Heating device based on secondary circuit heat supply type of nuclear power plant and its control method

Abstract

The present invention discloses a heating device based on the secondary circuit heat supply mode of a nuclear power plant and its control method, relating to the field of secondary circuit heat supply of a nuclear power plant. In the heating device based on the secondary circuit heat supply mode of a nuclear power plant, the heat supply drain end outlets of the multi-stage high-pressure feedwater heaters in the steam turbine extraction steam heat supply device are respectively connected in a one-to-one manner to the high-temperature side medium inlets of the multi-stage heat exchangers. The high-temperature side medium outlets of the multi-stage heat exchangers are all connected to the drain end inlets of the low-pressure feedwater heaters in the steam turbine extraction steam heat supply device. The low-temperature side medium inlets and low-temperature side medium outlets of the multi-stage heat exchangers are all connected in series to the heat supply pipe network. The present invention can realize heat supply without changing the main pipeline of the secondary circuit, and can reduce the renovation cost of the secondary circuit pipeline and the influence on the working fluid of the main steam pipeline.

Description

CROSS-REFERENCE TO RELATED APPLICATIONS

[0001] This invention claims priority from a Chinese patent application bearing application number 202310737909.4 and entitled "Heating device and control method based on secondary circuit heat supply type of nuclear power plant" filed with the China Patent Office on June 20, 2023, the entire contents of which are incorporated by reference. [Technical Field]

[0002] The present invention relates to the field of secondary circuit heat supply in nuclear power plants, and more particularly to a heating device based on the secondary circuit heat supply type of nuclear power plants and a control method thereof. [Background technology]

[0003] Nuclear energy is a clean and efficient form of energy that can not only be used to generate electricity, but can also achieve the purpose of heat supply with appropriate design. Currently, research into nuclear energy heat supply mainly focuses on low-temperature nuclear energy heat supply and heat supply using steam extracted from the steam turbine unit of a nuclear power plant. Among these, heat supply using steam extracted from the steam turbine unit of a nuclear power plant can stably supply large amounts of high-quality heat energy without affecting the original output of the nuclear power plant, and it requires little modification work, while at the same time improving the economic benefits and thermal efficiency of the nuclear power plant, so it is attracting increasingly widespread attention and research.

[0004] Currently, the main form of heat supply in nuclear power plants is to use a specific stage of extracted steam from the steam turbine to heat the circulating water in the heat network to a preset temperature. In this stage, the extracted steam from the steam turbine is converted into drain water after the heat exchange process, which then goes through a series of cycles and finally returns to the condenser. This form requires significant modifications to the main pipeline of the secondary circuit, which is costly. Summary of the Invention [Problem to be solved by the invention]

[0005] SUMMARY OF THE INVENTION An object of the present invention is to provide a heating device based on a secondary circuit heat supply type of a nuclear power plant, which can realize heat supply without changing the main pipeline of the secondary circuit, and a control method thereof. [Means for solving the problem]

[0006] A heating device based on a secondary circuit heat supply type of a nuclear power plant, the heating device based on the secondary circuit heat supply type of the nuclear power plant including a steam turbine extraction steam heat supply device and a multi-stage heat exchanger; The heat supply drain end outlet of the multi-stage high-pressure feed water heater in the steam turbine extraction steam heat supply device is 、 each Each stage It is connected one-to-one to the high-temperature side medium inlet of the heat exchanger, Each stage The high temperature medium outlet of the heat exchanger is 、 Both are connected to the drain end inlet of the low-pressure feed water heater in the steam turbine extraction steam heat supply device, Each stage The low-temperature medium inlet and outlet of the heat exchanger are both connected in series to a heat supply pipe network. The heat supply pipe network is heated by drain water flowing from the high-pressure feedwater heater of each stage into the heat exchanger of each stage.

[0007] Furthermore, a pressure reducing valve may be installed between the drain end inlet of the low-pressure feed water heater and the high-temperature side medium outlet of the heat exchanger of each stage in the steam turbine extraction steam heat supply system.

