High temperature gas cooled nuclear power plant heat supply system and control method thereof

Abstract

This invention provides a heating system and control method for a high-temperature gas-cooled reactor (HTGR) nuclear power plant. The HTGR heating system includes: a HTGR nuclear island, a turbine generator set, a steam generator, a primary superheater, a secondary superheater, a heating mains, a user end, a feedwater preheater, a feedwater inlet, a deaerator, a feedwater heater, a feedwater pump, and a condenser. This invention fully utilizes the main steam from the HTGR nuclear island and the extracted steam from the turbine generator set as the heating steam source for the primary and secondary superheaters of the external heating system, producing externally supplied heating steam. Based on the operating status of the HTGR nuclear island, the heating system is controlled to adopt different operating modes, thereby achieving coordinated operation of power generation and heating. This provides high flexibility, high reliability, and good safety, and helps alleviate the pressure of carbon emissions from industrial heat consumption.

Description

Technical Field

[0001] This invention relates to nuclear power plant heating systems, specifically to a high-temperature gas-cooled reactor nuclear power plant heating system and a control method for the high-temperature gas-cooled reactor nuclear power plant heating system. Background Technology

[0002] Domestic nuclear power plant heating systems are primarily used for residential heating, with limited clean energy supply for industrial heating. Currently, the main method for urban heating is based on pressurized water reactor nuclear power units, utilizing exhaust steam from turbine generator units for preheating and heat exchange. This system operates on a fixed cycle, primarily concentrated during the winter heating season (mostly November to April of the following year). Due to intermittent operation, the steam supply for heating is mainly controlled by operators, and the power generation supply lacks adjustment capabilities during heating system operation, resulting in low flexibility, weak reliability, and potential safety hazards. Summary of the Invention

[0003] To address the aforementioned technical problems, the present invention aims to propose a heating system for a high-temperature gas-cooled reactor nuclear power plant and a control method for the heating system. This system can operate in different modes according to varying power and heat source energy demands, thereby achieving coordinated operation of power generation and heating. It offers high flexibility, high reliability, and good safety, and helps alleviate the pressure on carbon emissions from industrial heat consumption.

[0004] The technical solution adopted in this invention is as follows:

[0005] An embodiment of the present invention provides a heating system for a high-temperature gas-cooled reactor nuclear power plant, comprising: a high-temperature gas-cooled reactor nuclear island; a steam turbine generator set, one end of which is connected to the high-temperature gas-cooled reactor nuclear island; a steam generator, the first input end of which is connected to the other end of the steam turbine generator set; a primary superheater, the first input end of which is connected to the first output end of the steam generator; a secondary superheater, the first input end of which is connected to the first output end of the primary superheater, the first output end of which is connected to a user end via a heating header, the second input end of which is connected to the high-temperature gas-cooled reactor nuclear island, and the second output end of which is connected to the primary superheater. The feedwater preheater has its first input connected to the feedwater inlet and its second input connected to the second output of the first-stage superheater. The deaerator has its input connected to the first output of the feedwater preheater. The feedwater heater has its first input connected to the output of the deaerator via a feedwater pump, and its first output connected to the second input of the steam generator. The condenser is connected to both the feedwater preheater and the feedwater heater.

[0006] In addition, the high-temperature gas-cooled reactor nuclear power plant heating system proposed according to the present invention may also have the following additional technical features:

[0007] According to one embodiment of the present invention, the heating system of the high-temperature gas-cooled reactor nuclear power plant further includes: a liquid level regulating valve, which is disposed in the pipe section from the feedwater heater to the steam generator and is used to regulate the liquid level of the steam generator.

[0008] According to one embodiment of the present invention, the heating system of the high-temperature gas-cooled reactor nuclear power plant further includes: a bypass regulating valve CV. bp The bypass regulating valve CV bp The main steam regulating valve CV is installed in the cold resteam pipe section from the high-temperature gas-cooled reactor core island. g The main steam regulating valve CV g The main steam generated by the high-temperature gas-cooled reactor nuclear island is located from one end of the steam turbine generator set to the main steam regulating valve CV. A portion of the main steam generated by the high-temperature gas-cooled reactor nuclear island can pass through the main steam regulating valve CV. g The steam turbine generator set generates electricity externally, and a portion of this electricity can be supplied through the bypass regulating valve CV. bp Entering the cold resteam section.

[0009] According to one embodiment of the present invention, the heating system of the high-temperature gas-cooled reactor nuclear power plant further includes: a heating steam regulating valve CV.S1 The heating steam regulating valve CV S1 The second inlet pipe section from the high-temperature gas-cooled reactor core island to the secondary superheater; steam generator regulating valve CV S2 The steam generator regulating valve CV S2 A pipe section located from the other end of the steam turbine generator set to the first input end of the steam generator; a first-stage superheater heating steam regulating valve CV i The primary superheater heating steam regulating valve CV i The pipe section is provided from the second output end of the secondary superheater to the second input end of the primary superheater.

