Method, system and device for coordinated control of thermal parameters of primary circuit and secondary circuit of pressurized water reactor nuclear power plant, and readable storage medium

Abstract

The present application relates to a method, system and device for coordinated control of thermal parameters of primary loop and secondary loop of pressurized water reactor nuclear power plant, and a readable storage medium. The method comprises: S1, obtaining the main steam pressure, determining the first dead zone range according to the first predetermined value and the second predetermined value; generating the first trigger signal and selecting the first deviation signal when the main steam pressure exceeds the first dead zone range, and adjusting the opening of the main loop regulating valve to make the main steam pressure return to the first dead zone range. S2, obtaining the coolant flow, determining the second dead zone range according to the third predetermined value and the fourth predetermined value; generating the second trigger signal and selecting the second deviation signal when the coolant flow exceeds the second dead zone range, and adjusting the opening of the bypass regulating valve to make the coolant flow return to the second dead zone range. The present application can maintain the stability of the reactor thermal parameters, reduce thermal fatigue and mechanical stress, and improve the service life and structural safety of the equipment.

Description

Technical Field

[0001] This invention relates to the field of nuclear power plant operation control technology, and in particular to a method, control system, control equipment, and readable storage medium for the coordinated control of thermal parameters of the primary and secondary loops in a pressurized water reactor nuclear power plant. Background Technology

[0002] Currently operating pressurized water reactor nuclear power plants generally adopt a primary and secondary loop design. After absorbing the heat of nuclear fission in the reactor core, the primary loop coolant transfers the heat to the secondary loop working fluid through a steam generator. The secondary loop water is heated and evaporated to generate saturated steam, which drives the steam turbine generator set to generate electricity.

[0003] During operation, the heat transfer area of ​​the steam generator is a fixed design parameter and cannot be changed with power adjustments. Therefore, as the unit power increases, the heat transfer load between the primary and secondary loops increases, leading to a corresponding increase in the temperature difference. Under these conditions, if the average temperature of the primary loop is kept constant, the working fluid temperature in the secondary loop will decrease accordingly, causing a significant drop in the steam generator outlet steam pressure at high power. Conversely, at high power, in order to maintain sufficient steam pressure to meet the turbine's operating requirements, the steam generator pressure at low power conditions is much higher than at high power conditions, posing an unnecessary design pressure margin challenge to the pressure-bearing equipment in the secondary loop.

[0004] On the other hand, to maintain a relatively constant main steam pressure in the secondary loop, it is necessary to adjust the average temperature of the reactor coolant in the primary loop to compensate for changes in the heat transfer temperature difference. This will cause the primary loop temperature to fluctuate significantly with power output. These drastic temperature changes not only exacerbate the thermal stress cycle of critical equipment, leading to the risk of thermal fatigue, but also affect reactivity feedback characteristics such as the moderator temperature coefficient, increasing the difficulty of reactivity control.

[0005] In existing coordinated control technologies, most schemes only control the average temperature of the reactor coolant, while the steam pressure is determined by the heat transfer characteristics of the steam generator. For example, reactivity is adjusted using control rods to maintain the average coolant temperature. In such schemes, if the primary loop average temperature is to be kept constant under different power levels, the steam pressure will fluctuate significantly with power changes; if the steam pressure is to remain stable under different power levels, the primary loop average temperature will fluctuate significantly, making it difficult to achieve both simultaneously.

[0006] Therefore, rationally coordinating the temperature and pressure matching between the primary and secondary loops to achieve safe, stable, and efficient operation of nuclear power plants while avoiding the aforementioned control interferences is a technical problem that needs to be solved in the field of pressurized water reactor nuclear power plant control. Summary of the Invention

[0007] To address the aforementioned problems in the prior art, this invention proposes a method, control system, control equipment, and readable storage medium for the coordinated control of the primary and secondary thermal parameters of a pressurized water reactor nuclear power plant, in order to solve the technical problem of severe fluctuations in the primary and secondary parameters in the prior art.

[0008] Specifically, this invention proposes a method for coordinated control of the thermal parameters of the primary and secondary loops in a pressurized water reactor nuclear power plant. The pressurized water reactor nuclear power plant includes a primary loop reactor coolant system and a secondary loop steam generator system. The coordinated control method includes the following steps: S1, regulating the main steam pressure of the secondary loop steam generator system, including: Obtain the main steam pressure of the dual-loop steam generator system; The upper and lower limits of the first dead zone range are determined based on a first predetermined value and a second predetermined value, wherein the first predetermined value is the target set value of the main steam pressure and the second predetermined value is the dead zone control bandwidth value of the main steam pressure; A first trigger signal is generated in response to the main steam pressure exceeding the first dead zone range; Select the first deviation signal based on the first trigger signal; Adjust the valve opening of the main regulating valve of the primary coolant system based on the first deviation signal until the main steam pressure returns to the first dead zone range; S2, adjusting the coolant flow rate of the primary coolant system, including: Obtain the coolant flow rate of the primary coolant system; The upper and lower limits of the second dead zone range are determined based on a third predetermined value and a fourth predetermined value, wherein the third predetermined value is the target set value of the coolant flow rate and the second predetermined value is the dead zone control bandwidth value of the coolant flow rate. A second trigger signal is generated in response to the coolant flow rate exceeding the second dead zone range; The second deviation signal is selected based on the second trigger signal; Adjust the valve opening of the bypass regulating valve of the primary reactor coolant system based on the second deviation signal until the coolant flow rate returns to the second dead zone range.

