Heating device based on the secondary circuit heat supply form of an atomic 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 the priority of the Chinese patent application with the application number 202310737909.4 and the invention title "Heating device based on the secondary circuit heat supply mode of nuclear power plants and its control method" filed with the Chinese Patent Office on June 20, 2023, and all its contents are incorporated by reference.

Technical field

[0002] The present invention relates to the field of secondary circuit heat supply of nuclear power plants, and particularly to a heating device based on the secondary circuit heat supply mode of nuclear power plants and its control method.

Background technology

[0003] Nuclear energy, a clean and efficient form of energy, can not only be used for power generation but also achieve the purpose of heat supply with appropriate design. Currently, the research directions of nuclear energy heat supply mainly include low - temperature nuclear energy heat supply and heat supply by extracted steam from the steam turbine unit of nuclear power plants. Among them, heat supply by extracted steam from the steam turbine unit of nuclear power plants can stably supply a large amount of high - quality thermal energy with little impact on the original output of nuclear power plants. In addition, the amount of renovation work for this form of nuclear energy heat supply is small, which can improve the economic benefits and thermal efficiency of nuclear power plants at the same time, and has attracted more and more extensive 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 of the heat exchange process, the extracted steam from the steam turbine is converted into drain water after the heat exchange process and finally returns to the condenser after a series of cycles. In this form, significant changes are required in the main pipeline of the secondary circuit, which is costly.

Summary of the invention

Problems to be solved by the invention

[0005] An object of the present invention is to provide a heating device based on a secondary circuit heat supply system of a nuclear power plant and a control method thereof, which can realize heat supply without changing the main pipeline of the secondary circuit.

Means for Solving the Problems

[0006] A heating device based on a secondary circuit heat supply system of a nuclear power plant, wherein the heating device based on the secondary circuit heat supply system of the nuclear power plant includes a steam turbine extraction steam heat supply device and a multi-stage heat exchanger. 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 one-to-one to the high-temperature side medium inlets of the multi-stage heat exchangers, and 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.

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

[0008] A control method for a heating device based on a secondary circuit heat supply system of a nuclear power plant, wherein the control method for a heating device based on the secondary circuit heat supply system of a nuclear power plant is used for the heating device based on the secondary circuit heat supply system of the nuclear power plant, and the control method for a heating device based on the secondary circuit heat supply system of the nuclear power plant includes: Obtaining actual operation data of a heating device based on a secondary circuit heat supply system of a nuclear power plant under preset parameters. The actual operation data includes the actual steam consumption of each stage of high-pressure feedwater heaters, the actual heat dissipation of each stage of high-pressure feedwater heaters, the actual temperature of the high-temperature side medium outlet of each stage of heat exchangers, the actual heat absorption of the heat supply pipe network in each stage of heat exchangers, the actual condensate steam capacity of the condenser and the actual feedwater flow rate of the condenser. The preset parameters include parameters of high-pressure feedwater heaters, parameters of heat exchangers, and parameters of condensers. Obtain the preset operation data of the heating device based on the secondary circuit heat supply mode of the nuclear power plant under the preset parameters. The preset operation data includes the preset steam consumption of each stage of the high-pressure feedwater heater, the preset condensed steam amount of the condenser, the preset temperature at the outlet of the high-temperature side medium of each stage of the heat exchanger, and the preset feedwater flow rate of the condenser. Adjust the preset parameters so that the actual operation data and the preset operation data meet the preset conditions.

[0009] Specifically, adjusting the preset parameters so that the actual operation data and the preset operation data meet the preset conditions includes: Adjusting each stage of the heat exchanger so that the actual heat release amount of each stage of the high-pressure feedwater heater and the actual heat absorption amount of the heat supply pipe network in each stage of the 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 of the high-pressure feedwater heater, the preset temperature at the outlet of the high-temperature side medium of each stage of the heat exchanger, the preset steam consumption of each stage of the high-pressure feedwater heater, and the actual temperature at the outlet of the high-temperature side medium of each stage of the heat exchanger meet the second preset condition. It may also include adjusting the parameters of the condenser 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 meet the third preset condition.