[0010] An embodiment of the present invention proposes a control method for a heating system of a high-temperature gas-cooled reactor nuclear power plant, comprising the following steps: determining the total power demand of the high-temperature gas-cooled reactor nuclear island based on the output power demand range and heating power demand range of the turbine generator set; determining whether the total power demand of the high-temperature gas-cooled reactor nuclear island meets the requirements for coordinated operation of power generation and heat supply of the heating system of the high-temperature gas-cooled reactor nuclear power plant; if it meets the requirements, controlling the heating system of the high-temperature gas-cooled reactor nuclear power plant to operate in a coordinated power generation and heating operation mode; if it does not meet the requirements, controlling the heating system of the high-temperature gas-cooled reactor nuclear power plant to operate in a single-output operation mode according to the user instructions of the operator, wherein the user instructions are generated based on the actual operating conditions and the power plant's operation decisions.

[0011] In addition, the control method for the heating system of a high-temperature gas-cooled reactor nuclear power plant proposed above according to the present invention may also have the following additional technical features:

[0012] According to one embodiment of the present invention, the power generation and heating coordinated operation mode of the control method for the heating system of the high-temperature gas-cooled reactor nuclear power plant includes: a turbine generator set main mode and a heating power main mode. In the turbine generator set main mode, the turbine generator set adjusts its power generation in response to changes in power generation demand, and the heating power adjustment enters a follow-up mode. In the heating power main mode, heating power adjustment is the primary function, but the system enters a combined control mode of heating steam pressure and temperature, and the turbine generator set power generation adjustment enters a follow-up mode.

[0013] According to an embodiment of the present invention, when the main mode of the steam turbine generator set is a fixed external heating temperature mode, the control method specifically includes the following steps: controlling the main steam regulating valve CV g In response to the power demand of the power grid, the heating steam regulating valve CV S1 Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This is the actual value at the nuclear island outlet; the CV of the primary superheater heating steam regulating valve. i Adjusting the temperature T at the end of the heating main pipeT ; Calculate the steam flow rate requirement at the steam generator outlet, based on the steam flow rate requirement at the steam generator outlet and the CV of the primary superheater heating steam regulating valve. i The target value of the saturated steam flow rate at the steam generator outlet is obtained by determining the opening degree k; based on the target value of the saturated steam flow rate at the steam generator outlet and the saturated steam flow rate Q at the first output end of the steam generator... w For the steam generator regulating valve CV s2 To take control.

[0014] According to one embodiment of the present invention, the required steam flow rate at the outlet of the steam generator is specifically calculated according to the following formula:

[0015]

[0016] Among them, Q wsp Q represents the required steam flow rate at the steam generator outlet. s P is the steam flow rate for heating the secondary superheater. S CV for heating steam regulating valve S1 Export pressure, T S CV for heating steam regulating valve S1 outlet temperature, P S1 CV heating steam regulating valve for the first-stage superheater i Inlet pressure, T S1 CV heating steam regulating valve for the first-stage superheater i Inlet temperature, K W is the adjustment coefficient, and h is the enthalpy value.

[0017] According to an embodiment of the present invention, when the main mode of the steam turbine generator set is a fixed external heating temperature mode, the control method specifically includes the following steps: controlling the main steam regulating valve CV g In response to the power demand of the power grid, the heating steam regulating valve CV S1 Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This represents the actual value at the nuclear island outlet; the steam generator regulating valve CV. S2 Opening degree response to heating main pipe terminal pressure P T The corresponding PID controller calculates and outputs instructions when the temperature T at the end of the heating main pipe... T When the temperature is below the lower limit of the reasonable temperature range, the CV of the steam generator regulating valve is limited. S2 The opening degree is the terminal pressure P of the heating main pipe. T The corresponding PID controller calculates and outputs the command multiplied by the first coefficient K1; the primary superheater heating steam regulating valve CV... i Opening degree response to heating main pipe terminal temperature T TThe corresponding PID controller calculates and outputs instructions when the temperature T at the end of the heating main pipe... T When the temperature is below the upper limit of the reasonable temperature range, control the CV regulating valve of the first-stage superheater heating steam. i Fully open.

[0018] According to one embodiment of the present invention, when the heating system of the high-temperature gas-cooled reactor nuclear power plant is operating in the main heating power mode, the control method includes: adjusting the heating steam regulating valve CV. S1 The main steam regulating valve CV is set to control the temperature of the externally supplied heating steam. g Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This is the actual value at the nuclear island outlet; adjusted by regulating the steam generator regulating valve CV. S2 Adjust the pressure PT at the end of the heating main pipe to the set pressure value; adjust the steam regulating valve CV of the first-stage superheater. i The control command is multiplied by the second coefficient K2 and then added to the heating steam regulating valve CV. S1 The control loop is designed to coordinate the effects of the two-stage superheater.

[0019] The beneficial effects of this invention are:

[0020] The high-temperature gas-cooled reactor nuclear power plant heating system and its control method according to embodiments of the present invention fully utilize the main steam of the high-temperature gas-cooled reactor nuclear island and the steam extracted from the turbine generator set as the heating gas source for the first-stage and second-stage superheaters of the external heating system to produce external heating steam. It fully utilizes nuclear energy as the initial energy source, which is an effective use of clean energy. It can alleviate the pressure of carbon emissions from industrial heating and promote carbon emission reduction in the industrial heating sector. According to the operating status of the high-temperature gas-cooled reactor nuclear island, the high-temperature gas-cooled reactor nuclear power plant heating system can be controlled to adopt different operating modes, thereby achieving coordinated operation of power generation and heating. It has high flexibility, high reliability, and good safety, which is conducive to alleviating the pressure of carbon emissions from industrial heating. Attached Figure Description

