A method of supplying steam for a nuclear power plant

Abstract

The application discloses a steam supply method for a heat supply pipe network, and comprises the following steps: S02, saturated steam with a pressure of 5.0 MPa or below generated by a pressurized water reactor through a first steam generator and then through a first heat exchanger to generate medium and low pressure saturated steam with a pressure of 5.0 MPa or below; S03, after the medium and low pressure saturated steam is superheated by main steam of a high-temperature gas cooled reactor, medium and low pressure superheated steam is generated and then supplied to a user end through a long-distance pipe network; and S04, superheated steam with a pressure of 14.1 MPa generated by the high-temperature gas cooled reactor through a second steam generator and then through a second heat exchanger to generate medium and high pressure superheated steam, which is then supplied to the user end through the long-distance pipe network. In the application, the steam supply system fully utilizes the characteristics that the high-temperature gas cooled reactor has high steam parameters but small quantity and the pressurized water reactor has low steam parameters but large quantity, adopts a combined steam supply mode of the high-temperature gas cooled reactor and the pressurized water reactor, can realize the effect of multi-parameter and long-distance industrial steam supply, provides an industrial steam decarburization solution for high-energy-consumption enterprises, and solves the limitation caused by the carbon emission pressure.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of industrial steam supply, in particular to a steam supply method of a multi-parameter and long-distance nuclear energy steam supply system. BACKGROUND

[0002] Steam is one of the essential production materials in many industrial productions, and is widely used in chemical industry, food industry, textile industry, building material manufacturing industry and other industries, especially medium and low pressure steam is most widely used, different grades of steam pressure have different steam supply schemes, and a large amount of steam with multiple parameters is required in a chemical industrial park, the demand for low pressure steam is the largest, and the demand for high pressure steam is relatively small, in order to meet the steam demand of the chemical industrial park, multi-parameter steam supply needs to be provided for the chemical industrial park.

[0003] Chinese patent publication No. CN113864747A discloses an industrial steam composite steam supply system, which comprises a boiler, a high pressure cylinder, a medium pressure cylinder, a low pressure cylinder, a condenser, a steam compressor, a first temperature and pressure reducer, a steam ejector device and a second temperature and pressure reducer; the steam of the boiler enters the high pressure cylinder to do work and then returns to the boiler for heating, the reheated steam of the boiler is divided into four paths, the first path enters the second temperature and pressure reducer, the second path enters the high pressure inlet of the steam ejector device, the third path enters the first temperature and pressure reducer, and the fourth path enters the medium pressure cylinder to do work; the steam at the outlet of the medium pressure cylinder is divided into two paths, one path enters the steam compressor, and the other path enters the low pressure cylinder; the exhaust steam of the steam compressor is divided into two paths, one path is combined with the steam of the first temperature and pressure reducer to enter the low pressure steam supply pipeline, and the other path enters the low pressure inlet of the steam ejector device; the outlet steam of the steam ejector device is combined with the steam of the second temperature and pressure reducer to enter the high pressure steam supply pipeline; and the exhaust steam of the low pressure cylinder enters the condenser to generate condensed water, the condensed water in the condenser is heated by a high and low pressure heater group and then enters the boiler, so as to realize a thermal cycle.

[0004] At present, the steam supply mode of the chemical industrial park mainly obtains steam through cogeneration of thermal power units or self-provided boilers of chemical enterprises, which consumes a large amount of fossil fuels and produces a large amount of carbon emissions; nuclear power pressurized water reactor steam supply mode is also being developed, but the steam parameters are low and the main steam is saturated steam, which can only meet the demand for low pressure steam and short distance external supply and transportation, and cannot realize multi-parameter and long-distance steam supply effect. SUMMARY

[0005] The purpose of the present application is to provide a nuclear energy steam supply system using a high temperature gas cooled reactor combined with a pressurized water reactor, which can meet the multi-parameter and long-distance industrial steam demand of a chemical industrial park.

[0006] In order to achieve the above purpose, the present application provides the following technical scheme:

[0007] A multi-parameter, long-distance nuclear energy steam supply system, comprising a pressurized water reactor, a high-temperature gas cooled reactor, a nuclear power unit and a user end; a first steam heat exchange assembly is arranged on the steam outlet side of the pressurized water reactor, and the first steam heat exchange assembly is circulated with

[0008] heat generation of low-pressure saturated steam; the steam outlet side of the high-temperature gas cooled reactor is provided with a second steam heat exchange assembly, and the second steam heat exchange assembly is circulated with

[0009] heat generation of high-pressure superheated steam, and flows into the user end; the low-pressure saturated steam generated by the first steam heat exchange assembly enters the second steam heat exchange assembly after heat exchange, generates low-pressure superheated steam, and flows into the user end; the water outlet side of the nuclear power unit is provided with a circulating water treatment assembly, and the circulating water treatment assembly supplies water to the first steam heat exchange assembly and the second steam heat exchange assembly.