[0010] Also, 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 i-th stage heat exchanger, and Q sshi represents the actual heat release amount of the i-th stage high-pressure feedwater heater.

[0013] Also, the second preset condition may be as follows.

[0014]

Number

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

[0016] Also, the third preset condition may be as follows.

[0017]

Number

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

Advantages of the Invention

[0019] According to the specific embodiments provided by the present invention, the following technical effects are disclosed: A heating device based on the secondary circuit heat supply form 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.

Brief Description of the Drawings

[0020] To more clearly explain the technical solutions in the embodiments of the present invention or 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 creative efforts.

Figure 1

Figure 2

Figure 3

Modes for Carrying Out the Invention

[0021] The following clearly and fully describes the technical solutions in the embodiments of the present invention with reference to the drawings. It is obvious that the described embodiments are only part of the embodiments of the present invention, not all of them. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative labor belong to the protection scope of the present invention.

[0022] An object of the present invention is to provide a heating device and its control method based on the secondary circuit heat supply form of a nuclear power plant that can realize heat supply without changing the main pipeline of the secondary circuit.

[0023] In order to make the above objects, features and advantages of the present invention clearer and easier to understand, the present invention will be further described in detail below with reference to the drawings and specific embodiments.

Embodiment

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

[0025] 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 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 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 connected in series to the heat supply pipeline network.

[0026] Pressure reducing valves are installed between the drain end inlets of the low-pressure feedwater heaters in the steam turbine extraction steam heat supply device and the high-temperature side medium outlets of each stage of the heat exchangers.

[0027] As shown in FIG. 1, the new steam path in the heating device based on the secondary circuit heat supply mode of the nuclear power plant returns to the steam generator 1 through the steam generator 1, the high-pressure cylinder 2 of the steam turbine, the steam and water separation reheater 3, the low-pressure cylinder 4 of the steam turbine, the condenser 6, the condensate pump 7, the first-stage low-pressure feedwater heater 8, the second-stage low-pressure feedwater heater 17, the third-stage low-pressure feedwater heater 18, the deaerator 9, the feedwater pump 10, 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. And the low-pressure cylinder 4 of the steam turbine is connected to the generator 5 and used to supply power.

[0028] The present invention heats a 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, it is to improve 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 design of the original drain ports is shown in FIGS. 2 and 3). Connect the drain end outlet of the third-stage high-pressure feedwater heater 13 to the high-temperature side medium inlet of the third-stage heat exchanger 16, connect the drain end outlet of the second-stage high-pressure feedwater heater 12 to the second-stage heat exchanger 15, and connect the drain end outlet of the first-stage high-pressure feedwater heater 11 to the high-temperature side medium inlet of the first-stage heat exchanger 14. In this way, the drain water from the third-stage high-pressure feedwater heater 13 flows into the third-stage heat exchanger 16, the drain water from the second-stage high-pressure feedwater heater 12 flows into the second-stage heat exchanger 15, and the drain water from the first-stage high-pressure feedwater heater 11 flows into the first-stage heat exchanger 14. Heat-treat the heat supply pipe network connected in series to the low-temperature side medium inlet and the low-temperature side medium outlet of the first-stage heat exchanger 14, the second-stage heat exchanger 15, and the third-stage heat exchanger 16. After the heating is completed, the drain water flows into the pressure reducing valve from the high-temperature side medium outlet of each of the first-stage heat exchanger 14, the second-stage heat exchanger 15, and the third-stage heat exchanger 16. After being depressurized to an appropriate pressure by the pressure reducing valve, the drain water is mixed and refluxed to the drain port inlet of the first-stage low-pressure feedwater heater 8. Thereby, the drain water from the entire device at this stage continues to flow in the secondary circuit main pipeline and finally enters the condenser 6 for the next cycle, so that the influence on the secondary circuit main pipeline is small. In FIG. 1, only three-stage high-pressure feedwater heaters, three-stage low-pressure feedwater heaters, and three-stage heat exchangers are provided. Actually, multiple-stage high-pressure feedwater heaters, multiple-stage low-pressure feedwater heaters, and multiple-stage heat exchangers can be provided, and there is no limit to the number of stages of the high-pressure feedwater heaters, low-pressure feedwater heaters, and heat exchangers.