[0021] Figure 1 This is a schematic diagram of the heating system of a high-temperature gas-cooled reactor nuclear power plant according to the first embodiment of the present invention;

[0022] Figure 2 This is a schematic diagram of the heating system of a high-temperature gas-cooled reactor nuclear power plant according to the second embodiment of the present invention;

[0023] Figure 3 A flowchart of a control method for a heating system in a high-temperature gas-cooled reactor nuclear power plant according to an embodiment of the present invention:

[0024] Figure 4 A flowchart illustrating the coordinated control mode of the heating system of a high-temperature gas-cooled reactor nuclear power plant according to a specific embodiment of the present invention;

[0025] Figure 5 A flowchart illustrating the fixed external heating temperature mode of a high-temperature gas-cooled reactor nuclear power plant heating system according to an embodiment of the present invention;

[0026] Figures 6a-6c This is a schematic diagram illustrating the principle of a fixed external heating temperature mode for a high-temperature gas-cooled reactor nuclear power plant heating system according to an embodiment of the present invention.

[0027] Figure 7 A flowchart illustrating the fixed external heating pressure mode of a high-temperature gas-cooled reactor nuclear power plant heating system according to an embodiment of the present invention;

[0028] Figures 8a-8d This is a schematic diagram illustrating the principle of a fixed external heating pressure mode for a high-temperature gas-cooled reactor nuclear power plant heating system according to an embodiment of the present invention.

[0029] Figure 9 A flowchart of the main mode of heating power supply of a high-temperature gas-cooled reactor nuclear power plant heating system according to an embodiment of the present invention;

[0030] Figures 10a-10c This is a schematic diagram illustrating the principle of the main mode of heating power supply in a high-temperature gas-cooled reactor nuclear power plant heating system according to an embodiment of the present invention. Detailed Implementation

[0031] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0032] like Figure 1As shown, the heating system of a high-temperature gas-cooled reactor nuclear power plant according to the first embodiment of the present invention includes: a high-temperature gas-cooled reactor nuclear island 100, a steam turbine generator set 200, a steam generator 300, a primary superheater 400, a secondary superheater 500, a heating main pipe 600, a user end 700, a feedwater preheater 800, a feedwater inlet end 900, a deaerator 1000, a feedwater heater 1100, a feedwater pump 1200, and a condenser 1300. Among them, one end of the steam turbine generator set 200 is connected to the high-temperature gas-cooled reactor core island 100; the first input end of the steam generator 300 is connected to the other end of the steam turbine generator set 200; the first input end of the primary superheater 400 is connected to the first output end of the steam generator 300; the first input end of the secondary superheater 500 is connected to the first output end of the primary superheater 400, the first output end of the secondary superheater 500 is connected to the user end 700 through the heating header 600, the second input end of the secondary superheater 500 is connected to the high-temperature gas-cooled reactor core island 100, and the second output end of the secondary superheater 500 is connected to the second input end of the primary superheater 400; feedwater preheating... The input terminal of the preheater 800 is connected to the feedwater inlet 900, and the second input terminal of the feedwater preheater 800 is connected to the second output terminal of the first-stage superheater 400; the input terminal of the deaerator 1000 is connected to the first output terminal of the feedwater preheater 800; the first input terminal of the feedwater heater 1100 is connected to the output terminal of the deaerator 1000 through the feedwater pump 1200, the first output terminal of the feedwater heater 1100 is connected to the second input terminal of the steam generator 300, and the second input terminal of the feedwater heater 1100 is connected to the second output terminal of the steam generator 300; the condenser 1300 is connected to the feedwater preheater 800 and the feedwater heater 1100 respectively.

[0033] Specifically, a portion of the main steam generated in the high-temperature gas-cooled reactor nuclear island 100 enters the turbine generator set 200 for power generation, and another portion enters the secondary superheater 500 to heat the steam exiting the primary superheater 400, thereby generating steam for external heating. The turbine generator set 200 extracts steam to the steam generator 300, providing a heat source for the saturated steam generated by the steam generator 300. The saturated steam generated by the steam generator then passes sequentially through the primary and secondary superheaters to further absorb heat and generate steam for external heating. Feedwater is output from feedwater inlet 900, heated by feedwater preheater 800, and then deaerated by deaerator 1000. After deaeration, the feedwater is pumped by water pump 1200 to feedwater heater 1100 for further heating, and then enters steam generator 300 to produce saturated steam. The saturated steam continues to absorb heat by passing sequentially through primary superheater 400 and secondary superheater 500 to match the temperature control requirements of the external heating steam. Finally, it enters the user terminal 700 through heating header 600 to provide heating to users. Condenser 1300 collects condensate from feedwater preheater 800, feedwater heater 1100, primary superheater 400, and steam generator 300. Steam generator 300 also exchanges heat with the medium in feedwater heater 1100, and primary superheater 400 also exchanges heat with the medium in feedwater preheater 800 to maximize energy utilization efficiency.

[0034] Therefore, by making full use of the high-temperature gas-cooled reactor nuclear power plant with the characteristics of the fourth-generation nuclear power system to construct the nuclear power plant heating system, the high-quality parameters of the high-temperature gas-cooled reactor nuclear island main steam and turbine extraction steam can be used as the heating steam source for the heaters at all levels of the external heating system to produce heating steam for external heating. This can solve the problem of heat source supply and control in the heat source network and help alleviate the pressure of carbon emissions from industrial heat use.