[0010] Further description of the above technical solution:

[0011] The first steam heat exchange assembly is composed of a first steam generator and a first heat exchanger, the first steam generator realizes heat circulation flow with the pressurized water reactor, and the first heat exchanger realizes steam circulation flow with the first steam generator.

[0012] Further description of the above technical solution:

[0013] The second steam heat exchange assembly is composed of a second steam generator and a superheater, the second steam generator realizes heat circulation flow with the high-temperature gas cooled reactor, and the superheater and the second heat exchanger realize steam circulation flow with the second steam generator.

[0014] Further description of the above technical solution:

[0015] The low-pressure saturated steam generated by the first heat exchanger enters the superheater, generates low-pressure superheated steam, and flows into the user end.

[0016] Further description of the above technical solution:

[0017] The superheated steam generated by the second steam generator enters the second heat exchanger for heat exchange, generates high-pressure superheated steam, and flows into the user end.

[0018] Further description of the above technical solution:

[0019] The circulating water treatment assembly is composed of a seawater desalination system and a desalination storage tank, the seawater desalination system is used for receiving circulating water discharged from the nuclear power unit, and the desalinated water generated after desalination is stored in the desalination storage tank, and water is supplied to the first heat exchanger and the second heat exchanger.

[0020] Further description of the above technical solution:

[0021] The fresh water in the desalination reservoir is exchanged by the first heat exchanger to generate medium-low pressure saturated steam and flow into the superheater; the fresh water in the desalination reservoir is exchanged by the second heat exchanger to generate medium-high pressure superheated steam and flow into the user end.

[0022] Further description of the above technical solution:

[0023] The parameters of the medium-low pressure saturated steam and the medium-low pressure superheated steam are both below 5.0 MPa, and the parameter of the medium-high pressure superheated steam is 5.0-10.0 MPa.

[0024] In the above technical solution, the nuclear energy steam supply system supply method provided by the application has the following beneficial effects: the steam supply system fully utilizes the characteristics of high steam parameters and small amount of high-temperature gas cooled reactor and low steam parameters and large amount of pressurized water reactor, adopts the combined steam supply mode of high-temperature gas cooled reactor and pressurized water reactor, can realize the effect of multi-parameter and long-distance industrial steam supply, provides an industrial steam decarburization solution for high-energy-consuming enterprises, and solves the restriction caused by carbon emission pressure. BRIEF DESCRIPTION OF DRAWINGS

[0025] In order to more clearly illustrate the technical solutions in the embodiments of the present application or the prior art, the drawings needed in the embodiments will be briefly introduced as follows. Obviously, the drawings in the following description are only some embodiments described in the present application, and other drawings can also be obtained by those skilled in the art according to these drawings.

[0026] Figure 1 The structure diagram of the nuclear energy steam supply system supply method provided by the embodiment of the present application. DETAILED DESCRIPTION

[0027] In order to make those skilled in the art better understand the technical solutions of the present application, the present application will be further described in detail below with reference to the drawings.

[0028] The drawings are further described in detail.

[0029] For example, the high-temperature gas cooled reactor is a high-temperature gas cooled reactor with a power of 10-100 MW, and the pressurized water reactor is a pressurized water reactor with a power of 100-1000 MW. Figure 1As shown, a multi-parameter, long-distance nuclear energy steam supply system includes a pressurized water reactor, a high-temperature gas cooled reactor, a nuclear power unit, and a user end; the steam outlet side of the pressurized water reactor is provided with a first steam heat exchange assembly, and the first steam heat exchange assembly is cyclically supplied with heat to generate medium-low pressure saturated steam; the steam outlet side of the high-temperature gas cooled reactor is provided with a second steam heat exchange assembly, and the second steam heat exchange assembly is cyclically supplied with heat to generate medium-high pressure superheated steam, which flows into the user end; the medium-low pressure saturated steam generated by the first steam heat exchange assembly flows into the second steam heat exchange assembly after heat exchange to generate medium-low pressure superheated steam, which flows into the user end; the water outlet side of the nuclear power unit is provided with a circulating water treatment assembly, which supplies water to the first steam heat exchange assembly and the second steam heat exchange assembly.

