 to output 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. After monitoring that there is no radioactivity, it is sent to the user's heating network. Prevent the release of radioactive material 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 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 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 pipelines.

The first-stage preheater 205 heats the feed water provided by the feedwater pump 204 by using the drainage of the heat source steam to meet the requirements for the feed water temperature of the first-stage evaporator 207 and the second-stage evaporator 206; After heating, 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 gradual utilization of the heat of the heat source steam.

The primary evaporator 207 and the secondary evaporator 206 heat the feed water from the primary preheater 205 by using heat source steam and water-repellent heat to generate the required saturated industrial steam; the primary evaporator 207 produces industrial steam for nuclear steam, and the secondary The evaporator 206 produces industrial steam for nuclear steam drainage, and makes full use of the heat of the high-parameter heat source steam to effectively reduce the drainage temperature of the heat source steam after passing through the primary preheater 205 and the secondary preheater 202, improving the efficiency of the industrial steam production system. Thermal efficiency.

The industrial steam production system used in the pressurized water reactor nuclear power unit in this embodiment meets the relevant requirements in the "Nuclear Power Plant Design Safety Regulations" (HAF102) to prevent radionuclides from migrating from the nuclear power plant to the heating device.

The industrial steam production system used in 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, 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 the present 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 second circuit. The circuit is then transferred from the secondary circuit to the third circuit of industrial steam, which realizes the double isolation of the circuit, and prevents the migration of radionuclides from the nuclear power plant to the outside of the nuclear power plant through the reasonable setting of the radioactive monitoring device.

(2) This embodiment provides a design scheme for the production and supply of industrial steam for pressurized water reactor nuclear power units, which is to solve the environmental pollution problems caused by traditional energy sources such as coal and gas, improve my country's energy structure, and ensure the clean energy required for industrial development effective means of supply.

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

Claims (7)

1. An industrial steam production system for pressurized water reactor nuclear power units, characterized in that, comprising: Nuclear steam supply devices, including pressurized water reactor nuclear power units, which provide heat source steam for industrial steam production devices while generating electricity; The industrial steam production device, its inlet is connected with the outlet of the nuclear steam supply device, the heat source steam exchanges heat with the feed water fed into the industrial steam production device, and the feed water is heated by the heat source steam to generate industrial steam with preset parameters for delivery to heat users ; Industrial steam production units include: The preheater group is connected with the evaporator group. The heat source steam flowing out of the evaporator group drains into the preheater group to exchange heat with the feed water passing into the preheater group, so that the feed water passing into the preheater group temperature rise; The evaporator group is connected to the nuclear steam supply device. 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, and the obtained industrial steam; Industrial steam production units also include: The superheater is connected to the outlet of the industrial steam output by the evaporator group, and the superheater is used to further heat the industrial steam output by the evaporator group to a preset superheating temperature for delivery to heat users; 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 primary evaporator, including the primary evaporator cold room and the primary evaporator hot room that exchange heat with each other, the inlet of the primary evaporator hot room is connected with the outlet of the superheater hot room, and the outlet of the primary evaporator cold room Inlet connection to the cold chamber of the superheater; Secondary evaporator, including mutual heat exchange secondary evaporator cold room, secondary evaporator hot room, the inlet of the second evaporator hot room is connected with the outlet of the first evaporator hot room, the second evaporator cold room The outlet is connected to the inlet of the cold chamber of the superheater; The preheater group includes: The first-stage preheater includes the first-stage preheater cold chamber and the first-stage preheater hot chamber that exchange heat with each other. The inlet of the first-stage preheater hot chamber is connected to the outlet of the second-stage evaporator hot chamber. 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, including the secondary preheater cold chamber and the secondary preheater hot chamber that exchange heat with each other, the inlet of the secondary preheater hot chamber is connected with the outlet of the primary preheater hot chamber, and the secondary The outlet of the cold chamber of the preheater is connected to the inlet of the cold chamber of the primary preheater, and the inlet of the cold chamber of the secondary preheater is used for inputting feed water. 2. the industrial steam production system for pressurized water reactor nuclear power unit according to claim 1, is characterized in that, nuclear steam supply device also comprises standby heat source, and industrial steam production device is also connected with standby heat source, and standby heat source is used for When the nuclear reactor of the nuclear steam supply device is out of service, the backup heat source steam is continuously supplied to the industrial steam production device. 3. the industrial steam production system for pressurized water reactor nuclear power unit according to claim 1, is characterized in that, the outlet of industrial steam production device is connected with nuclear steam supply device, and heat source steam flows into industrial steam production by nuclear steam supply device After the heat exchange is completed, it becomes nuclear steam drain, and flows back to the nuclear steam supply device. 4. the industrial steam production system for pressurized water reactor nuclear power unit according to claim 1, is characterized in that, pressurized water reactor nuclear power unit comprises: Nuclear reactors, for heating the coolant; The steam generator is connected to the nuclear reactor, and the steam generator is used to produce nuclear steam by using the coolant heated by the nuclear reactor. The steam generator is also connected to 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 heat energy of the nuclear steam into the rotational kinetic energy of the steam turbine; The generator is connected with 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 exhaust steam that has done work in the steam turbine into water. The condenser is also connected with the steam generator. Flow back to the steam generator. 5. the industrial steam production system for pressurized water reactor nuclear power unit according to claim 1, is characterized in that, industrial steam production device also comprises: A deaerator used for deaeration of feed water, the inlet of the deaerator is connected to the outlet of the cold room of the secondary preheater, and the outlet of the deaerator is connected to the inlet of the cold room of the first preheater. 6. the industrial steam production system for pressurized water reactor nuclear power unit according to claim 5, is characterized in that, the cold room outlet of superheater is connected with deaerator, is used for sending industrial steam into deaerator, Deaerators utilize industrial steam to deaerate feed water. 7. the industrial steam production system for pressurized water reactor nuclear power unit according to claim 1, is characterized in that, industrial steam production device also comprises: The radiation monitoring instrument is connected with the outlet of the industrial steam output by the superheater, and the radiation monitoring instrument is used to monitor the radiation of the industrial steam.

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