[0035] In one embodiment of the present invention, such as Figure 2 As shown, the heating system of a high-temperature gas-cooled reactor nuclear power plant may also include a liquid level regulating valve (LCV), which is installed in the pipe section from the feedwater heater 1100 to the steam generator 300 to regulate the liquid level in the steam generator 300.

[0036] In one embodiment of the present invention, such as Figure 2 As shown, the heating system of a high-temperature gas-cooled reactor nuclear power plant may also include a bypass regulating valve CV. bp and main steam regulating valve CV g Among them, the bypass regulating valve CV bp The main steam regulating valve CV is located in the 100-degree reheat steam pipe section of the high-temperature gas-cooled reactor nuclear island. g It is located at one end of the steam turbine generator set 200, extending to the reactor tube section of the high-temperature gas-cooled nuclear island. A portion of the main steam generated by the high-temperature gas-cooled reactor nuclear island 100 passes through the main steam regulating valve CV. gThe steam turbine generator set 200 generates electricity externally, with a portion passing through the bypass regulating valve CV. bp Entering the cold resteam section, which is the steam coordination branch of the steam turbine generator set during startup, shutdown, and tripping.

[0037] In one embodiment of the present invention, such as Figure 2 As shown, the heating system of a high-temperature gas-cooled reactor nuclear power plant may also include a heating steam regulating valve CV. S1 Steam generator regulating valve CV S2 and the first-stage superheater heating steam regulating valve CV i Among them, the heating steam regulating valve CV S1 The second input pipe section, located between the high-temperature gas-cooled reactor core island 100 and the secondary superheater 500, is used to transport the main steam output from the high-temperature gas-cooled reactor core island 100 for heating the steam output from the steam generator 300. The steam generator regulating valve CV... S2 A pipe section located at the other end of the steam turbine generator set 200 to the first input end of the steam generator 300 is used to supply heating steam to the steam generator 300 to produce saturated steam. The first-stage superheater heating steam regulating valve CV... i A pipe section installed between the second output end of the secondary superheater 500 and the second input end of the primary superheater 400 is used to transport heating steam into the primary superheater 400, thereby regulating the terminal temperature T of the heating header. T .

[0038] like Figure 2 As shown, in a specific embodiment of the present invention, a triple redundant pressure detection element P can be installed on the main steam output pipe of the high-temperature gas-cooled reactor nuclear island 100. S0 and triple redundant temperature sensing element T S0 A liquid level detection element L1 and a heating steam regulating valve CV can be installed on the steam generator 300. S1 Pressure sensing element P can be installed on the main steam outlet pipeline. S Flow detection element Q S and temperature sensing element T S A flow detection device Q can be installed at the steam outlet of the steam generator 300 (i.e., the first output end of the evaporator). W This is used to detect the steam flow rate at the outlet of the steam generator 300. A pressure sensing element P can be installed at the heating steam inlet of the first-stage superheater 400 (i.e., the second input terminal of the first-stage superheater 400). S1 and temperature sensing element T S1 A pressure sensing element P can be installed at the heated steam outlet of the first-stage superheater 400 (i.e., the first output end of the first-stage superheater 400). i and temperature sensing element T iA pressure sensing element P can be installed at the heated steam outlet of the secondary superheater 500 (i.e., the first output end of the secondary superheater 500). T Flow detection element F T and temperature sensing element T T The user terminal 700 can have multiple user branches, including user 1, user 2, user 3 to user n. User branch 1 can be equipped with a branch 1 steam regulating valve CV1 and a branch 1 steam flow measuring device F1, which are used to regulate the heating steam flow of user branch 1 and measure the heating steam flow of user branch 1, respectively. User branch 2 can be further equipped with a branch 2 steam regulating valve CV2 and a branch 2 steam flow measuring device F2, which are used to regulate the heating steam flow of user branch 2 and measure the heating steam flow of user branch 2, respectively. Similarly, other branches can be configured in this way.

[0039] The following is combined Figure 2 The illustrated embodiment demonstrates the working principle of the heating system in a high-temperature gas-cooled reactor nuclear power plant.

[0040] Feedwater is heated by the feedwater preheater 800 and then deaerated by the deaerator 1000. It is then pumped by the feedwater pump 1200 to the feedwater heater 1100, where it is heated and fed into the steam generator 300 to produce steam. Steam is extracted from the turbine generator set 200 and output through the heating steam regulating valve CV. S2 Steam enters the steam generator 300 from its first input terminal, heating the steam to produce saturated steam. The saturated steam produced by the steam generator 300 is output from its first output terminal and passes sequentially through the first-stage superheater 400 and the second-stage superheater 500 to continue absorbing heat and producing steam for external heating. The liquid level L1 in the steam generator can be adjusted by the liquid level regulating valve LCV.

[0041] A portion of the main steam generated in the high-temperature gas-cooled reactor nuclear island 100 is bypassed by the regulating valve CV. bp Entering the cold resteam section, a portion passes through the main steam regulating valve CV. g The steam turbine generator set 200 generates electricity externally, and part of it is fed into the heating steam regulating valve CV. S1 Steam enters the secondary superheater 500 from the second input terminal and heats the steam exiting the first output terminal of the primary superheater 400 as external heating steam.