[0029] A control method for a heating device based on the secondary circuit heat supply form of a nuclear power plant, wherein the control method for the heating device based on the secondary circuit heat supply form of the nuclear power plant is used in the heating device based on the secondary circuit heat supply form of the nuclear power plant, and the control method for the heating device based on the secondary circuit heat supply form of the nuclear power plant includes the following. As shown in Fig. 1, actual operation data of a heating device based on the secondary circuit heat supply mode of a nuclear power plant under preset parameters is acquired. The actual operation data includes the actual steam consumption of each stage of high-pressure feedwater heaters, the actual heat release of each stage of high-pressure feedwater heaters, the actual temperature at the outlet of the high-temperature side medium of each stage of heat exchangers, the actual heat absorption of the heat supply pipe network in each stage of heat exchangers, the actual condensed steam capacity of the condenser 6 and the actual feedwater flow rate of the condenser 6. The preset parameters include parameters of high-pressure feedwater heaters, parameters of heat exchangers, and parameters of condensers.

[0030] Preset operation data of a heating device based on the secondary circuit heat supply mode of a nuclear power plant under preset parameters is acquired. The preset operation data includes the preset steam consumption of each stage of high-pressure feedwater heaters, the preset condensed steam amount of the condenser 6, the preset temperature at the outlet of the high-temperature side medium of each stage of heat exchangers, and the preset feedwater flow rate of the condenser 6.

[0031] Adjust the preset parameters so that the actual operation data and the preset operation data meet the preset conditions.

[0032] For example, as shown in Fig. 1, when performing the design calculation of the present invention, assume the temperatures from the outlets of the high-temperature side media of the first-stage heat exchanger 14, the second-stage heat exchanger 15, and the third-stage heat exchanger 16 as follows in advance.

[0033]

Number

[0034] wherein, T j1 、T j2 、T j3 are the temperatures at the outlets of the high-temperature side media of the first-stage heat exchanger 14, the second-stage heat exchanger 15, and the third-stage heat exchanger 16 respectively, and T0 is the preset temperature.

[0035] The drain water in three stages is depressurized by a pressure reducing valve and then mixed, and the parameters of the mixed working fluid can be known. All the mixed drain water flows into the first-stage low-pressure feedwater heater 8, and the steam consumption of the first-stage low-pressure feedwater heater 8 is as follows.

[0036]

Number

[0037] In the formula, h grout is the enthalpy value of the heat-supplied return water, G cd is the preset condensate steam capacity of the condenser 6, d hl is the increase in the feedwater enthalpy of the first-stage low-pressure feedwater heater 8, g les3 , g les2 are the steam consumptions of the third-stage low-pressure feedwater heater 18 and the second-stage low-pressure feedwater heater 17 respectively, 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, eff j is the thermal efficiency of the first-stage low-pressure feedwater heater 8 respectively, h lcq1 is the extraction steam enthalpy of the first-stage low-pressure feedwater heater 8, 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 FIG. 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 feedwater heater, and according to the terminal temperature difference of the heat exchanger used and the initial parameters and final parameters of the set heat supply pipe network before and after entering all the heat exchangers, the inlet and outlet heat supply pipe networks of each stage of the heat exchanger and the output temperature of the high-pressure feedwater heater can be easily obtained.

[0039] For example,

Number

[0040] Adjusting the preset parameters so that the actual operation data and the preset operation data meet the preset conditions specifically includes the following. Adjust the heat exchangers of each stage so that the actual heat dissipation of each stage of high-pressure feedwater heater and the actual heat absorption of the heat supply pipe network in each stage of heat exchanger meet the first preset condition.

