Heating device based on secondary circuit heating form of nuclear power plant and control method thereof

Abstract

The invention discloses a heating device based on the secondary circuit heating form of a nuclear power plant and a control method thereof, and relates to the field of secondary circuit heating of a nuclear power plant; the heating device based on the secondary circuit heating form of a nuclear power plant comprises: the heat drain outlets of the multi-stage high-pressure feedwater heater in the steam turbine extraction heating device are respectively connected to the hot side medium inlet of the multi-stage heat exchanger in a one-to-one correspondence, the hot side medium outlets of the multi-stage heat exchanger are all connected to the drain inlet of the low-pressure feedwater heater in the steam turbine extraction heating device, and the cold side medium inlet and the cold side medium outlet of the multi-stage heat exchanger are all connected in series to the heating pipe network. The invention can realize heating without changing the secondary circuit main pipeline, reducing the cost of modifying the secondary circuit pipeline and the impact on the working medium in the main steam pipeline.

Description

Technical Field

[0001] The invention relates to the field of secondary circuit heating in nuclear power plants, and in particular to a heating device based on the secondary circuit heating form of nuclear power plants and a control method thereof. Background Art

[0002] As a clean and efficient form of energy, nuclear energy can not only be used for power generation, but also for heating through appropriate design. At present, the research directions of nuclear energy heating mainly include low-temperature nuclear energy heating reactors and steam extraction heating of nuclear power plant steam turbine units. Among them, steam extraction heating of nuclear power plant steam turbine units can provide stable, large amounts of high-quality thermal energy on the basis of having little impact on the original electric power of the nuclear power plant. The transformation amount of this nuclear energy heating form is relatively small. At the same time, it can improve the economic benefits and thermal efficiency of nuclear power plants to a certain extent, and has received more and more attention and research.

[0003] At present, the main form of heating in nuclear power plants is to use a certain stage of steam extraction from the steam turbine to heat the circulating water in the heat network to a specified temperature. In this stage of heat exchange, the steam extraction from the steam turbine is converted into water after the heat exchange process, and finally flows back to the condenser after a series of cycles. This form makes significant changes to the secondary circuit main pipeline and is costly. Summary of the invention

[0004] The purpose of the present invention is to provide a heating device based on the secondary circuit heating form of a nuclear power plant and a control method thereof, which can realize heating without changing the secondary circuit main pipeline.

[0005] To achieve the above object, the present invention provides the following solutions:

[0006] A heating device based on the secondary circuit heating form of a nuclear power plant, the heating device based on the secondary circuit heating form of a nuclear power plant comprises: a steam turbine extraction heating device and a multi-stage heat exchanger;

[0007] The heat supply drain outlets of the multi-stage high-pressure feedwater heaters in the steam turbine extraction steam heating device are respectively connected one-to-one with the hot side medium inlets of the multi-stage heat exchangers, the hot 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 heating device, and the cold side medium inlets and cold side medium outlets of the multi-stage heat exchangers are all connected in series to the heating pipe network.

[0008] Optionally, a pressure reducing valve is provided between the drain end inlet of the low-pressure feedwater heater in the steam turbine extraction heating device and the hot side medium outlet of each stage of the heat exchanger.

[0009] A control method for a heating device based on a secondary heating circuit of a nuclear power plant, the control method for a heating device based on a secondary heating circuit of a nuclear power plant is applied to the above-mentioned heating device based on a secondary heating circuit of a nuclear power plant, the control method for a heating device based on a secondary heating circuit of a nuclear power plant comprises:

[0010] Acquire the actual operation data of the heating device based on the secondary circuit heating form of the nuclear power plant under preset parameters; the actual operation data include: the actual steam consumption of each stage of the high-pressure feedwater heater, the actual heat release of each stage of the high-pressure feedwater heater, the actual temperature of the hot side medium outlet of each stage of the heat exchanger, the actual heat absorption of the heating pipe network in each stage of the heat exchanger, the actual condensation amount 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;

[0011] Calculate and obtain preset operating data of a heating device based on the secondary circuit heating form of a nuclear power plant under preset parameters, wherein the preset operating data includes: a preset steam consumption of each stage of high-pressure feedwater heater, a preset condensation amount of the condenser, a preset temperature of the hot side medium outlet of each stage of the heat exchanger, and a preset feedwater flow rate of the condenser;

[0012] The preset parameters are adjusted so that the actual operation data and the preset operation data meet preset conditions.