[0042] The high-temperature gas-cooled reactor nuclear power plant heating system according to an embodiment of the present invention fully utilizes the main steam of the high-temperature gas-cooled reactor nuclear island and the steam extracted from the turbine generator set as the heating gas source for the first-stage and second-stage superheaters of the external heating system to produce external heating steam. It fully utilizes nuclear energy as the initial energy source, which is an effective use of clean energy. It can solve the pressure of carbon emissions from industrial heating and promote the advancement of carbon emission reduction in the field of industrial heating.

[0043] Considering the needs of power generation and heating operations, the operating mode of the heating system of the high-temperature gas-cooled reactor nuclear power plant is determined by weighing factors such as the power plant's economic decisions and external contracts. For example, based on the output power demand range of the turbine generator set 200 and the heating power demand range, the total power demand of the high-temperature gas-cooled reactor nuclear island 100 is determined, basically fixing the reactor power output to reduce fluctuations in the reactor nuclear island and ensure the overall stability and reliability of the high-temperature gas-cooled reactor nuclear power unit. The following describes how to implement the control of the high-temperature gas-cooled reactor nuclear power plant heating system proposed in the above embodiments of the present invention with specific examples.

[0044] Figure 3 This is a flowchart of a control method for a heating system of a high-temperature gas-cooled reactor nuclear power plant according to an embodiment of the present invention. Figure 3 As shown, the control method includes the following steps:

[0045] S1. Determine the total power requirement of the high-temperature gas-cooled reactor nuclear island based on the output power requirement range and heating power requirement range of the steam turbine generator set.

[0046] Specifically, by determining the total power requirements of the high-temperature gas-cooled reactor nuclear island and adjusting the power output of the basically fixed reactor to reduce fluctuations in the reactor nuclear island, the overall stability and reliability of the heating system of the high-temperature gas-cooled reactor nuclear power plant can be ensured.

[0047] S2, determine whether the total power demand of the high-temperature gas-cooled reactor nuclear island meets the requirements for coordinated operation of the power generation and heat supply of the heating system of the high-temperature gas-cooled reactor nuclear power plant.

[0048] If S3 is satisfied, the heating system of the high-temperature gas-cooled reactor nuclear power plant will be controlled to operate in a coordinated power generation and heating operation mode.

[0049] S4, if not satisfied, controls the heating system of the high-temperature gas-cooled reactor nuclear power plant to operate in single-output mode according to the user instructions of the operators. The user instructions are generated based on the actual operating conditions and the power plant's operating decisions.

[0050] Specifically, such as Figure 4 As shown, the control method for the heating system of the high-temperature gas-cooled reactor nuclear power plant may include the following process: Based on the operating status of the high-temperature gas-cooled reactor nuclear island, determine whether its total nuclear island power meets the requirements for coordinated operation of power generation and heat supply. If it does, select the coordinated operation mode of power generation and heat supply. Otherwise, the operators select the single-output operation mode (power generation or heat supply) based on the actual operating conditions and the power plant's operating decisions.

[0051] Furthermore, in one embodiment of the present invention, as Figure 4As shown, when the power generation and heating coordinated operation mode is selected, the operation mode of the heating system of the high-temperature gas-cooled reactor nuclear power plant can be divided into two types: turbine generator set main mode and heating power main mode. In turbine generator set main mode, the turbine generator set adjusts its power generation in response to changes in power generation demand. At this time, heating power adjustment enters a follow-up mode. In the heating power follow-up adjustment mode, the heating steam temperature control mode or the heating steam pressure control mode is selected according to the external heating contract conditions. In the heating power main mode, heating power adjustment is the primary method, and the system enters a combined control mode of external heating pressure and temperature. At this time, the turbine generator set power generation adjustment enters a follow-up mode.

[0052] In one embodiment of the present invention, the main mode of the steam turbine generator set may include a fixed external heating temperature mode, such as... Figure 5 As shown, when the heating system of a high-temperature gas-cooled reactor nuclear power plant operates in a fixed external heating temperature mode, the above control method may specifically include the following steps:

[0053] S3111, controls the main steam regulating valve CV g CV heating steam regulating valve responds to grid power demand S1 Entering a follow-up state to maintain the main steam pressure P output by the high-temperature gas-cooled reactor nuclear island 100 reactor. S0 This represents the actual export value of the nuclear island.

[0054] Specifically, such as Figure 6a As shown, based on the power generation demand and the steam generator regulating valve CV S2 The calculation result of the control command f1(x) is combined with the power generation feedback, and the PID (Proportional-Integral-Derivative) controller controls the main steam regulating valve CV. g The opening degree responds to the power demand of the power grid, regulating the main steam entering the turbine generator unit; such as Figure 6b As shown, the PID controller controls the heating steam regulating valve CV based on the main steam pressure setpoint. S1 Entering a follow-up state to maintain the main steam pressure P output by the high-temperature gas-cooled reactor nuclear island 100 reactor. S0 This represents the actual export value of the nuclear island.

[0055] S3112, Primary superheater heating steam regulating valve CV i Adjusting the temperature T at the end of the heating main pipe T .

[0056] Specifically, such as Figure 6c As shown, the PID controller is based on the temperature T at the end of the heating main pipe. T The primary superheater heating steam regulating valve CV controls the target value of the heating steam temperature. iThe opening degree is adjusted to maintain the terminal temperature T of the heating header. T This is the actual heating temperature.

