A nuclear energy steam heat supply system and method capable of increasing superheat degree

Abstract

The application provides a nuclear energy steam heat supply system and method capable of improving superheat degree, a second outlet of a steam generator is communicated with an inlet of a steam turbine and an inlet of an electric heating boiler through pipelines respectively, an outlet of the electric heating boiler is connected to a steam user through a pipeline, the steam turbine is connected with a generator, an outlet pipeline of the steam turbine is communicated with a first inlet of a condenser, a first outlet of the condenser is communicated with a condensate tank, the condensate tank is communicated with a second inlet of the steam generator through a second main pump, a storage and discharge circuit comprises a storage and discharge module, inlets of the storage and discharge module are connected with a power grid and the generator respectively, an outlet of the storage and discharge module is connected with the power grid and each electric equipment, and the application effectively improves the superheat degree of the secondary circuit steam and can meet the temperature parameter requirements of various users.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear energy heating, in particular to a nuclear energy steam heating system and method capable of improving superheat degree. BACKGROUND

[0002] The statements in this section merely provide background technology related to the present application and do not necessarily constitute prior art.

[0003] Nuclear energy heating is a heating method taking the energy generated by nuclear fission as a heat source. The initial investment of a nuclear heating reactor is higher than that of a coal-fired boiler, but a large amount of fuel cost can be saved during the operation period, and compared with a coal-fired boiler of the same power, the annual transportation amount of nuclear fuel is only one ten-millionth of the amount of coal, and the overall fuel cost is much lower than that of a coal-fired or gas-fired boiler. As a supplement to nuclear power, its popularization and application can help improve the energy structure, reduce greenhouse gas emissions and improve the urban environment.

[0004] The inventors have found that, based on the economic efficiency and safety of system operation, a nuclear energy heating system often adopts a two-loop steam heating system, and the superheat degree of the two-loop steam is generally low. If used for heating and heating, the parameters can meet the demand of the first heating station, and if used for industrial heating, the low superheat degree will limit the pipeline transportation distance or make it difficult to meet the demand of the steam end user. SUMMARY

[0005] In order to solve the problems of the prior art, the present application provides a nuclear energy steam heating system and method capable of improving superheat degree, which effectively improves the superheat degree of the two-loop steam and meets the temperature parameter demand of various users.

[0006] In order to achieve the above-mentioned purpose, the present application adopts the following technical solutions:

[0007] The present application provides a nuclear energy steam heating system capable of improving superheat degree in the first aspect.

[0008] A nuclear energy steam heating system capable of improving superheat degree, at least comprising a second loop and a storage and discharge circuit:

[0009] The second loop comprises a steam generator, a steam turbine, a generator, a condenser, a condensate tank, a second main pump and an electric boiler.

[0010] The second outlet of the steam generator is respectively communicated with the inlet of the steam turbine and the inlet of the electric boiler through pipelines, the outlet of the electric boiler is connected to a steam user through a pipeline, and the steam turbine is connected to the generator.

[0011] The outlet pipeline of the steam turbine is communicated with the first inlet of the condenser, the first outlet of the condenser is communicated with the condensate tank, and the condensate tank is communicated with the second inlet of the steam generator through the second main pump.

[0012] The storage and discharge circuit comprises a storage and discharge module, the inlet of the storage and discharge module is connected with the power grid and the generator respectively, and the outlet of the storage and discharge module is connected with the power grid and each electrical equipment.

[0013] As a further limitation of the first aspect of the application, the system further comprises a first loop, the first loop comprising: a reactor, a steam generator, a first main pump and a pressurizer;

[0014] The outlet pipeline of the reactor is communicated with the inlet of the pressurizer and the first inlet of the steam generator respectively, the first outlet of the steam generator is communicated with the inlet of the first main pump through a pipeline, and the outlet pipeline of the first main pump is communicated with the outlet pipeline of the pressurizer and then with the inlet of the reactor.

[0015] As a further limitation of the first aspect of the application, the steam bypass is connected between the inlet and the outlet of the electric heating boiler, and a bypass control valve is connected on the steam bypass.

[0016] As a further limitation of the first aspect of the application, the second inlet of the condenser is communicated with the outlet of the circulating cooling water pump through a pipeline, the second outlet of the condenser is communicated with the natural cooling water source through a pipeline, and the inlet of the circulating water pump is communicated with the natural cooling water source through a pipeline.