[0030] The steam supply system fully utilizes the characteristics of the high-temperature gas cooled reactor, which has high steam parameters but small quantity, and the pressurized water reactor, which has low steam parameters but large quantity, adopts a combined steam supply mode of the high-temperature gas cooled reactor and the pressurized water reactor, can realize multi-parameter and long-distance industrial steam supply effect, provides an industrial steam decarbonization solution for high-energy-consuming enterprises, and solves the restriction caused by carbon emission pressure.

[0031] The first steam heat exchange assembly is composed of a first steam generator and a first heat exchanger, the first steam generator realizes heat circulation flow with the pressurized water reactor, and the first heat exchanger realizes steam circulation flow with the first steam generator.

[0032] The second steam heat exchange assembly is composed of a second steam generator and a superheater, the second steam generator realizes heat circulation flow with the high-temperature gas cooled reactor, and the superheater and the second heat exchanger realize steam circulation flow with the second steam generator.

[0033] The medium-low pressure saturated steam generated by the first heat exchanger flows into the superheater to generate medium-low pressure superheated steam, which flows into the user end.

[0034] The superheated steam generated by the second steam generator flows into the second heat exchanger to exchange heat, generating medium-high pressure superheated steam, which flows into the user end.

[0035] The circulating water treatment assembly is composed of a seawater desalination system and a desalination storage pool, the seawater desalination system is used to receive the circulating water discharged by the nuclear power unit, and the fresh water generated after desalination flows into the desalination storage pool for storage, and supplies water to the first heat exchanger and the second heat exchanger.

[0036] The fresh water in the desalination storage pool exchanges heat through the first heat exchanger to generate medium-low pressure saturated steam, which flows into the superheater; the fresh water in the desalination storage pool exchanges heat through the second heat exchanger to generate medium-high pressure superheated steam, which flows into the user end.

[0037] The parameters of the medium-low pressure saturated steam and the medium-low pressure superheated steam are both below 5.0 MPa, and the parameter of the medium-high pressure superheated steam is 5.0 MPa-10.0 MPa.

[0038] A steam supply method of a nuclear energy steam supply system, as shown below:

[0039] S01: The circulating water drainage of the nuclear power unit is used as the water inlet of seawater desalination, the seawater is desalinated by the seawater desalination system, and then enters a fresh water storage pool for storage and use;

[0040] S02: The heat of the pressurized water reactor is used to generate saturated steam of 5.0 MPa and below through the first steam generator, and then the first heat exchanger generates medium and low pressure saturated steam of 5.0 MPa and below;

[0041] S03: The main steam of the high-temperature gas-cooled reactor is used to superheat the medium and low pressure saturated steam to generate medium and low pressure superheated steam of 5 MPa and below, which is supplied to the user end through a long transmission pipe network;

[0042] S04: The heat of the high-temperature gas-cooled reactor is used to generate superheated steam of 14.1 MPa through the second steam generator, and then the second heat exchanger generates medium and high pressure superheated steam of 5.0-10 MPa, which is supplied to the user end through a long transmission pipe network.

[0043] The above only describes some exemplary embodiments of the present application in a descriptive manner, and it is needless to say that those skilled in the art can modify the described embodiments in various ways without departing from the spirit and scope of the present application. Therefore, the above drawings and descriptions are illustrative in nature and should not be understood as limiting the scope of protection of the claims of the present application.

Claims

1. A steam supply method for a nuclear power steam supply system, characterized in that, Includes the following steps, S01: The circulating water drainage of the nuclear power unit is used as the feed water for seawater desalination. After the seawater is desalinated by the seawater desalination system, it is stored in a freshwater storage tank for use. S02: Utilize the heat from the pressurized water reactor to generate saturated steam of 5.0 MPa and below through the first steam generator, and then generate medium and low pressure saturated steam of 5.0 MPa and below through the first heat exchanger. S03: The main steam from the high-temperature gas-cooled reactor is used to superheat the medium and low-pressure saturated steam to generate medium and low-pressure superheated steam below 5.0 MPa, which is then supplied to users via long-distance pipelines. S04: The heat from the high-temperature gas-cooled reactor is used to generate superheated steam at 14.1 MPa through the second steam generator, and then medium- and high-pressure superheated steam at 5.0 MPa-10.0 MPa is generated through the second heat exchanger. The steam is then supplied to users via long-distance pipelines.

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