[0057] S3113, Calculate the steam flow demand at the steam generator outlet, based on the steam flow demand at the steam generator outlet and the CV of the primary superheater heating steam regulating valve. i The opening degree k is used to obtain the target value of the saturated steam flow rate at the outlet of the steam generator.

[0058] Specifically, the required steam flow rate at the steam generator outlet can be calculated using the following formula:

[0059]

[0060] Among them, Q Wsp =f(x) represents the steam flow rate requirement at the steam generator outlet, Q S For the secondary superheater, the heating steam flow rate is 500, P S CV for heating steam regulating valve S1 Export pressure, T S CV for heating steam regulating valve S1 outlet temperature, P S1 CV heating steam regulating valve for the first-stage superheater i Inlet pressure, T S1 CV heating steam regulating valve for the first-stage superheater i Inlet temperature, K W The adjustment coefficient can be 1.05 to 1.1, h is the enthalpy value, and h(P,T) is the enthalpy value of the corresponding pressure P and temperature T.

[0061] S3114, based on the target value of the saturated steam flow rate at the steam generator outlet and the saturated steam flow rate Q at the first output end of the steam generator. w For steam generator regulating valve CV S2 To take control.

[0062] It should be understood that, under a fixed external heating temperature mode, in order to ensure that the terminal temperature of the heating header reaches the required level, the steam flow rate at the steam generator outlet is coordinated and controlled. The required steam flow rate at the steam generator outlet is calculated based on the energy transfer formula, taking into account the CV of the primary superheater heating steam regulating valve. i The command's effect is to feed forward and accumulate to the steam generator regulating valve CV. S2 This ensures that the production of saturated steam responds to the supply of main steam for heating, while simultaneously matching the temperature control requirements of external heating steam. This couples the main steam for heating steam input with the external heating output, organically integrating the entire system. Meanwhile, the steam generator regulating valve CV... S2 The action will consume the turbine main steam regulating valve CV gThe introduced main steam energy, therefore in the main steam regulating valve CV g The regulating loop is introduced into the steam generator regulating valve CV. S2 The control command matches the function f1(x) and accumulates to increase the introduction of main steam energy into the turbine generator set 200.

[0063] In one embodiment of the present invention, the main mode of the steam turbine generator set also includes a fixed external heating pressure mode, such as... Figure 7 As shown, when the heating system of a high-temperature gas-cooled reactor nuclear power plant operates in a fixed external heating pressure mode, the control method specifically includes the following steps:

[0064] S3121, controls the main steam regulating valve CV g CV heating steam regulating valve responds to grid power demand S1 Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This represents the actual export value of the nuclear island.

[0065] Specifically, such as Figure 8a As shown, based on the power generation demand and the steam generator regulating valve CV S2 The calculation result of the function f1(x) matched by the control command, combined with the power generation feedback, enables the PID controller to control the main steam regulating valve CV. g The opening degree responds to the power demand of the power grid, regulating the main steam entering the turbine generator unit; such as Figure 8b As shown, the PID controller controls the heating steam regulating valve CV based on the main steam pressure setpoint. S1 Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This represents the actual export value of the nuclear island.

[0066] S3122, Steam generator regulating valve CV S2 Opening degree response to heating main pipe terminal pressure P T The corresponding PID controller calculates and outputs instructions when the temperature T at the end of the heating main pipe... T When the temperature is below the lower limit of the reasonable temperature range, the CV of the steam generator regulating valve is limited. S2 The opening degree is the terminal pressure P of the heating main pipe. T The corresponding PID controller calculates the output command multiplied by the first coefficient K1.

[0067] Specifically, such as Figure 8c As shown, the steam generator regulating valve CV S2 Response to heating main pipe terminal pressure P T The corresponding PID controller calculates and outputs instructions to adjust the steam extraction from the turbine generator set, thereby increasing the terminal pressure P of the heating header. T Maintain the heating steam pressure at the target value, when the heating header terminal temperature TT When the temperature is below the lower limit of the reasonable temperature range, the CV of the steam generator regulating valve is limited. S2 The opening degree is calculated by multiplying the output command of the PID controller by the first coefficient K1, and an alarm is issued to the operator for handling as appropriate; otherwise, the steam generator regulating valve CV... S2 The opening degree is the output command calculated by the PID controller.

[0068] S3123, Primary superheater heating steam regulating valve CV i Opening degree response to heating main pipe terminal temperature T T The corresponding PID controller calculates and outputs instructions when the temperature T at the end of the heating main pipe... T When the temperature is below the upper limit of the reasonable temperature range, control the CV regulating valve of the first-stage superheater heating steam. i Fully open.

[0069] Specifically, such as Figure 8d As shown, the primary superheater heating steam regulating valve CV i Opening degree response to heating main pipe terminal temperature T T The corresponding PID controller's output command is used to adjust the terminal temperature T of the heating main pipe. T Maintain the heating steam temperature at the target value, when the heating header terminal temperature T T When the temperature is below the upper limit of the reasonable range, the steam regulating valve CV of the first-stage superheater is fully opened. i This allows all the heating steam to enter the primary heater for heating the external heating steam, thus raising the terminal temperature T of the heating header. T The target value has been achieved.