[0009] According to one embodiment of the present invention, the first predetermined value is 5.5 MPa to 6.5 MPa, and the second predetermined value is 0.05 MPa to 0.15 MPa.

[0010] According to one embodiment of the present invention, the third predetermined value is 90% to 100%, and the fourth predetermined value is 0.05% to 0.15%.

[0011] According to one embodiment of the present invention, determining the upper limit and lower limit of the first dead zone range includes: performing addition and subtraction operations on the first predetermined value and the second predetermined value to generate the upper limit and lower limit of the first dead zone range, respectively. The method of generating a first trigger signal in response to the main steam pressure exceeding the first dead zone range includes: comparing the main steam pressure with the upper limit and lower limit of the first dead zone range respectively; if the main steam pressure is higher than the upper limit of the first dead zone range, generating a first high-value trigger signal; if the main steam pressure is lower than the lower limit of the first dead zone range, generating a first low-value trigger signal. Selecting a first deviation signal based on the first trigger signal includes: when the first high-value trigger signal is valid, calculating the positive deviation between the main steam pressure and the upper limit of the first dead zone range as the first deviation signal; when the first low-value trigger signal is valid, calculating the absolute value of the negative deviation between the main steam pressure and the lower limit of the first dead zone range as the first deviation signal; and selecting a zero signal when both the first high-value trigger signal and the first low-value trigger signal are invalid. Adjusting the valve opening of the main control valve based on the first deviation signal includes: performing PID control processing on the first deviation signal to generate a valve opening adjustment command for the main control valve of the primary reactor coolant system, so as to adjust the valve opening of the main control valve.

[0012] According to one embodiment of the present invention, determining the upper limit and lower limit of the second dead zone range includes: performing addition and subtraction operations on the third predetermined value and the fourth predetermined value to generate the upper limit and lower limit of the second dead zone range, respectively. The method of generating a second trigger signal in response to the coolant flow rate exceeding the second dead zone range includes: comparing the coolant flow rate with the upper limit and lower limit of the second dead zone range respectively; if the coolant flow rate is higher than the upper limit of the second dead zone range, generating a second high-value trigger signal; if the coolant flow rate is less than the lower limit of the second dead zone range, generating a second low-value trigger signal. Selecting a second deviation signal based on the second trigger signal includes: when the second high-value trigger signal is valid, calculating the positive deviation between the coolant flow rate and the upper limit of the second dead zone range as the second deviation signal; when the second low-value trigger signal is valid, calculating the absolute value of the negative deviation between the coolant flow rate and the lower limit of the second dead zone range as the second deviation signal; and selecting a zero signal when both the second high-value trigger signal and the second low-value trigger signal are invalid. Adjusting the valve opening of the bypass regulating valve based on the second deviation signal includes: performing PID control processing on the second deviation signal to generate a valve opening adjustment command for the bypass regulating valve of the primary reactor coolant system, so as to adjust the valve opening of the bypass regulating valve.

[0013] This invention also provides a coordinated control system for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant, wherein the pressurized water reactor nuclear power plant includes a primary loop reactor coolant system and a secondary loop steam generator system, and the coordinated control system includes: A pressure sensor, connected to the secondary loop steam generator system, is used to obtain the main steam pressure of the secondary loop steam generator system; The main regulating valve is installed on the main pipeline of the primary coolant system. A flow meter, connected to the primary coolant system, is used to obtain the coolant flow rate of the primary coolant system. A bypass regulating valve is installed on the bypass pipeline of the primary coolant system. The control unit is connected to the pressure sensor, the main regulating valve, the flow meter, and the bypass regulating valve, respectively. The control unit is configured as follows: A first deviation signal is obtained based on the main steam pressure and a first dead zone range determined by a first predetermined value and a second predetermined value; based on the first deviation signal, a valve opening signal for adjusting the main control valve is obtained so that the main steam pressure returns to the first dead zone range; The upper limit of the first dead zone range is obtained based on the sum of the first predetermined value and the second predetermined value, and the lower limit of the first dead zone range is obtained based on the difference between the first predetermined value and the second predetermined value; the first predetermined value is the target set value of the main steam pressure, and the second predetermined value is the dead zone control bandwidth value of the main steam pressure. A second deviation signal is obtained based on the coolant flow rate and the second dead zone range determined by the third and fourth predetermined values; based on the second deviation signal, a valve opening signal for adjusting the bypass regulating valve is obtained so that the coolant flow rate returns to the second dead zone range; Specifically, the upper limit of the second dead zone range is obtained based on the sum of the third predetermined value and the fourth predetermined value, and the lower limit of the second dead zone range is obtained based on the difference between the third predetermined value and the fourth predetermined value; the third predetermined value is the target set value of the coolant flow rate, and the fourth predetermined value is the dead zone control bandwidth value of the coolant flow rate.