[0013] Optionally, the adjusting the preset parameters so that the actual operation data and the preset operation data meet preset conditions specifically includes:

[0014] Adjust the parameters of each stage of heat exchanger so that the actual heat release of each stage of high-pressure feedwater heater and the actual heat absorption of the heating pipe network in each stage of heat exchanger meet the first preset condition;

[0015] Adjust 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 of the hot side medium outlet of each stage of the heat exchanger, the preset steam consumption of each stage of the high-pressure feedwater heater and the actual temperature of the hot side medium outlet of each stage of the heat exchanger meet the second preset condition;

[0016] The parameters of the condenser are adjusted so that the actual condensed steam volume of the condenser, the actual feed water flow rate of the condenser, the preset condensed steam volume of the condenser and the preset feed water flow rate of the condenser meet the third preset condition.

[0017] Optionally, the first preset condition is:

[0018]

[0019] Among them, Q rwi It represents the actual heat absorption of the heating network in the i-th stage heat exchanger; Q sshiRepresents the actual heat release of the i-th stage high-pressure feedwater heater.

[0020] Optionally, the second preset condition is:

[0021]

[0022] Among them, T j1 Indicates the preset temperature of the hot side medium outlet of the first stage heat exchanger; g 1 Indicates the preset steam consumption of the first stage high pressure feedwater heater; T ssh1out Indicates the actual temperature of the hot side medium outlet of the first stage heat exchanger; g hes1 Indicates the actual steam consumption of the first stage high pressure feedwater heater; T j2 Indicates the preset temperature of the hot side medium outlet of the second stage heat exchanger; g 2 Indicates the preset steam consumption of the second stage high pressure feedwater heater; T ssh2out Indicates the actual temperature of the hot side medium outlet of the second stage heat exchanger; g hes2 Indicates the actual steam consumption of the second-stage high-pressure feedwater heater; T ji Indicates the preset temperature of the hot 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 Indicates the actual temperature of the hot side medium outlet of the i-th stage heat exchanger; g hesi Indicates the actual steam consumption of the i-th stage high-pressure feedwater heater.

[0023] Optionally, the third preset condition is:

[0024]

[0025] Among them, G cd1 Indicates the actual condensation volume of the condenser; G cd Indicates the preset condensation volume of the condenser; G fw1 Indicates the actual water flow rate of the condenser; G fw Indicates the preset feed water flow rate of the condenser.

[0026] According to the specific embodiments provided by the present invention, the present invention discloses the following technical effects:

[0027] The heating device based on the secondary circuit heating form of the nuclear power plant includes: the heat drain outlets of the multi-stage high-pressure feedwater heater in the steam turbine extraction heating device are respectively connected to the hot side medium inlet of the multi-stage heat exchanger in a one-to-one correspondence, the hot side medium outlets of the multi-stage heat exchanger are all connected to the drain inlet of the low-pressure feedwater heater in the steam turbine extraction heating device, and the cold side medium inlet and the cold side medium outlet of the multi-stage heat exchanger are all connected in series to the heating pipe network. The present invention can realize heating without changing the secondary circuit main pipeline, reducing the cost of modifying the secondary circuit pipeline and the impact on the working medium in the main steam pipeline. BRIEF DESCRIPTION OF THE DRAWINGS

[0028] In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings required for use in the embodiments will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present invention. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying creative work.