[0070] like Figures 8a-8d As shown, in the fixed external heating pressure mode, the control method of the heating system of the high-temperature gas-cooled reactor nuclear power plant ensures the quality of heating steam by setting stable limit control boundary functions in the pressure regulation and temperature regulation of the heating header terminal.

[0071] like Figure 9 As shown, in one embodiment of the present invention, when the heating system of a high-temperature gas-cooled reactor nuclear power plant is operating in the main heating power mode, a combined control mode for external heating pressure and temperature will be implemented. The control method includes:

[0072] S3211, Adjusting the heating steam regulating valve CV S1 The main steam regulating valve CV is set to control the temperature of the externally supplied heating steam. g Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This represents the actual export value of the nuclear island.

[0073] Specifically, such as Figure 10a As shown, the PID controller is based on the main steam pressure PS0 And consider the steam generator regulating valve CV S2 The calculation result of the control command f1(x), and the feedforward accumulator heating steam regulating valve CV g This puts it into a follow-up state, combining it with the main steam pressure setpoint to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This represents the actual export value of the nuclear island.

[0074] S3212, by adjusting the steam generator regulating valve CV S2 Adjust the pressure P at the end of the heating main pipe T To set the pressure value.

[0075] Specifically, such as Figure 10b As shown, the PID controller controls the steam generator regulating valve CV based on the target value of the heating steam pressure. S2 To regulate the terminal pressure P of the heating main pipe T To set the pressure value.

[0076] S3213, the primary superheater heating steam regulating valve CV i The control command is multiplied by the second coefficient K2 and then added to the heating steam regulating valve CV. S1 The control loop is designed to coordinate the response of the two-stage superheater.

[0077] Specifically, such as Figure 10c As shown, the primary superheater heating steam regulating valve CV i Used to regulate the steam temperature T at the outlet of the first-stage superheater i To coordinate the heating effects of the primary and secondary superheaters on the externally supplied steam, a PID controller is used to regulate the terminal temperature T of the heating header. T To set the pressure value, the primary superheater heating steam regulating valve CV is simultaneously activated. i The control command is multiplied by a coefficient K2 and accumulated to the heating steam regulating valve CV. S1 The control loop is designed to coordinate the response of the two-stage superheater.

[0078] In summary, the control method for the heating system of a high-temperature gas-cooled reactor nuclear power plant according to embodiments of the present invention fully explores the centralized heating mode of the heat source network, making the energy generation station a flexible node in the heat source network. Based on this, it proposes a coordinated operation mode for power generation and heating of the high-temperature gas-cooled reactor nuclear power plant heating system, and rationally selects the appropriate coordinated operation mode based on grid demand, heat network demand, contract terms, and economic operation strategies to obtain the optimal output mode. The present invention provides control methods for the steam turbine generator set as the main mode for heating steam pressure and temperature control, as well as the main mode for heating power for the proposed high-temperature gas-cooled reactor nuclear power plant heating system. In each control mode, the coupling relationship of each parameter is fully considered, a coordinated control relationship is established, and parameter control boundaries are set to ensure the stability and reliability of system control. This enables coordinated operation of power generation and heating, with high flexibility, high reliability, and good safety, which helps alleviate the pressure of carbon emissions from industrial heat consumption.

[0079] In the description of this invention, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. "A plurality of" means two or more, unless otherwise explicitly specified.

[0080] In the description of this specification, the references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Furthermore, those skilled in the art can combine and integrate the different embodiments or examples and features of different embodiments or examples described in this specification without contradiction. Furthermore, those skilled in the art can combine and integrate the different embodiments or examples described herein, as well as the features of the different embodiments or examples, without contradiction.

[0081] It should be understood that various parts of the present invention can be implemented in hardware, software, firmware, or a combination thereof. In the above embodiments, multiple steps or methods can be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. For example, if implemented in hardware as in another embodiment, it can be implemented using any of the following techniques known in the art, or a combination thereof: discrete logic circuits having logic gates for implementing logical functions on data signals, application-specific integrated circuits (ASICs) having suitable combinational logic gates, programmable gate arrays (PGAs), field-programmable gate arrays (FPGAs), etc.

[0082] Those skilled in the art will understand that all or part of the steps of the methods in the above embodiments can be implemented by a program instructing related hardware. The program can be stored in a computer-readable storage medium, and when executed, the program includes one or a combination of the steps of the method embodiments.

[0083] Furthermore, the functional units in the various embodiments of the present invention can be integrated into a processing module, or each unit can exist physically separately, or two or more units can be integrated into a module. The integrated module can be implemented in hardware or as a software functional module. If the integrated module is implemented as a software functional module and sold or used as an independent product, it can also be stored in a computer-readable storage medium.

[0084] The storage medium mentioned above can be a read-only memory, a disk, or an optical disk, etc. Although embodiments of the present invention have been shown and described above, it is to be understood that the above embodiments are exemplary and should not be construed as limiting the present invention. Those skilled in the art can make changes, modifications, substitutions, and variations to the above embodiments within the scope of the present invention.

[0085] Although embodiments of the invention have been shown and described, it will be understood by those skilled in the art that various changes, modifications, substitutions and alterations can be made to these embodiments without departing from the principles and spirit of the invention, the scope of which is defined by the appended claims and their equivalents.