[0017] As a further limitation of the first aspect of the application, the condensed water returned by the self-heating user and the chemical water supplement are communicated with the condensate tank through a pipeline.

[0018] The second aspect of the application provides a nuclear energy steam heating system operation method capable of improving superheat degree.

[0019] The nuclear energy steam heating system operation method capable of improving superheat degree utilizes the nuclear energy steam heating system capable of improving superheat degree in the first aspect of the application, and when there is no heat load, the method comprises the following processes:

[0020] Each device of the first loop is normally operated according to the cooling requirement of the reactor;

[0021] The second loop does not supply heat to the outside, all the high-temperature steam generated by the steam generator enters the steam turbine, the steam turbine is driven to drive the generator to generate electricity, the exhaust steam of the steam turbine enters the condenser to be cooled into condensed water, the condensed water enters the condensate tank, and the outlet water of the condensate tank is pressurized by the second main pump and then enters the steam generator for the next working cycle;

[0022] The circulating cooling water pipeline is normally operated according to the cooling requirement of the condenser;

[0023] The generated power of the generator enters the storage and discharge module, and is preferentially supplied to each electrical equipment of the system, and the excess power can be stored for standby or transmitted to the power grid.

[0024] The third aspect of the present application provides a nuclear energy steam heating system operation method capable of improving superheat degree.

[0025] The nuclear energy steam heating system operation method capable of improving superheat degree utilizes the nuclear energy steam heating system capable of improving superheat degree according to the first aspect of the present application, and comprises the following processes when the heat load is low:

[0026] Each device of the first loop is normally operated according to the cooling requirement of the reactor;

[0027] In the second loop, high-temperature steam generated by the steam generator is divided into two parts, one part enters the steam turbine to drive the steam turbine to drive the generator to generate electricity, the exhaust steam of the steam turbine enters the condenser to be cooled into condensed water, and the condensed water enters the condensed water tank, and the outlet water of the condensed water tank is pressurized by the second main pump to enter the steam generator for the next working cycle, the other part enters the electric heating boiler to be heated into high superheat steam to ensure that the user parameter requirement is met without generating excess condensed water, and the condensed water after being used by the steam user is finally recovered to the condensed water tank;

[0028] The circulating cooling water pipeline is normally operated according to the cooling requirement of the condenser;

[0029] The generated power of the generator enters the power storage module, and is preferentially used by each power consumption device of the system, and the excess power can be stored for standby or transmitted to the power grid.

[0030] The fourth aspect of the present application provides a nuclear energy steam heating system operation method capable of improving superheat degree.

[0031] The nuclear energy steam heating system operation method capable of improving superheat degree utilizes the nuclear energy steam heating system capable of improving superheat degree according to the first aspect of the present application, and comprises the following processes when the heat load is high:

[0032] Each device of the first loop is normally operated according to the cooling requirement of the reactor;

[0033] In the second loop, high-temperature steam generated by the steam generator enters the electric heating boiler to be heated into high superheat steam to ensure that the user parameter requirement is met without generating excess condensed water, and the condensed water after being used by the steam user is finally recovered to the condensed water tank, and the outlet water of the condensed water tank is pressurized by the second main pump to enter the steam generator for the next working cycle, if the superheat degree of the steam without heating by the electric heating boiler can also meet the heating requirement, the steam directly enters the user through the bypass;

[0034] The circulating cooling water pipeline is not operated;

[0035] The power storage module releases the previously stored power to be used by each power consumption device of the system, and if the power is insufficient, the power grid is accessed for charging.

[0036] As further limitation of the second aspect, the third aspect or the fourth aspect of the present application, the steam or water as the working medium is continuously circulated in the first loop, the water in the reactor is heated to become steam, the steam is condensed to release heat after entering the steam generator, and the water is pressurized by the first main pump to re-enter the reactor, the inlet and outlet of the pressurizer are connected to the inlet of the steam generator and the outlet pipe of the first loop feed water pump respectively, for stabilizing the pressure in the first loop.

[0037] As further limitation of the second aspect, the third aspect or the fourth aspect of the present application, the cooling water as the working medium is in open circulation in the system, the limited normal temperature water enters the circulating cooling water pump, is pressurized by the pump, enters the condenser, cools the steam in the second loop, and is discharged to the natural environment after being heated.