[0029] Figure 1 This is a structural diagram of a heating device based on a secondary circuit heating form of a nuclear power plant in Example 1 of the present invention;

[0030] Figure 2 This is a structural diagram of a steam heating device for a low-pressure cylinder inlet of a nuclear power plant steam turbine in Example 1 of the present invention;

[0031] Figure 3 This is a structural diagram of the nuclear power plant steam turbine high-pressure cylinder exhaust steam heating device in Example 1 of the present invention.

[0032] Explanation of symbols:

[0033] 1. Steam generator; 2. Steam turbine high-pressure cylinder; 3. Steam-water separator reheater; 4. Steam turbine low-pressure cylinder; 5. Generator; 6. Condenser; 7. Condensate pump; 8. 1st stage low-pressure feedwater heater; 9. Deaerator; 10. Feedwater pump; 11. 1st stage high-pressure feedwater heater; 12. 2nd stage high-pressure feedwater heater; 13. 3rd stage high-pressure feedwater heater; 14. 1st stage heat exchanger; 15. 2nd stage heat exchanger; 16. 3rd stage heat exchanger; 17. 2nd stage low-pressure feedwater heater; 18. 3rd stage low-pressure feedwater heater. DETAILED DESCRIPTION

[0034] The following will be combined with the drawings in the embodiments of the present invention to clearly and completely describe the technical solutions in the embodiments of the present invention. Obviously, the described embodiments are only part of the embodiments of the present invention, not all of the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0035] The purpose of the present invention is to provide a heating device based on the secondary circuit heating form of a nuclear power plant and a control method thereof, so as to realize heating without changing the secondary circuit main pipeline.

[0036] In order to make the above-mentioned objects, features and advantages of the present invention more obvious and easy to understand, the present invention is further described in detail below with reference to the accompanying drawings and specific embodiments.

[0037] Example 1

[0038] The heating device based on the secondary circuit heating form of the nuclear power plant comprises: a steam turbine extraction heating device and a multi-stage heat exchanger.

[0039] The heat supply drain outlets of the multi-stage high-pressure feedwater heaters in the steam turbine extraction steam heating device are respectively connected one-to-one with the hot side medium inlets of the multi-stage heat exchangers, the hot side medium outlets of the multi-stage heat exchangers are connected with the drain inlets of the low-pressure feedwater heaters in the steam turbine extraction steam heating device, and the cold side medium inlets and cold side medium outlets of the multi-stage heat exchangers are connected in series to the heating pipe network.

[0040] A pressure reducing valve is provided between the drain end inlet of the low-pressure feedwater heater in the steam turbine extraction heating device and the hot side medium outlet of each stage of the heat exchanger.

[0041] like Figure 1 As shown, the new steam path in the heating device based on the secondary circuit heating form of the nuclear power plant is the steam generator 1, the high-pressure cylinder of the steam turbine 2, the steam-water separator reheater 3, the low-pressure cylinder of the steam turbine 4, the condenser 6, the condensate pump 7, the first-stage low-pressure feed water 8, the second-stage low-pressure feed water heater 17, the third-stage low-pressure feed water heater 18, the deaerator 9, the feed water pump 10, the third-stage high-pressure feed water heater 13, the second-stage high-pressure feed water heater 12, the first-stage high-pressure feed water heater 11 and then back to the steam generator 1. And the low-pressure cylinder of the steam turbine 4 is connected to the generator 5 for providing power.