Claims

1. A control method for a heating system of a high-temperature gas-cooled reactor nuclear power plant, characterized in that, The heating system of a high-temperature gas-cooled reactor nuclear power plant includes: High-temperature gas-cooled reactor nuclear island; A steam turbine generator set, one end of which is connected to the high-temperature gas-cooled reactor core island; A steam generator, wherein the first input end of the steam generator is connected to the other end of the steam turbine generator set; A primary superheater, wherein the first input terminal of the primary superheater is connected to the first output terminal of the steam generator; A secondary superheater, wherein the first input terminal of the secondary superheater is connected to the first output terminal of the primary superheater, the first output terminal of the secondary superheater is connected to the user terminal through a heating header, the second input terminal of the secondary superheater is connected to the high-temperature gas-cooled reactor core island, and the second output terminal of the secondary superheater is connected to the second input terminal of the primary superheater. A feedwater preheater, wherein the first input terminal of the feedwater preheater is connected to the feedwater inlet terminal, and the second input terminal of the feedwater preheater is connected to the second output terminal of the first-stage superheater; A deaerator, the input end of which is connected to the first output end of the feedwater preheater; The feedwater heater has a first input terminal connected to the output terminal of the deaerator via a feedwater pump, and a first output terminal connected to the second input terminal of the steam generator. The second input terminal of the feedwater heater is also connected to the second output terminal of the steam generator. A condenser, which is connected to the feedwater preheater and the feedwater heater respectively; A level regulating valve is installed in the pipe section from the feedwater heater to the steam generator; Bypass regulating valve CV bp The bypass regulating valve CV bp Located in the cold resteam pipe section from the nuclear island of the high-temperature gas-cooled reactor; Main steam regulating valve CV g The main steam regulating valve CV g The section of the turbine generator set is located from one end of the high-temperature gas-cooled reactor nuclear island tube. Heating steam regulating valve CV S1 The heating steam regulating valve CV S1 The second input pipe section is installed from the nuclear island of the high-temperature gas-cooled reactor to the secondary superheater; Steam generator regulating valve CV S2 The steam generator regulating valve CV S2 A pipe section is provided from the other end of the steam turbine generator set to the first input end of the steam generator; First-stage superheater heating steam regulating valve CV i The primary superheater heating steam regulating valve CV i The pipe section from the second output end of the secondary superheater to the second input end of the primary superheater; The control method includes the following steps: The total power requirement of the high-temperature gas-cooled reactor nuclear island is determined based on the output power requirement range and heating power requirement range of the steam turbine generator set. Determine whether the total power demand of the high-temperature gas-cooled reactor nuclear island meets the requirements for coordinated operation of the power generation and heat supply of the heating system of the high-temperature gas-cooled reactor nuclear power plant. If the conditions are met, the heating system of the high-temperature gas-cooled reactor nuclear power plant will be controlled to operate in a coordinated power generation and heating operation mode. If not, the high-temperature gas-cooled reactor nuclear power plant heating system is controlled to operate in single-output mode according to the user instructions of the operators. The user instructions are generated based on the actual operating conditions and the power plant's operating decisions. The coordinated operation modes for power generation and heating include: the main mode for steam turbine generator sets and the main mode for heating power, wherein, The main mode of the steam turbine generator set is to adjust the power generation of the steam turbine generator set in response to changes in power generation demand, and the heating power adjustment enters the follow mode; the main mode of heating power adjustment is based on heating power adjustment, and enters the combined control mode of heating steam pressure and temperature, and the power generation adjustment of the steam turbine generator set enters the follow mode.

2. The control method for the heating system of a high-temperature gas-cooled reactor nuclear power plant according to claim 1, characterized in that, When the main mode of the steam turbine generator set is a fixed external heating pressure mode, the control method specifically includes the following steps: Control the main steam regulating valve CV g In response to the power demand of the power grid, the heating steam regulating valve CV S1 Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This represents the actual value of nuclear island exports. Steam generator regulating valve CV S2 Opening degree response to heating main pipe terminal pressure P T The corresponding PID controller calculates and outputs instructions when the temperature T at the end of the heating main pipe... T When the temperature is below the lower limit of the reasonable temperature range, the CV of the steam generator regulating valve is limited. S2 The opening degree is the terminal pressure P of the heating main pipe. T The corresponding PID controller calculates and outputs the command multiplied by the first coefficient K1; First-stage superheater heating steam regulating valve CV i Opening degree response to heating main pipe terminal temperature T T The corresponding PID controller calculates and outputs instructions when the temperature T at the end of the heating main pipe... T When the temperature is below the lower limit of the reasonable temperature range, control the CV of the primary superheater heating steam regulating valve. i Fully open.

3. The control method for the heating system of a high-temperature gas-cooled reactor nuclear power plant according to claim 1, characterized in that, When the heating system of the high-temperature gas-cooled reactor nuclear power plant is operating in the main heating power mode, the control method includes: Adjust the heating steam regulating valve CV S1 The main steam regulating valve CV is set to control the temperature of the externally supplied heating steam. g Entering a servo mode to maintain the main steam pressure P output from the high-temperature gas-cooled reactor nuclear island. S0 This represents the actual value of nuclear island exports. By adjusting the regulating valve CV of the steam generator S2 Adjust the pressure P at the end of the heating main pipe T To set the pressure value; The primary superheater heating steam regulating valve CV i The control command is multiplied by the second coefficient K2 and then added to the heating steam regulating valve CV. S1 The control loop is designed to coordinate the effects of the two-stage superheater.

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