[0038] Compared with the prior art, the present application has the following beneficial effects:

[0039] 1. The present application innovatively proposes a nuclear energy steam heating system and method capable of improving the superheat degree, which can effectively improve the superheat degree of the second loop steam, and meet the temperature parameter requirements of various users.

[0040] 2. The present application innovatively proposes a nuclear energy steam heating system and method capable of improving the superheat degree, in which part of the high-temperature steam enters the electric heating boiler to be heated to become high-superheat steam under low heat load and high heat load, and the superheat degree can guarantee to meet the user parameter requirements without generating excess condensate.

[0041] The advantages of the additional aspects of the present application will be partially given in the following description, partially become obvious from the following description, or be understood through the practice of the present application. BRIEF DESCRIPTION OF DRAWINGS

[0042] The accompanying drawings, which form a part of the present application, are used to provide further understanding of the present application, and the schematic embodiments of the present application and the description thereof are used to explain the present application, and do not constitute improper limitation of the present application.

[0043] Figure 1 A schematic diagram of the nuclear energy steam heating system capable of improving the superheat degree provided for the embodiment 1 of the present application;

[0044] Figure 2 A schematic diagram of the nuclear energy heating system provided for the embodiment 2 of the present application;

[0045] Figure 3 A schematic diagram of the nuclear energy heating system capable of improving the superheat degree provided for the embodiment 2 of the present application;

[0046] Wherein, 1 -reactor; 2-steam generator; 3-one loop main pump; 4-pressure stabilizer; 5-turbine; 6-generator; 7- condenser; 8-condensed water tank; 9-two loop main pump; 10-electric heating boiler; 11-steam bypass; 12-circulating cooling water pump; 13-storage module; 14-bypass control valve; 15-power grid. DETAILED DESCRIPTION

[0047] The application will be further described below with reference to the drawings and examples.

[0048] It should be noted that the following detailed description is exemplary in nature and is intended to provide further description of the application. Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs.

[0049] It is to be understood that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of example embodiments in accordance with the present application. As used herein, the singular forms "a", "an" and "the" are intended to include the plural forms as well, unless the context clearly indicates otherwise. It will be further understood that the terms "comprises" and / or "comprising," when used in this specification, specify the presence of stated features, steps, operations, elements, components, and / or groups thereof, but do not preclude the presence or addition of one or more other features, steps, operations, elements, components, and / or groups thereof.

[0050] The embodiments in the present application and the features in the embodiments can be combined with each other without conflict.

[0051] Embodiment 1

[0052] As shown in the figure, the nuclear energy steam heating system capable of improving superheat degree provided by the embodiment 1 of the present application comprises a one loop steam-water pipeline (i.e. a first loop), a two loop steam-water pipeline (i.e. a second loop), a circulating cooling water pipeline and a storage and power supply circuit, specifically comprising: Figure 1 The one loop steam-water pipeline (i.e. the first loop) comprises four main devices: a reactor 1, a steam generator 2, a one loop main pump 3 (i.e. a first main pump) and a pressure stabilizer 4, and the outlet pipeline of the reactor 1 is connected to the steam generator 2 and the pressure stabilizer 4 through branches respectively;

[0053] The outlet pipeline of the steam generator 2 is connected to the inlet pipeline of the one loop main pump 3 (i.e. the first main pump), and the outlet pipeline of the one loop main pump 3 (i.e. the first main pump) is combined with the outlet pipeline of the pressure stabilizer 4, and then connected to the inlet pipeline of the reactor 1;

[0054]

[0055] ​In this embodiment, steam or water as the working medium in a continuous cycle in the primary circuit, into the reactor 1 water heated into steam, steam into the steam generator 2 after condensation exothermic, become water after the primary circuit main pump 3 re-pressurized into the reactor 1, the stabilizer 4 inlet and outlet are connected to the steam generator 2 inlet and primary circuit feedwater pump outlet pipe, for stabilizing the system pressure of the primary circuit.

[0056] The secondary circuit steam and water pipeline includes seven main equipment: steam generator 2, steam turbine 5, generator 6, condenser 7, condensate tank 8, secondary circuit main pump 9 (i.e. the second main pump), electric boiler 10 and steam bypass 11;

[0057] Steam generator 2 outlet pipe through branch respectively with steam turbine 5, electric boiler 10 connection, steam turbine 5 outlet pipe to the condenser 7, condenser 7 outlet pipe to the condensate tank 8, condensate tank 8 outlet pipe to the secondary circuit main pump 9, secondary circuit main pump 9 outlet pipe to the steam generator 2;

[0058] Electric boiler 10 outlet pipe to each heat user (i.e. steam heat user), from the heat user returned condensate and chemical water make-up through the pipeline to the condensate tank 8, electric boiler 10 inlet and outlet pipe with steam bypass 11 connection, equivalent to parallel connection with steam bypass 11, steam bypass 11 is connected with bypass control valve 14.