[0014] According to one embodiment of the present invention, the control unit includes a PID controller, which is used to control the main control valve to increase or decrease its valve opening according to the valve opening signal of the main control valve, and to control the bypass control valve to increase or decrease its valve opening according to the valve opening signal of the bypass control valve.

[0015] According to one embodiment of the present invention, the control unit includes a first control subunit, and the first control subunit further includes a first addition logic unit, a first subtraction logic unit, a first high-value trigger logic unit, a first low-value trigger logic unit, and a first switching logic unit; The first addition logic unit is used to calculate the sum of the first predetermined value and the second predetermined value to obtain the upper limit of the first dead zone range, and the first subtraction logic unit is used to calculate the difference between the first predetermined value and the second predetermined value to obtain the lower limit of the first dead zone range. The first high-value triggering logic unit is used to determine whether the main steam pressure exceeds the upper limit of the first dead zone range, and the first low-value triggering logic unit is used to determine whether the main steam pressure exceeds the lower limit of the first dead zone range. The first high-value triggering logic unit and the first low-value triggering logic unit generate trigger signals respectively. The first switching logic unit generates the first deviation signal based on the trigger signal. The PID controller generates a valve opening adjustment command for the main circuit regulating valve of the primary loop reactor coolant system based on the first deviation signal.

[0016] According to one embodiment of the present invention, the control unit further includes a second control subunit, the second control subunit including a second addition logic unit, a second subtraction logic unit, a second high-value trigger logic unit, a second low-value trigger logic unit, and a second switching logic unit; The second addition logic unit is used to calculate the sum of the third predetermined value and the fourth predetermined value to obtain the upper limit value of the second dead zone range, and the second subtraction logic unit is used to calculate the difference between the third predetermined value and the fourth predetermined value to obtain the lower limit value of the second dead zone range; The second high-value triggering logic unit is used to determine whether the coolant flow rate exceeds the upper limit of the second dead zone range, and the second low-value triggering logic unit is used to determine whether the coolant flow rate exceeds the lower limit of the second dead zone range. The second high-value triggering logic unit and the second low-value triggering logic unit generate trigger signals respectively. The second switching logic unit generates a second deviation signal based on the trigger signal. The PID controller generates a valve opening adjustment command for the bypass regulating valve of the primary reactor coolant system based on the second deviation signal.

[0017] The present invention also provides a device for coordinated control of thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor. When the processor executes the computer program, it implements the steps of the coordinated control method for thermal parameters of the primary and secondary loops of the pressurized water reactor nuclear power plant described in any of the preceding claims.

[0018] The present invention also provides a computer-readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, implements the steps of the coordinated control method for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant as described in any of the preceding claims.

[0019] This invention provides a method, control system, control equipment, and readable storage medium for the coordinated control of primary and secondary thermal parameters in pressurized water reactor nuclear power plants. Addressing the problem in existing technologies where temperature and pressure controls are independent and lack coordination, leading to reactive disturbances and water level coupling interference, this invention employs parallel control with dual dead zones. When the temperature exceeds the dead zone, the main and bypass regulating valves directly adjust the coolant flow, replacing the independent control rod temperature and feedwater pressure regulation schemes of existing technologies. The two control loops operate in coordination through the thermal coupling relationship between the primary and secondary loops, stabilizing the main steam pressure and coolant flow, achieving coordinated matching between primary loop temperature and secondary loop pressure, and reducing thermal fatigue and mechanical stress in critical equipment.

[0020] It should be understood that the above general description and the following detailed description of the present invention are exemplary and illustrative, and are intended to provide further explanation of the present invention. Attached Figure Description

[0021] The accompanying drawings are included to provide further explanation of the invention; they are incorporated into and constitute a part of this application. The drawings illustrate embodiments of the invention and, together with this specification, serve to explain the principles of the invention. In the drawings: Figure 1 A schematic diagram of the primary loop reactor coolant system and secondary loop steam generator system of a pressurized water reactor nuclear power plant according to an embodiment of the present invention is shown.