[0042] The present invention heats the heating pipe network by draining the third-stage high-pressure water heater 13, the second-stage high-pressure water heater 12, and the first-stage high-pressure water heater 11, mainly by replacing the original drain ports (the design of the original drain ports is as follows) of the third-stage high-pressure water heater 13, the second-stage high-pressure water heater 12, and the first-stage high-pressure water heater 11 with the original drain ports. Figure 2 and Figure 3The improvement is made by connecting the drain end outlet of the third-stage high-pressure feedwater heater 13 to the hot side medium inlet of the third-stage heat exchanger 16, connecting the drain end outlet of the second-stage high-pressure feedwater heater 12 to the hot side medium inlet of the second-stage heat exchanger 15, and connecting the drain end outlet of the first-stage high-pressure feedwater heater 11 to the hot side medium inlet of the first-stage heat exchanger 14, so that the drain of the third-stage high-pressure feedwater heater 13 flows into the third-stage heat exchanger 16, the drain of the second-stage high-pressure feedwater heater 12 flows into the second-stage heat exchanger 15, and the drain of the first-stage high-pressure feedwater heater 11 flows into the first-stage heat exchanger 14, The heating pipe network connected in series at the cold side medium inlet and cold side medium outlet of the first-stage heat exchanger 14, the second-stage heat exchanger 15 and the third-stage heat exchanger 16 is heated. After the heating is completed, the drain flows into the pressure reducing valve from the hot side medium outlet of the first-stage heat exchanger 14, the second-stage heat exchanger 15 and the third-stage heat exchanger 16 respectively. After the pressure reducing valve reduces the pressure to an appropriate value, the drain is mixed together and flows back to the drain end inlet of the first-stage low-pressure feed water heater 8, so that the drain of the entire device can continue to circulate in the secondary circuit main pipeline and finally enter the condenser 6 for the next round of circulation, which has little impact on the secondary circuit main pipeline. Figure 1 Only three-stage high-pressure feedwater heaters, three-stage low-pressure feedwater heaters and three-stage heat exchangers are provided. In actual applications, multiple stages of high-pressure feedwater heaters, multiple stages of low-pressure feedwater heaters and multiple stages of heat exchangers can be set, and the number of stages of high-pressure feedwater heaters, low-pressure feedwater heaters and heat exchangers is not limited.

[0043] A control method for a heating device based on a secondary heating circuit of a nuclear power plant, the control method for a heating device based on a secondary heating circuit of a nuclear power plant is applied to the heating device based on a secondary heating circuit of a nuclear power plant, the control method for a heating device based on a secondary heating circuit of a nuclear power plant comprises:

[0044] like Figure 1 As shown, the actual operation data of the heating device based on the secondary circuit heating form of the nuclear power plant under the preset parameters are obtained; the actual operation data include: the actual steam consumption of each stage of high-pressure feed water heater, the actual heat release of each stage of high-pressure feed water heater, the actual temperature of the hot side medium outlet of each stage of heat exchanger, the actual heat absorption of the heating pipeline network in each stage of heat exchanger, the actual condensation amount of condenser 6 and the actual feed water flow of condenser 6; the preset parameters include the parameters of the high-pressure feed water heater, the parameters of the heat exchanger and the parameters of the condenser.

[0045] The preset operating data of the heating device based on the secondary circuit heating form of the nuclear power plant under the preset parameters are calculated and obtained, and the preset operating data include: the preset steam consumption of each stage of high-pressure feed water heater, the preset condensation amount of condenser 6, the preset temperature of the hot side medium outlet of each stage of heat exchanger and the preset feed water flow rate of condenser 6.

[0046] The preset parameters are adjusted so that the actual operation data and the preset operation data meet preset conditions.

[0047] For example, Figure 1 As shown, when designing and calculating the present invention, the temperature of the hot side medium outlet from the first stage heat exchanger 14, the second stage heat exchanger 15 and the third stage heat exchanger 16 is assumed in advance:

[0048] T j1 =T j2 =T j3 =T 0 ;

[0049] Where, T j1 ,T j2 ,T j3 ——respectively, the temperature of the hot side medium outlet of the first stage heat exchanger 14, the second stage heat exchanger 15 and the third stage heat exchanger 16; T 0 ——Preset temperature.