[0059] In this embodiment, steam or water as the working medium in a continuous cycle in the secondary circuit, into the steam generator 2 water heated into steam, steam into the steam turbine 5 after expansion work, steam turbine 5 drive generator 6 power generation, steam turbine 5 outlet of the exhaust steam into the condenser 7 fully condensed into water and then into the condensate tank 8, condensate tank 8 outlet water through the secondary circuit main pump 9 re-pressurized into the steam generator 2;

[0060] Steam generator 2 outlet part of the steam through branch into the electric boiler 10, after heating into the steam with higher superheat degree to the steam user, the final user side used steam re-condensed into water, with chemical water make-up into the condensate tank, if no need to increase the superheat degree, steam generator 2 outlet steam can also be directly through the bypass directly to the steam user.

[0061] The circulating cooling water pipeline includes two main equipment: condenser 7 and circulating cooling water pump 12, circulating cooling water pump 12 inlet pipe with natural cooling water source connection, outlet pipe to the condenser 7, condenser 7 outlet pipe to the natural cooling water source;

[0062] In this embodiment, cooling water as the working medium in the system for open cycle, limited room temperature water into the circulating cooling water pump 12, through the pump pressurized into the condenser 7, cooling the secondary circuit steam, itself after heating is discharged to the natural environment.

[0063] The core device of the storage and discharge circuit is a storage and discharge module 13, which is connected with the power grid and the generator 6 at the inlet and connected with the power grid 15, the electric heating boiler 10, the motor of the primary loop pump 3, the motor of the secondary loop pump 9, the motor of the circulating cooling water pump 12 and other possible electric devices at the outlet; the storage and discharge module 13 has the ability of storing and releasing electric energy, and can receive the electric power of the power grid and the generator 6 at any time, or send the electric power to the system and provide electric power to each electric user in the system at any time.

[0064] Embodiment 2

[0065] The embodiment 2 of the present application provides a nuclear energy steam heat supply system operation method capable of improving superheat degree, and comprises the following process:

[0066] S1: When there is no heat load, the steam user does not need steam, at this time, the reactor 1 needs to be cooled, and the heat energy generated thereby needs to be reasonably stored and released, and the operation mode is as follows:

[0067] The primary loop steam-water pipeline is normally operated according to the cooling needs of the reactor 1, and is usually continuously and stably operated and does not change with external load adjustment;

[0068] The secondary loop steam-water pipeline does not supply heat to the outside, the high-temperature steam generated by the steam generator 2 all enters the steam turbine 5, drives the steam turbine 5 to drive the generator 6 to generate electricity, the exhaust steam of the steam turbine 5 enters the condenser 7 to be cooled into condensed water, and then enters the condensed water tank 8, and the outlet water of the condensed water tank 8 is pressurized by the secondary loop pump 9 and then enters the steam generator 2 for the next working cycle;

[0069] The circulating cooling water pipeline is normally operated according to the cooling needs of the condenser 7;

[0070] The electric power generated by the generator 6 enters the storage and discharge module, and is preferentially supplied to the electric devices in the system, such as the motor of the primary loop pump 3, the motor of the secondary loop pump 9, the motor of the circulating cooling water pump 12 and other electric devices, and the excess electric power can be stored for standby or sold to the power grid 15.

[0071] S2: When the heat load is low, the steam required by the steam user is relatively low compared with the design quantity of the heat supply pipeline network, the heat produced by the reactor 1 can meet the heat supply demand, and the excess heat also needs to be reasonably stored and released. When the heat load is low, because the superheat degree of the steam produced by the nuclear reactor is low, the steam flow of the heat supply pipeline network is small, and the flow rate is slow, which leads to the steam being easily cooled into water, on the one hand, the terminal parameters cannot meet the user demand, and on the other hand, the water discharge causes a lot of working medium waste, in view of the above problems, the operation mode is as follows:

[0072] The primary loop steam-water pipeline is normally operated according to the cooling needs of the reactor 1, and is usually continuously and stably operated and does not change with external load adjustment;