[0008] A method for controlling a heating device based on a secondary circuit heat supply type of a nuclear power plant, the method for controlling a heating device based on a secondary circuit heat supply type of the nuclear power plant being used for a heating device based on a secondary circuit heat supply type of the nuclear power plant, and the method for controlling a heating device based on a secondary circuit heat supply type of the nuclear power plant comprising: Obtain actual operation data of the heating device based on the secondary circuit heat supply type of the nuclear power plant under preset parameters, the actual operation data including the actual steam consumption of each stage high-pressure feedwater heater, the actual heat release amount of each stage high-pressure feedwater heater, the actual temperature of the high-temperature side medium outlet of each stage heat exchanger, the actual heat absorption amount of the heat supply pipe network in each stage heat exchanger, the actual condensed steam capacity of the condenser and the actual feedwater flow rate of the condenser, the preset parameters including the parameters of the high-pressure feedwater heater, the parameters of the heat exchanger and the parameters of the condenser; Obtain preset operating data of a heating device based on the secondary circuit heat supply type of a nuclear power plant under preset parameters, the preset operating data including: a preset steam consumption of each stage high-pressure feedwater heater, a preset condensed steam amount of a condenser, a preset temperature of a high-temperature side medium outlet of each stage heat exchanger, and a preset feedwater flow rate of the condenser; The preset parameters are adjusted so that the actual operating data and the preset operating data satisfy preset conditions.

[0009] In addition, adjusting the preset parameters so that the actual operation data and the preset operation data satisfy the preset conditions includes, specifically, Adjusting each stage heat exchanger so that the actual heat dissipation amount of each stage high-pressure feed water heater and the actual heat absorption amount of the heat supply pipe network in each stage heat exchanger meet the first preset condition; Adjusting the parameters of the high-pressure feedwater heater so that the actual steam consumption of each stage high-pressure feedwater heater, the preset temperature of the high-temperature side medium outlet of each stage heat exchanger, the preset steam consumption of each stage high-pressure feedwater heater, and the actual temperature of the high-temperature side medium outlet of each stage heat exchanger satisfy a second preset condition; This may include adjusting parameters of the condenser such that the actual condensing steam capacity of the condenser, the actual feedwater flow rate of the condenser, the preset condensing steam capacity of the condenser, and the preset feedwater flow rate of the condenser satisfy a third preset condition.

[0010] The first preset condition may be as follows.

[0011]

number

[0012] Here, Q rwi represents the actual heat absorption amount of the heat supply pipe network in the ith stage heat exchanger, and Q sshi represents the actual heat dissipation amount of the i-th stage high-pressure feedwater heater.

[0013] The second preset condition may be as follows.

[0014]

number

[0015] where T j1 represents the preset temperature of the hot medium outlet of the first stage heat exchanger, g1 represents the preset steam consumption of the first stage high-pressure feedwater heater, and T ssh1out represents the actual temperature at the hot medium outlet of the first stage heat exchanger, and g hes1 represents the actual steam consumption of the first stage high pressure feedwater heater, and T j2 represents the preset temperature of the hot medium outlet of the second-stage heat exchanger, g2 represents the preset steam consumption of the second-stage high-pressure feedwater heater, and T ssh2out represents the actual temperature at the hot side outlet of the second stage heat exchanger, and g hes2 represents the actual steam consumption of the second stage high pressure feedwater heater, and T ji represents the preset temperature of the hot medium outlet of the ith stage heat exchanger, and g i represents the preset steam consumption of the ith stage high-pressure feedwater heater, and T sshiout represents the actual temperature at the hot side outlet of the ith stage heat exchanger, and g hesi represents the actual steam consumption of the i-th stage high-pressure feedwater heater.

[0016] The third preset condition may be as follows.

[0017]

number

[0018] where G cd1 represents the actual condensed steam capacity of the condenser, and G cd represents the preset condensed steam capacity of the condenser, and G fw1 represents the actual feedwater flow rate of the condenser, and G fw represents the preset feedwater flow rate of the condenser. [Effects of the Invention]

[0019] According to the specific embodiments provided by the present invention, the following technical effects are disclosed: In a heating system based on the secondary circuit heat supply format of a nuclear power plant, the heat supply drain end outlets of the multi-stage high-pressure feedwater heaters in a steam turbine extracted steam heat supply device are each connected one-to-one to the high-temperature side medium inlets of the multi-stage heat exchangers, the high-temperature side medium outlets of the multi-stage heat exchangers are all connected to the drain end inlets of the low-pressure feedwater heaters in the steam turbine extracted steam heat supply device, and the low-temperature side medium inlets and outlets of the multi-stage heat exchangers are all connected in series to the heat supply pipe network. This invention achieves heat supply without modifying the main pipeline of the secondary circuit, reducing the cost of modifying the secondary circuit pipeline and the impact on the working fluid of the main steam pipeline. [Brief explanation of the drawings]