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

[0042] Adjust the parameters of the condenser 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 meet the third preset condition.

[0043] The first preset condition is as follows.

Number

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

[0045] Specific practice is as follows.

Number

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

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

Number

[0048] Here, 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 of the high-temperature side medium outlet of the first-stage heat exchanger 14, and g hes1 represents the actual steam consumption of the first-stage high-pressure feedwater 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 of the high-temperature side medium outlet of the second-stage heat exchanger 15, and g hes2 represents the actual steam consumption of the second-stage high-pressure feedwater heater 12, and T ji represents the preset temperature of the high-temperature side 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 of the high-temperature side medium outlet of the i-th 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] Here, G cd1 represents the actual condensed steam capacity of the condenser 6, and G cd represents the preset condensed steam capacity of the condenser 6, and G fw1 represents the actual feed water flow rate of the condenser 6, and G fw represents the preset feed water flow rate of the condenser 6.

[0051] As shown in Figure 2, the solution for the existing 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 outlet pipeline of the second-stage reheater) in the main steam pipeline of the secondary circuit of the nuclear power plant, and to derive a part of the steam from the main pipeline. Then, the steam is transported through the pipeline to the first-stage heat exchanger 14, exchanges heat with the heat supply network, and is condensed into saturated water in the first-stage heat exchanger 14.

[0052] Then, it is transported through the pipeline to the first-stage low-pressure feed water heater 8 and finally enters the condenser 6 to return to the main steam cycle process.

[0053] For example, in the case of the low-pressure cylinder inlet steam heat supply solution, the heat balance method is used to calculate the heat supply steam consumed by the solution, and the consumption of the heat supply steam 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 heating extraction steam before and after heat exchange in the first-stage heat exchanger 14 respectively,

Number

[0056] Since the return water from the heat supply extraction steam is discharged into the first-stage low-pressure feedwater heater 8, the steam consumption of the first-stage low-pressure feedwater heater 8 is as follows.

[0057]

Number

[0058] And other related parameters can be obtained by the heat balance method.

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

[0060] Then, it is transported through the 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 the same parts and similar parts among various embodiments can be referred to each other.

[0062] In this specification, specific examples are used to explain the principles and implementation methods of the present invention. However, the description of the above embodiments is only used to understand the method and the central concept of the present invention. At the same time, for those skilled in the art, based on the concept of the present invention, changes will occur in specific implementations and application scopes. In summary, the content of this specification should not be construed as limiting the present invention.

Explanation of Signs

[0063] 1 Steam generator 2 High-pressure cylinder of steam turbine 3 Steam and water separation reheater 4 Steam turbine low-pressure cylinder 5 Generator 6 Condenser 7 Condensate pump 8 First-stage low-pressure feedwater heater 9 Deaerator 10 Feedwater 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 18 Third-stage low-pressure feedwater heater.

Claims

1. A heating device based on the secondary circuit heat supply form of a nuclear power plant, wherein the heating device based on the secondary circuit heat supply form of the nuclear power plant includes a steam turbine extraction steam heat supply device and a multi-stage heat exchanger, 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 one-to-one to the high-temperature side medium inlets of the multi-stage heat exchangers, and 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. A heating device based on the secondary circuit heat supply form of a nuclear power plant, characterized in that.

2. A pressure reducing valve is installed between the drain end inlet of the low-pressure feedwater heater in the steam turbine extraction steam heat supply device and the high-temperature side medium outlet of each stage of the heat exchanger. The heating device based on the secondary circuit heat supply form of the nuclear power plant described in Claim 1, characterized in that.