[0073] The high-temperature steam generated by the steam generator 2 is divided into two parts. One part enters the steam turbine 5 to drive the steam turbine 5 to drive the generator 6 to generate electricity. The exhaust steam of the steam turbine 5 enters the condenser 7 to be cooled into condensed water, which enters the condensed water tank 8. The outlet water of the condensed water tank 8 is pressurized by the secondary loop main pump 9 and enters the steam generator 2 for the next working cycle. The other part enters the electric heating boiler 10 to be heated into high-temperature superheated steam. The superheat degree can ensure that the user parameter demand is met without generating excess condensed water. The condensed water after being used by the steam user is finally recovered to the condensed water tank 8.

[0074] The circulating cooling water pipeline is normally operated according to the cooling needs of the condenser 7.

[0075] The generated power of the generator 6 enters the storage and release module, which is preferentially used for the motor of the primary loop main pump 3, the motor of the secondary loop main pump 9, the motor of the circulating cooling water pump 12, the electric heating boiler 10 and other electrical equipment in the system. The excess power can be stored for standby or sold to the power grid 15.

[0076] S3, when the heat load is high, the steam demand of the steam user is close to the design capacity of the heating pipe network, and the heat produced by the reactor 1 is almost entirely used to meet the heating demand. The operation mode is as follows:

[0077] The primary loop steam and water pipeline is normally operated according to the cooling needs of the reactor 1, and is usually continuously and stably operated without adjustment and change with external load.

[0078] The secondary loop steam and water pipeline is normally operated according to the cooling needs of the condenser 7, and is usually continuously and stably operated without adjustment and change with external load.

[0079] The circulating cooling water pipeline is not operated.

[0080] The storage and release module releases the previously stored electrical energy to supply the motor of the primary loop main pump 3, the motor of the secondary loop main pump 9, the electric heating boiler 10 and other electrical equipment in the system. If the electrical energy is insufficient, the power grid 15 is connected for charging.

[0081] If Figure 2 and Figure 3As shown, the conventional heat supply nuclear reactor produces steam with limited superheat degree, the steam temperature is t1, the corresponding saturation temperature is t2, and the superheat degree is t1-t2. The system and the operation method thereof can use the enthalpy drop of part of the steam (or part of the steam in a period) to heat another part of the steam (or another part of the steam in a period), so that the temperature of the output steam is increased from t1 to t3, at this time the corresponding saturation temperature is t4, and the superheat degree t3-t4 is greater than t1-t2, and the superheat degree is higher.

[0082] The above only describes the preferred embodiments of the present application and is not intended to limit the present application. For those skilled in the art, the present application can have various modifications and changes. Any modification, equivalent replacement, improvement, etc. within the spirit and principle of the present application shall be included in the protection scope of the present application.

Claims

1. A nuclear energy steam heating system capable of increasing superheat, characterized by, At least comprising a second loop and a storage and discharge circuit: The second loop comprises a steam generator, a steam turbine, a generator, a condenser, a condensate tank, a second main pump and an electric heating boiler; The second outlet of the steam generator is connected to the inlet of the steam turbine and the inlet of the electric heating boiler through pipelines respectively, the outlet of the electric heating boiler is connected to a steam user through a pipeline, the steam turbine is connected to the generator; a steam bypass is connected between the inlet and the outlet of the electric heating boiler, and a bypass control valve is connected to the steam bypass; the steam user is a heat user; The outlet pipeline of the steam turbine is connected to the first inlet of the condenser, the first outlet of the condenser is connected to the condensate tank, and the condensate tank is connected to the second inlet of the steam generator through the second main pump; The storage and discharge circuit comprises a storage and discharge module, the inlet of the storage and discharge module is connected to the power grid and the generator respectively, the outlet of the storage and discharge module is connected to the electric heating boiler, the power grid and each electrical equipment; the storage and discharge module receives the power of the power grid and the generator, or transmits the generated power to the power grid at any time, and provides power for each electrical equipment in the system.

2. The nuclear energy steam heating system capable of improving superheat degree according to claim 1, wherein the system further comprises a first loop, and the first loop comprises a reactor, a steam generator, a first main pump and a pressurizer; The outlet pipeline of the reactor is connected to the inlet of the pressurizer and the first inlet of the steam generator respectively, the first outlet of the steam generator is connected to the inlet of the first main pump through a pipeline, and the outlet pipeline of the first main pump is connected to the outlet pipeline of the pressurizer and then connected to the inlet of the reactor.