[0050] The three-stage drain is mixed after being reduced in pressure by the pressure reducing valve, and the parameters of the mixed working medium can be known. The mixed drain all enters the first-stage low-pressure feedwater heater 8, and the steam consumption of the first-stage low-pressure feedwater heater 8 is:

[0051]

[0052] In the formula, G cd ——Condensate volume of condenser 6; dh l ——1st stage low pressure feed water heater 8 feed water enthalpy rise; g les3 ,g les2 ——Steam consumption of the third-stage low-pressure feedwater heater 18 and the second-stage low-pressure feedwater heater 17; h ss2 ,h ss1 ——Drainage enthalpy of the second-stage low-pressure feedwater heater 17 and the first-stage low-pressure feedwater heater 8; eff j ——Thermal efficiency of the first stage low pressure feed water heater 8; h lcq1 —— extraction enthalpy of the first stage low pressure feed water heater 8; g h1 ,g h2 ,g h3 ——respectively the flow rates of the first stage heat exchanger 14, the second stage heat exchanger 15 and the third stage heat exchanger 16; h av ——Enthalpy of the working fluid after mixing.

[0053] like Figure 1As shown, the working fluid flow rate used to heat the heating network in the heat exchanger is equivalent to the steam consumption of the high-pressure feedwater heater. According to the end difference of the heat exchanger used and the initial and final parameters of the heating network before and after entering all heat exchangers, the output temperature of the heating network at the inlet and outlet of each stage of the heat exchanger and the high-pressure feedwater heater can be easily obtained.

[0054] For example:

[0055] T ssh1out =T rw1out +T duancha ;

[0056] Where, T ssh1out represents the actual temperature of the hot side medium outlet of the first stage heat exchanger 14, T rw1out ,T duancha ——respectively, they are the temperature of the cold side medium outlet of the first stage heat exchanger 14 and the end difference of the first stage heat exchanger 14.

[0057] Adjusting the preset parameters so that the actual operation data and the preset operation data meet the preset conditions specifically includes:

[0058] The parameters of each stage of heat exchanger are adjusted so that the actual heat release of each stage of high-pressure feedwater heater and the actual heat absorption of the heating pipe network in each stage of heat exchanger meet the first preset condition.

[0059] Adjust 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 of the hot side medium outlet of each stage of the heat exchanger, the preset steam consumption of each stage of the high-pressure feedwater heater and the actual temperature of the hot side medium outlet of each stage of the heat exchanger meet the second preset condition.

[0060] The parameters of the condenser are adjusted so that the actual condensed steam volume of the condenser, the actual feed water flow rate of the condenser, the preset condensed steam volume of the condenser and the preset feed water flow rate of the condenser meet the third preset condition.

[0061] The first precondition is:

[0062]

[0063] Among them, Q rwi It represents the actual heat absorption of the heating network in the i-th stage heat exchanger; Q sshi Represents the actual heat release of the i-th stage high-pressure feedwater heater.

[0064] In actual practice,

[0065] Q rwi =h rwiout -h rwiin ;

[0066] Q sshi =hsshiout -h sshiin ;

[0067] Among them, h rwiout It represents the enthalpy value of the cold side medium outlet of the i-th stage heat exchanger in the heating network; h rwiin It represents the enthalpy value of the cold side medium inlet of the i-th stage heat exchanger in the heating network; h sshiout represents the enthalpy value of the outlet of the heat drain end of the i-th stage high-pressure feedwater heater; h sshiin It represents the enthalpy value at the inlet of the heat drain end of the i-th stage high-pressure feedwater heater.

[0068] like Figure 1 As shown, the second preset condition is:

[0069]

[0070] Among them, T j1 represents the temperature of the hot side medium outlet of the first stage heat exchanger 14; g 1 represents the preset steam consumption of the first stage high pressure feed water heater 11; T ssh1out Indicates the actual temperature of the hot side medium outlet of the first stage heat exchanger 14; g hes1 Indicates the actual steam consumption of the first stage high pressure feed water heater 11; T j2 represents the temperature of the hot side medium outlet of the second stage heat exchanger 15; g 2 represents the preset steam consumption of the second stage high pressure feed water heater 12; T ssh2out Indicates the actual temperature of the hot side medium outlet of the second stage heat exchanger 15; g hes2 Indicates the actual steam consumption of the second stage high pressure feed water heater 12; T ji represents the temperature of the hot 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 Indicates the actual temperature of the hot side medium outlet of the i-th stage heat exchanger; g hesi Indicates the actual steam consumption of the i-th stage high-pressure feedwater heater.