[0020] In order to more clearly describe the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the embodiments will be briefly described below. However, the drawings in the following description are only a part of the embodiments of the present invention, and those skilled in the art can obtain other drawings based on these drawings without any creative efforts. [Figure 1] 1 is a structural diagram of a heating device based on a secondary circuit heat supply type of a nuclear power plant according to a first embodiment of the present invention; [Figure 2] 1 is a structural diagram of a low-pressure cylinder inlet steam heating device for a steam turbine of a nuclear power plant according to a first embodiment of the present invention; [Figure 3]1 is a structural diagram of a high-pressure cylinder exhaust steam heating device for a steam turbine of a nuclear power plant according to a first embodiment of the present invention; DETAILED DESCRIPTION OF THE INVENTION

[0021] The technical solutions in the embodiments of the present invention will be clearly and completely described below in the embodiments of the present invention with accompanying drawings, but it is clear that the described embodiments are only a part of the embodiments of the present invention, and are not all of the embodiments. Based on the embodiments of the present invention, all other embodiments that can be obtained by those skilled in the art without any creative efforts fall within the protection scope of the present invention.

[0022] SUMMARY OF THE INVENTION An object of the present invention is to provide a heating device based on a secondary circuit heat supply type of a nuclear power plant, which can realize heat supply without changing the main pipeline of the secondary circuit, and a control method thereof.

[0023] To make the above objects, features and advantages of the present invention more apparent and understandable, the present invention will be described in more detail below with reference to the drawings and specific embodiments. [Example]

[0024] The heating device based on the secondary circuit heat supply type of the nuclear power plant of the present invention includes a steam turbine extraction steam heat supply device and a multi-stage heat exchanger, which is a heat exchanger of the heat supply network.

[0025] The heat supply drain end outlets of the multi-stage high-pressure feed water heater in the steam turbine extracted steam heat supply device are respectively connected one-to-one to the high-temperature side medium inlets of the multi-stage heat exchangers, the high-temperature side medium outlets of the multi-stage heat exchangers are connected to the drain end inlets of the low-pressure feed water heater in the steam turbine extracted steam heat supply device, and the low-temperature side medium inlets and low-temperature side medium outlets of the multi-stage heat exchangers are connected in series to the heat supply pipe network.

[0026] In the steam turbine extraction steam heat supply system, a pressure reducing valve is installed between the drain end inlet of the low-pressure feed water heater and the high-temperature side medium outlet of the heat exchanger of each stage.

[0027] As shown in Figure 1, the new steam path in a nuclear power plant's secondary circuit heat supply system runs through steam generator 1, steam turbine high-pressure cylinder 2, steam / water separator / reheater 3, steam turbine low-pressure cylinder 4, condenser 6, condensate pump 7, first-stage low-pressure feedwater heater 8, second-stage low-pressure feedwater heater 17, third-stage low-pressure feedwater heater 18, deaerator 9, feedwater pump 10, third-stage high-pressure feedwater heater 13, second-stage high-pressure feedwater heater 12, first-stage high-pressure feedwater heater 11, and back to steam generator 1. Steam turbine low-pressure cylinder 4 is then connected to generator 5 to supply electricity.