3. A control method for a heating device based on the secondary circuit heat supply form of a nuclear power plant, wherein the control method for the heating device based on the secondary circuit heat supply form of the nuclear power plant used in the heating device based on the secondary circuit heat supply form of the nuclear power plant described in Claim 1 or 2 includes, Obtain the actual operating data of the heating device based on the secondary circuit heat supply form of the nuclear power plant under the preset parameters. The actual operating data includes the actual steam consumption of each stage of the high-pressure feedwater heater, the actual heat dissipation of each stage of the high-pressure feedwater heater, the actual temperature of the high-temperature side medium outlet of each stage of the heat exchanger, the actual heat absorption of the heat supply pipe network in each stage of the heat exchanger, the actual condensate steam capacity of the condenser and the actual feedwater flow rate of the condenser. The preset parameters include the parameters of the high-pressure feedwater heater, the parameters of the heat exchanger, and the parameters of the condenser. Obtain the preset operating data of the heating device based on the secondary circuit heat supply form of the nuclear power plant under the preset parameters. The preset operating data includes the preset steam consumption of each stage of the high-pressure feedwater heater, the preset condensate steam amount of the condenser, the preset temperature of the high-temperature side medium outlet of each stage of the heat exchanger, and the preset feedwater flow rate of the condenser. A control method for a heating device based on a secondary circuit heat supply system of a nuclear power plant, characterized by including adjusting the preset parameters so that the actual operation data and the preset operation data satisfy the preset conditions.

4. Specifically, adjusting the preset parameters so that the actual operation data and the preset operation data satisfy the preset conditions includes: adjusting each stage of heat exchanger so that the actual heat dissipation of each stage of high-pressure feedwater heater and the actual heat absorption of the heat supply pipeline network in each stage of heat exchanger satisfy the first preset condition; adjusting the parameters of the high-pressure feedwater heater so that the actual steam consumption of each stage of high-pressure feedwater heater, the preset temperature of the high-temperature side medium outlet of each stage of heat exchanger, the preset steam consumption of each stage of high-pressure feedwater heater, and the actual temperature of the high-temperature side medium outlet of each stage of heat exchanger satisfy the second preset condition; A control method for a heating device based on a secondary circuit heat supply system of a nuclear power plant according to claim 3, characterized by including adjusting the parameters of the condenser 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 the third preset condition.

5. The first preset condition is as follows: 【Number 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 represents the actual heat dissipation amount of the i-th stage high-pressure feedwater heater. A control method for a heating device based on the secondary circuit heat supply mode of a nuclear power plant according to claim 4, characterized by the above.

6. The second preset condition is as follows: 【Number 2】 Here, T ｊ１ represents the preset temperature at the high-temperature side medium outlet of the first-stage heat exchanger, and g １ represents the preset steam consumption of the first-stage high-pressure feedwater heater, T ｓｓｈ１ｏｕｔ represents the actual temperature at the high-temperature side medium outlet of the first-stage heat exchanger, and g ｈｅｓ１ represents the actual steam consumption of the first-stage high-pressure feedwater heater, T ｊ２ represents the preset temperature at the high-temperature side medium outlet of the second-stage heat exchanger, and g ２ represents the preset steam consumption of the second-stage high-pressure feedwater heater, T ｓｓｈ２ｏｕｔ represents the actual temperature at the high-temperature side medium outlet of the second-stage heat exchanger, and g ｈｅｓ２ represents the actual steam consumption of the second-stage high-pressure feedwater heater, T ｊｉ represents the preset temperature at the high-temperature side 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, T ｓｓｈｉｏｕｔ represents the actual temperature at the high-temperature side medium outlet of the i-th stage heat exchanger, and g ｈｅｓｉ represents the actual steam consumption of the i-th stage high-pressure feedwater heater, and is characterized in that it is a control method of a heating device based on the secondary circuit heat supply form of a nuclear power plant according to claim 4.

7. The third preset condition is as follows: 【Mathematics 3】 Here, G ｃｄ１ represents the actual condensing steam capacity of the condenser, G ｃｄ represents the preset condensing steam capacity of the condenser, G ｆｗ１ represents the actual feed water flow rate of the condenser, G ｆｗ represents the preset feed water flow rate of the condenser, and is characterized in that it is a control method for a heating device based on the secondary circuit heat supply form of a nuclear power plant according to claim 4.

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