[0071] The third precondition is:

[0072]

[0073] Among them, G cd1 Indicates the actual condensation amount of condenser 6; G cd Indicates the preset condensation volume of condenser 6; G fw1 Indicates the actual water flow rate of condenser 6; G fw Indicates the preset feed water flow rate of condenser 6.

[0074] like Figure 2As shown in the figure, it is the original low-pressure cylinder inlet steam heating scheme, in which a steam extraction pipeline is set in the steam pipeline of the low-pressure cylinder 4 inlet of the steam turbine in the secondary circuit main steam pipeline of the nuclear power plant (i.e., the outlet pipeline of the second-stage reheater), where a part of the steam in the main steam pipeline is led out, and transported to the first-stage heat exchanger 14 through the pipeline, heat exchanged with the heating pipe network, and condensed into saturated water in the first-stage heat exchanger 14.

[0075] It is transported to the first-stage low-pressure feed water heater 8 through a pipeline, and finally enters the condenser 6 and returns to the main steam cycle process.

[0076] For example, the low-pressure cylinder inlet steam heating scheme uses the heat balance method to calculate the heating steam consumed by the scheme. The consumption of heating extraction steam is:

[0077]

[0078] In the formula, ξ heat ——Thermal efficiency of the first stage heat exchanger 14; h heatin ,h heatout are respectively the enthalpy values ​​of the heating extraction steam before and after heat exchange in the first stage heat exchanger 14; The amount of heat consumed by the heating network per second.

[0079] Since the return water of the heating 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 becomes:

[0080]

[0081] h grout ——Heating return water enthalpy, other relevant parameters can be obtained by the heat balance method.

[0082] like Figure 3 The figure shows a high-pressure cylinder exhaust steam heating scheme, in which a steam extraction pipe is led out from the outlet steam pipe of the high-pressure cylinder 2 of the steam turbine in the secondary circuit main steam pipe of the nuclear power plant, where part of the steam from the main steam pipe is led out and transported to the first-stage heat exchanger 14 through the pipe, for heat exchange with the heating network, and condensed into saturated water in the first-stage heat exchanger 14.

[0083] It is transported to the first-stage low-pressure feed water heater 8 through a pipeline, and finally enters the condenser 6 and returns to the main steam cycle process.

[0084] The various embodiments in this specification are described in a progressive manner, and each embodiment focuses on the differences from other embodiments. The same or similar parts between the various embodiments can be referenced to each other.

[0085] The principles and implementation methods of the present invention are described in this article using specific examples. The description of the above embodiments is only used to help understand the method and core idea of ​​the present invention. At the same time, for those skilled in the art, according to the idea of ​​the present invention, there will be changes in the specific implementation methods and application scope. In summary, the content of this specification should not be understood as limiting the present invention.

Claims

1. A heating device based on the secondary circuit heating form of a nuclear power plant, characterized in that: The heating device based on the secondary circuit heating form of the nuclear power plant includes: a steam turbine extraction heating device and a multi-stage heat exchanger; The heat drain outlets of the multi-stage high-pressure feedwater heaters in the steam turbine extraction heating device are respectively connected to the hot side medium inlets of the multi-stage heat exchangers in a one-to-one correspondence, and the hot side medium outlets of the multi-stage heat exchangers are all connected to the drain inlet of the low-pressure feedwater heater in the steam turbine extraction heating device, so that the drain of the whole device continues to flow in the secondary circuit main pipeline and finally enters the condenser for the next cycle, and the cold side medium inlet and cold side medium outlet of the multi-stage heat exchanger are all connected in series to the heating network; A pressure reducing valve is provided between the drain end inlet of the low-pressure feedwater heater in the steam turbine extraction heating device and the hot side medium outlet of each stage of the heat exchanger.