[0028] The present invention heats the heat supply pipe network through the drain water of the third-stage high-pressure feedwater heater 13, the second-stage high-pressure feedwater heater 12, and the first-stage high-pressure feedwater heater 11, mainly by improving the original drain ports of the third-stage high-pressure feedwater heater 13, the second-stage high-pressure feedwater heater 12, and the first-stage high-pressure feedwater heater 11 (the original drain port design is shown in Figures 2 and 3). The drain end outlet of the third-stage high-pressure feedwater heater 13 is connected to the high-temperature side medium inlet of the third-stage heat exchanger 16, the drain end outlet of the second-stage high-pressure feedwater heater 12 is connected to the second-stage heat exchanger 15, and the drain end outlet of the first-stage high-pressure feedwater heater 11 is connected to the high-temperature side medium inlet of the first-stage heat exchanger 14, so that the drain water from the third-stage high-pressure feedwater heater 13 flows into the third-stage heat exchanger 16, and the drain water from the second-stage high-pressure feedwater heater 12 flows into the second-stage heat exchanger 15. The drain water flows into the heat exchanger 15, and the drain water from the first-stage high-pressure feed water heater 11 flows into the first-stage heat exchanger 14, and heats the heat supply pipe network connected in series to the low-temperature side medium inlets and low-temperature side outlets of the first-stage heat exchanger 14, second-stage heat exchanger 15, and third-stage heat exchanger 16. After heating is completed, the drain water flows into the pressure reducing valve from the high-temperature side medium outlets of the first-stage heat exchanger 14, second-stage heat exchanger 15, and third-stage heat exchanger 16, and after being reduced to an appropriate pressure by the pressure reducing valve, the drain water is mixed and returned to the drain port inlet of the first-stage low-pressure feed water heater 8. As a result, the drain water from the entire device continues to flow through the secondary circuit main pipeline and finally enters the condenser 6 for the next circulation, which has little impact on the secondary circuit main pipeline. In Figure 1, only three stages of high-pressure feedwater heaters, three stages of low-pressure feedwater heaters, and three stages of heat exchangers are provided, but in reality, multiple stages of high-pressure feedwater heaters, multiple stages of low-pressure feedwater heaters, and multiple stages of heat exchangers can be provided, and there is no limit to the number of stages of high-pressure feedwater heaters, low-pressure feedwater heaters, and heat exchangers.

[0029] A method for controlling a heating device based on a secondary circuit heat supply type of a nuclear power plant, the method for controlling a heating device based on a secondary circuit heat supply type of the nuclear power plant is used for a heating device based on a secondary circuit heat supply type of the nuclear power plant, and the method for controlling a heating device based on a secondary circuit heat supply type of the nuclear power plant includes: As shown in Figure 1, actual operating data of the heating device is obtained based on the secondary circuit heat supply type of a nuclear power plant under preset parameters, and the actual operating data includes the actual steam consumption of each stage high-pressure feedwater heater, the actual heat release amount of each stage high-pressure feedwater heater, the actual temperature of the high-temperature side medium outlet of each stage heat exchanger, the actual heat absorption amount of the heat supply pipe network in each stage heat exchanger, the actual condensed steam capacity of the condenser 6, and the actual feedwater flow rate of the condenser 6. The preset parameters include the parameters of the high-pressure feedwater heater, the parameters of the heat exchanger, and the parameters of the condenser.

[0030] Preset operating data of the heating device is obtained based on the secondary circuit heat supply type of the nuclear power plant under preset parameters, and the preset operating data includes the preset steam consumption of each stage high-pressure feedwater heater, the preset condensed steam amount of the condenser 6, the preset temperature of the high-temperature side medium outlet of each stage heat exchanger, and the preset feedwater flow rate of the condenser 6.

[0031] The preset parameters are adjusted so that the actual operating data and the preset operating data satisfy preset conditions.

[0032] For example, as shown in FIG. 1, when performing design calculations of the present invention, the temperatures from the high-temperature side medium outlets of the first stage heat exchanger 14, the second stage heat exchanger 15, and the third stage heat exchanger 16 are assumed in advance as follows:

[0033]

number

[0034] In the formula, T j1 , T j2 , T j3 are the temperatures of the high temperature side medium outlets of the first stage heat exchanger 14, the second stage heat exchanger 15 and the third stage heat exchanger 16, respectively, and T0 is a preset temperature.

[0035] The drain water from the three stages is mixed after being reduced in pressure by the pressure reducing valve, and the parameters of the mixed working fluid can be determined. All of the mixed drain water flows into the first stage low pressure feed water heater 8, and the steam consumption of the first stage low pressure feed water heater 8 is as follows:

[0036]

number

[0037] In the formula, h grout is the enthalpy value of the heat return water, and G cd is the preset condensed steam capacity of the condenser 6, and d hl is the increase in feedwater enthalpy of the first-stage low-pressure feedwater heater 8, and g les3 , g les2 are the steam consumption of the third-stage low-pressure feedwater heater 18 and the second-stage low-pressure feedwater heater 17, respectively, and h ss2 , h ss1 are the drain water enthalpy values ​​of the second-stage low-pressure feedwater heater 17 and the first-stage low-pressure feedwater heater 8, respectively, and eff j are the thermal efficiencies of the first stage low pressure feed water heater 8, and h lcq1 is the extracted steam enthalpy of the first stage low pressure feedwater heater 8, and g h1 , g h2 , g h3 are the flow rates of the first stage heat exchanger 14, the second stage heat exchanger 15, and the third stage heat exchanger 16, respectively, and hhav is the enthalpy value of the mixed working fluid.