3. The nuclear energy steam heating system capable of improving superheat degree according to claim 1, wherein the second inlet of the condenser is connected to the outlet of the circulating cooling water pump through a pipeline, the second outlet of the condenser is connected to a natural cooling water source through a pipeline, and the inlet of the circulating water pump is connected to the natural cooling water source through a pipeline.

4. The nuclear energy steam heating system capable of improving superheat degree according to claim 1, wherein the condensate returned by the heat user and the chemical water supplement are connected to the condensate tank through a pipeline. The nuclear energy steam heating system capable of improving superheat degree according to any one of claims 1-4 is used in the following process when there is no heat load: Each device of the first loop normally operates according to the cooling requirement of the reactor; The second loop does not supply heat to the outside, the high-temperature steam generated by the steam generator enters the steam turbine, the steam turbine drives the generator to generate electricity, the exhaust steam of the steam turbine enters the condenser to be cooled into condensate water, the condensate water enters the condensate tank, and the outlet water of the condensate tank enters the steam generator through the second main pump for the next working cycle; 5. A method for operating a nuclear energy steam heating system with increased superheat, characterized in that The circulating cooling water pipeline normally operates according to the cooling requirement of the condenser; The generated power of the generator enters the storage and discharge module, and is preferentially supplied to each electrical equipment in the system, and the excess power can be stored for standby or transmitted to the power grid.

6. The operation method of the nuclear energy steam heating system capable of improving superheat degree according to claim 5, wherein ​ ​ ​ Steam or water as the working medium in the first circuit is constantly circulating, the water into the reactor is heated to become steam, the steam into the steam generator after condensation heat release, become water after the first main pump pressure re-enter the reactor, the inlet and outlet of the pressurizer are connected with the steam generator inlet and the first loop feed water pump outlet pipeline respectively, for stabilizing the pressure in the first circuit.

7. The method for operating the nuclear energy steam heat supply system with improved superheat degree according to claim 5, characterized in that, Cooling water as the working medium in the system for open cycle, limited constant temperature water into the circulating cooling water pump, after the pump pressurization into the condenser, cooling the second circuit steam, itself after being heated to be discharged to the natural environment.

8. A method for operating a nuclear energy steam heating system with increased superheat, characterized in that Using the nuclear energy steam heat supply system with improved superheat degree according to any one of claims 1-4, at low heat load, including the following processes: The devices of the first circuit are normally operated according to the cooling needs of the reactor; In the second circuit, the high-temperature steam generated by the steam generator is divided into two parts, one part enters the steam turbine to drive the steam turbine to drive the generator to generate electricity, the exhaust steam of the steam turbine enters the condenser to be cooled into condensed water, which enters the condenser water tank, and the outlet water of the condenser water tank is pressurized by the second main pump to enter the steam generator for the next working cycle, the other part enters the electric heating boiler to be heated into high superheat steam to ensure that the user parameter demand is met without generating excess condensed water, which is finally recovered to the condenser water tank after being used by the steam user; The circulating cooling water pipeline is normally operated according to the cooling needs of the condenser; The power generated by the generator enters the storage module, which is preferentially used by the electrical equipment of the system, and the excess power can be stored for standby or transmitted to the power grid.

9. A method for operating a nuclear energy steam heating system with increased superheat, characterized in that Using the nuclear energy steam heat supply system with improved superheat degree according to any one of claims 1-4, at high heat load, including the following processes: The devices of the first circuit are normally operated according to the cooling needs of the reactor; In the second circuit, the high-temperature steam generated by the steam generator is divided into two parts, one part enters the steam turbine to drive the steam turbine to drive the generator to generate electricity, the exhaust steam of the steam turbine enters the condenser to be cooled into condensed water, which enters the condenser water tank, and the outlet water of the condenser water tank is pressurized by the second main pump to enter the steam generator for the next working cycle, the other part enters the electric heating boiler to be heated into high superheat steam to ensure that the user parameter demand is met without generating excess condensed water, which is finally recovered to the condenser water tank after being used by the steam user; The circulating cooling water pipeline is not operated; The storage module releases the previously stored electrical energy to be used by the electrical equipment of the system, and if the electrical energy is insufficient, it is connected to the power grid for charging.

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