2. A control method for a heating device based on a secondary circuit heating form of a nuclear power plant, characterized in that: The control method of the heating device based on the secondary circuit heating form of the nuclear power plant is applied to the heating device based on the secondary circuit heating form of the nuclear power plant described in claim 1, and the control method of the heating device based on the secondary circuit heating form of the nuclear power plant includes: Acquire the actual operation data of the heating device based on the secondary circuit heating form of the nuclear power plant under preset parameters; the actual operation data include: the actual steam consumption of each stage of the high-pressure feedwater heater, the actual heat release of each stage of the high-pressure feedwater heater, the actual temperature of the hot side medium outlet of each stage of the heat exchanger, the actual heat absorption of the heating pipe network in each stage of the heat exchanger, the actual condensation amount 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; Calculate the preset operating data of the heating device based on the secondary circuit heating form of the nuclear power plant under the preset parameters, the preset operating data including: the preset steam consumption of each stage of high-pressure feed water heater, the preset condensation amount of the condenser, the preset temperature of the hot side medium outlet of each stage of the heat exchanger and the preset feed water flow of the condenser; The preset parameters are adjusted so that the actual operation data and the preset operation data meet preset conditions.

3. The control method of the heating device based on the secondary circuit heating form of a nuclear power plant according to claim 2 is characterized in that: Adjusting the preset parameters so that the actual operation data and the preset operation data meet the preset conditions specifically includes: Adjust the parameters of each stage of heat exchanger so that the actual heat release of each stage of high-pressure feedwater heater and the actual heat absorption of the heating pipe network in each stage of heat exchanger meet the first preset condition; Adjust 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 of the hot side medium outlet of each stage of the heat exchanger, the preset steam consumption of each stage of the high-pressure feedwater heater and the actual temperature of the hot side medium outlet of each stage of the heat exchanger meet the second preset condition; The parameters of the condenser are adjusted so that the actual condensed steam volume of the condenser, the actual feed water flow rate of the condenser, the preset condensed steam volume of the condenser and the preset feed water flow rate of the condenser meet the third preset condition.

4. The control method of the heating device based on the secondary circuit heating form of a nuclear power plant according to claim 3 is characterized in that: The first preset condition is: Among them, Q rwi It represents the actual heat absorption of the heating network in the i-th stage heat exchanger; Q sshi Represents the actual heat release of the i-th stage high-pressure feedwater heater.

5. The control method of the heating device based on the secondary circuit heating form of a nuclear power plant according to claim 3 is characterized in that: The second preset condition is: Among them, T j1 represents the preset temperature of the hot side medium outlet of the first stage heat exchanger; g1 represents the preset steam consumption of the first stage high pressure feed water heater; T ssh1out Indicates the actual temperature of the hot side medium outlet of the first stage heat exchanger; g hes1 Indicates the actual steam consumption of the first stage high pressure feedwater heater; T j2 represents the preset temperature of the hot side medium outlet of the second stage heat exchanger; g2 represents the preset steam consumption of the second stage high pressure feed water heater; T ssh2out Indicates the actual temperature of the hot side medium outlet of the second stage heat exchanger; g hes2 Indicates the actual steam consumption of the second-stage high-pressure feedwater heater; T ji Indicates the preset temperature of the hot 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 Indicates the actual temperature of the hot side medium outlet of the i-th stage heat exchanger; g hesi Indicates the actual steam consumption of the i-th stage high-pressure feedwater heater.

6. The control method of the heating device based on the secondary circuit heating form of a nuclear power plant according to claim 3 is characterized in that: The third preset condition is: Among them, G cd1 Indicates the actual condensation volume of the condenser; G cd Indicates the preset condensation volume of the condenser; G fw1 Indicates the actual water flow rate of the condenser; G fw Indicates the preset feed water flow rate of the condenser.

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