[0038] As shown in Figure 1, the flow rate of the working fluid in the heat exchanger used to heat the heat supply pipe network corresponds to the steam consumption of the high-pressure feed water heater. According to the terminal temperature difference of the heat exchanger used and the initial and final parameters of the heat supply pipe network set before and after entering all the heat exchangers, the output temperature of the inlet and outlet heat supply pipe network of each stage of the heat exchanger and the high-pressure feed water heater can be easily calculated.

[0039] for example,

number

[0040] Adjusting the preset parameters so that the actual operating data and the preset operating data meet the preset conditions specifically includes: The heat exchangers of each stage are adjusted so that the actual heat dissipation amount of the high-pressure feedwater heater of each stage and the actual heat absorption amount of the heat supply pipe network in the heat exchangers of each stage meet the first preset condition.

[0041] The parameters of the high-pressure feedwater heater are adjusted so that the actual steam consumption of each stage high-pressure feedwater heater, the preset temperature of the high-temperature side medium outlet of each stage heat exchanger, the preset steam consumption of each stage high-pressure feedwater heater, and the actual temperature of the high-temperature side medium outlet of each stage heat exchanger satisfy a second preset condition.

[0042] The parameters of the condenser are adjusted so that the actual condensed steam capacity of the condenser, the actual feedwater flow rate of the condenser, the preset condensed steam capacity of the condenser, and the preset feedwater flow rate of the condenser satisfy a third preset condition.

[0043] The first preset condition is as follows:

number

[0044] Here, Q rwi represents the actual heat absorption amount of the heat supply pipe network in the ith stage heat exchanger, and Q sshi represents the actual heat dissipation amount of the i-th stage high-pressure feedwater heater.

[0045] Specific practices include:

number

[0046] In the formula, h rwiout represents the enthalpy value at the outlet of the low-temperature medium in the heat supply pipe network in the ith stage heat exchanger, and h rwiin represents the enthalpy value at the low-temperature medium inlet of the ith stage heat exchanger in the heat supply pipe network, and h sshiout represents the enthalpy value at the outlet of the heating and drain end of the i-th stage high-pressure feedwater heater, and h sshiin represents the enthalpy value at the inlet of the heating and drain end of the i-th stage high-pressure feedwater heater.

[0047] As shown in FIG. 1, the second preset condition is as follows:

number

[0048] where T j1 represents the preset temperature of the high-temperature side medium outlet of the first-stage heat exchanger 14, g1 represents the preset steam consumption of the first-stage high-pressure feedwater heater 11, and T ssh1out represents the actual temperature at the hot medium outlet of the first stage heat exchanger 14, and g hes1 represents the actual steam consumption of the first stage high pressure feed water heater 11, and T j2 represents the preset temperature of the high-temperature side medium outlet of the second-stage heat exchanger 15, g2 represents the preset steam consumption of the second-stage high-pressure feedwater heater 12, and T ssh2out represents the actual temperature at the hot medium outlet of the second stage heat exchanger 15, and g hes2 represents the actual steam consumption of the second stage high pressure feed water heater 12, and T ji represents the preset temperature of the hot medium outlet of the ith stage heat exchanger, and g i represents the preset steam consumption of the ith stage high-pressure feedwater heater, and T sshiout represents the actual temperature at the hot side outlet of the ith stage heat exchanger, and g hesi represents the actual steam consumption of the i-th stage high-pressure feedwater heater.

[0049] The third preset condition is as follows.

number

[0050] where G cd1 represents the actual condensed steam capacity of the condenser 6, and G cd represents the preset condensed steam capacity of condenser 6, and G fw1 represents the actual feedwater flow rate of the condenser 6, and G fw represents the preset feedwater flow rate of the condenser 6.

[0051] As shown in Figure 2, the existing solution to the low-pressure cylinder inlet steam heat supply is to install a steam extraction pipeline in the inlet steam pipeline of the steam turbine low-pressure cylinder 4 (i.e., the second-stage reheater outlet pipeline) among the main steam pipelines of the secondary circuit of the nuclear power plant, and extract part of the steam from the main pipeline from this steam extraction pipeline.The steam is then transported through the pipeline to the first-stage heat exchanger 14, where it exchanges heat with the heat supply network and is condensed into saturated water.

[0052] It is then transported through a pipeline to the first stage low pressure feedwater heater 8 and finally enters the condenser 6 to return to the main steam cycle process.

[0053] For example, for the low pressure cylinder inlet steam heat supply solution, the heat balance method is used to calculate the heat supply steam consumed in the solution, and the heat supply steam consumption is as follows:

[0054]

number

[0055] In the formula, ξ heat is the thermal efficiency of the first stage heat exchanger 14, and h heatin , h heatout are the enthalpy values ​​of the heated extracted steam before and after the heat exchange in the first stage heat exchanger 14, respectively,

number

[0056] Since the return water from the heat supply extracted steam is discharged to the first stage low pressure feed water heater 8, the steam consumption of the first stage low pressure feed water heater 8 is as follows:

[0057]

number

[0058] And other relevant parameters can be obtained by thermal balance method.

[0059] Figure 3 shows a solution for supplying heat from the exhaust steam of an existing high-pressure cylinder. A steam extraction pipeline is led out from the steam pipeline at the outlet of the steam turbine high-pressure cylinder 2, which is one of the main steam pipelines in the secondary circuit of a nuclear power plant. Part of the steam in the main pipeline is extracted from this steam extraction pipeline. The steam is then transported through the pipeline to the first-stage heat exchanger 14, where it exchanges heat with the heat supply network and is condensed into saturated water.

[0060] It is then transported through a pipeline to the first stage low pressure feedwater heater 8 and finally enters the condenser 6 to return to the main steam cycle process.

[0061] Each embodiment in this specification is described step by step, focusing on the differences from other embodiments, and cross-references may be made to the same and similar parts between the various embodiments.

[0062] In this specification, the principle and implementation method of the present invention are explained using specific examples, but the description of the above examples is only used to understand the method of the present invention and its core concept, and at the same time, those skilled in the art will make changes to the specific implementation and application scope based on the concept of the present invention. In summary, the contents of this specification should not be interpreted as limiting the present invention. [Explanation of symbols]

[0063] 1 steam generator 2 Steam turbine high pressure cylinder 3 Steam and water separator reheater 4 Steam turbine low pressure cylinder 5 generators 6 Condenser 7 Condensate pump 8. First stage low pressure feedwater heater 9 Degassing device 10 water supply pump 11 First stage high pressure feedwater heater 12 Second stage high pressure feedwater heater 13 Third stage high pressure feedwater heater 14 First stage heat exchanger 15 Second stage heat exchanger 16 Third stage heat exchanger 17 Second stage low pressure feedwater heater 18Third stage low pressure feedwater heater.

Claims

1. A heating device based on a secondary circuit heat supply type of a nuclear power plant, the heating device based on the secondary circuit heat supply type of the nuclear power plant including a steam turbine extraction steam heat supply device and a multi-stage heat exchanger; The steam turbine is provided with a secondary circuit heat supply system based on the secondary circuit heat supply method of a nuclear power plant, characterized in that the heat supply drain end outlets of the multi-stage high-pressure feed water heater in the steam turbine extracted steam heat supply system are respectively connected one-to-one to the high-temperature side medium inlets of the heat exchangers of each stage, the high-temperature side medium outlets of the heat exchangers of each stage are all connected to the drain end inlets of the low-pressure feed water heater in the steam turbine extracted steam heat supply system, the low-temperature side medium inlets and low-temperature side medium outlets of the heat exchangers of each stage are all connected in series to a heat supply pipe network, and the heat supply pipe network is heated by the drain water flowing from the high-pressure feed water heater of each stage to the heat exchanger of each stage.

2. 2. A heating device based on a secondary circuit heat supply type for a nuclear power plant according to claim 1, wherein a pressure reducing valve is installed between the drain end inlet of the low-pressure feed water heater in the steam turbine extraction steam heat supply device and the high-temperature side medium outlet of each stage of the heat exchanger.

3. A method for controlling a heating device based on a secondary circuit heat supply system of a nuclear power plant, which is used in the heating device based on a secondary circuit heat supply system of a nuclear power plant according to claim 1 or 2, includes: Obtain actual operation data of the heating device based on the secondary circuit heat supply type of the nuclear power plant under preset parameters, the actual operation data including the actual steam consumption of each stage high-pressure feedwater heater, the actual heat release amount of each stage high-pressure feedwater heater, the actual temperature of the high-temperature side medium outlet of each stage heat exchanger, the actual heat absorption amount of the heat supply pipe network in each stage heat exchanger, the actual condensed steam capacity of the condenser and the actual feedwater flow rate of the condenser, the preset parameters including the parameters of the high-pressure feedwater heater, the parameters of the heat exchanger and the parameters of the condenser; Obtain preset operating data of the heating device based on the secondary circuit heat supply type of the nuclear power plant under the preset parameters, and the preset operating data includes a preset steam consumption of each stage high-pressure feedwater heater, a preset condensed steam amount of the condenser, a preset temperature of the high-temperature side medium outlet of each stage heat exchanger, and a preset feedwater flow rate of the condenser; a control method for a heating device based on a secondary circuit heat supply type of a nuclear power plant, comprising adjusting the preset parameters so that the actual operation data and the preset operation data satisfy preset conditions.

4. The adjusting of the preset parameters so that the actual operation data and the preset operation data satisfy the preset conditions may specifically include: Adjusting each stage heat exchanger so that the actual heat dissipation amount of each stage high-pressure feed water heater and the actual heat absorption amount of the heat supply pipe network in each stage heat exchanger meet the first preset condition; Adjusting the parameters of the high-pressure feedwater heater so that the actual steam consumption of each stage high-pressure feedwater heater, the preset temperature of the high-temperature side medium outlet of each stage heat exchanger, the preset steam consumption of each stage high-pressure feedwater heater, and the actual temperature of the high-temperature side medium outlet of each stage heat exchanger satisfy a second preset condition; 4. The method for controlling a heating device based on the heat supply type of the secondary circuit of a nuclear power plant according to claim 3, further comprising adjusting parameters of the condenser so that the actual condensing steam capacity of the condenser, the actual feedwater flow rate of the condenser, the preset condensing steam capacity of the condenser, and the preset feedwater flow rate of the condenser satisfy a third preset condition.

5. The first preset condition is as follows: [Equation 1] Here, Q ｒｗｉ represents the actual heat absorption amount of the heat supply pipe network in the i-th stage heat exchanger, and Q ｓｓｈｉ 5. The method for controlling a heating device according to the secondary circuit heat supply type of a nuclear power plant according to claim 4, wherein: i represents the actual heat dissipation amount of the i-th stage high pressure feed water heater.

6. The second preset condition is as follows: [Equation 2] Here, T ｊ１ represents the preset temperature of the hot medium outlet of the first stage heat exchanger, and g １ represents the preset steam consumption of the first stage high pressure feed water heater, and T ｓｓｈ１ｏｕｔ represents the actual temperature at the hot medium outlet of the first stage heat exchanger, and g ｈｅｓ１ represents the actual steam consumption of the first stage high pressure feed water heater, and T ｊ２ represents the preset temperature of the hot medium outlet of the second stage heat exchanger, and g ２ represents the preset steam consumption of the second stage high pressure feed water heater, and T ｓｓｈ２ｏｕｔ represents the actual temperature at the hot medium outlet of the second stage heat exchanger, and g ｈｅｓ２ represents the actual steam consumption of the second stage high pressure feed water heater, and T ｊｉ represents the preset temperature of the hot medium outlet of the i-th stage heat exchanger, and g ｉ represents the preset steam consumption of the i-th stage high-pressure feedwater heater, and T ｓｓｈｉｏｕｔ represents the actual temperature at the hot-side medium outlet of the i-th stage heat exchanger, and g ｈｅｓｉ 5. The method for controlling a heating device based on a secondary circuit heat supply type of a nuclear power plant according to claim 4, wherein: i represents the actual steam consumption of the i-th stage high pressure feed water heater.

7. The third preset condition is as follows: [Equation 3] Here, G ｃｄ１ represents the actual condensed steam capacity of the condenser, and G ｃｄ represents the preset condensed steam capacity of the condenser, and G ｆｗ１ represents the actual feedwater flow rate of the condenser, and G ｆｗ 5. The method for controlling a heating device based on a secondary circuit heat supply type of a nuclear power plant according to claim 4, wherein: represents a preset feedwater flow rate of the condenser.

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