[0022] Figure 2 A flowchart illustrating a method for coordinated control of thermal parameters of the primary and secondary loops in a pressurized water reactor nuclear power plant, according to an embodiment of the present invention, is shown.

[0023] Figure 3 A schematic diagram of the structure of a coordinated control system for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant, according to an embodiment of the present invention, is shown.

[0024] Figure 4 A control principle diagram of the first control subunit according to an embodiment of the present invention is shown.

[0025] Figure 5 A control principle diagram of the second control subunit according to an embodiment of the present invention is shown.

[0026] Figure 6 A system block diagram of a device for coordinated control of thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant, according to an embodiment of the present invention, is shown. Detailed Implementation

[0027] It should be noted that, unless otherwise specified, the embodiments and features described in this application can be combined with each other.

[0028] The technical solutions of the embodiments of this application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of this application, and not all embodiments. The following description of at least one exemplary embodiment is merely illustrative and is in no way intended to limit this application or its application or use. All other embodiments obtained by those skilled in the art based on the embodiments of this application without creative effort are within the scope of protection of this application.

[0029] It should be noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to limit the exemplary embodiments according to this application. As used herein, the singular form is intended to include the plural form as well, unless the context clearly indicates otherwise. Furthermore, it should be understood that when the terms "comprising" and / or "including" are used in this specification, they indicate the presence of features, steps, operations, devices, components, and / or combinations thereof.

[0030] Unless otherwise specifically stated, the relative arrangement, numerical expressions, and values ​​of the components and steps described in these embodiments do not limit the scope of this application. It should also be understood that, for ease of description, the dimensions of the various parts shown in the drawings are not drawn to actual scale. Techniques, methods, and devices known to those skilled in the art may not be discussed in detail, but where appropriate, such techniques, methods, and devices should be considered part of the specification. In all examples shown and discussed herein, any specific values ​​should be interpreted as merely exemplary and not as limitations. Therefore, other examples of exemplary embodiments may have different values. It should be noted that similar reference numerals and letters in the following drawings denote similar items; therefore, once an item is defined in one drawing, it need not be further discussed in subsequent drawings.

[0031] Furthermore, it should be noted that the use of terms such as "first" and "second" to define components is merely for the purpose of distinguishing the corresponding components. Unless otherwise stated, these terms have no special meaning and therefore should not be construed as limiting the scope of protection of this application. In addition, although the terminology used in this application is selected from commonly known and used terms, some terms mentioned in this application's specification may have been chosen by the applicant according to his or her judgment, and their detailed meanings are explained in the relevant sections of this description. Moreover, this application should be understood not only through the actual terms used, but also through the meaning implied by each term.

[0032] Figure 1 A schematic diagram of the primary coolant system and secondary steam generator system of a pressurized water reactor nuclear power plant according to an embodiment of the present invention is shown. As shown, the pressurized water reactor nuclear power plant 100 includes a primary coolant system 110 and a secondary steam generator system 120. The primary coolant system 110 includes a reactor pressure vessel 111, a main circulation pump, a main pipeline 130, and a bypass pipeline 140. After absorbing the heat generated by nuclear fission in the reactor pressure vessel 111, the coolant is transported to the secondary steam generator system 120 via the main pipeline 130. The heat is then transferred to the secondary working fluid through the secondary loop to generate steam, which drives the turbine to generate electricity. The secondary steam generator system 120 and the primary coolant system 110 are thermally connected through the main pipeline 130 and the bypass pipeline 140, providing a physical basis for subsequent coordinated control of primary and secondary loop parameters. The main regulating valve 131 is installed on the main pipeline 130 of the primary coolant system 110, and it regulates the main steam pressure of the secondary steam generator system 120 by changing the coolant flow rate. The bypass regulating valve 141 is installed on the bypass pipeline 140 of the primary coolant system 110, and it distributes the coolant ratio between the main loop and the bypass by regulating the bypass flow rate.

[0033] Figure 2 A flowchart illustrating a method for coordinated control of thermal parameters in the primary and secondary loops of a pressurized water reactor nuclear power plant, according to an embodiment of the present invention, is shown. In some embodiments, the method for coordinated control of thermal parameters in the primary and secondary loops of a pressurized water reactor nuclear power plant includes the following steps: S1, regulating the main steam pressure of the secondary circuit steam generator system 120 includes: Obtain the main steam pressure of the secondary loop steam generator system; The upper and lower limits of the first dead zone range are determined based on the first predetermined value and the second predetermined value, wherein the first predetermined value is the target set value of the main steam pressure and the second predetermined value is the dead zone control bandwidth value of the main steam pressure. A first trigger signal is generated in response to the main steam pressure exceeding the first dead zone range; The first deviation signal is selected based on the first trigger signal; Adjust the valve opening of the main control valve of the primary coolant system based on the first deviation signal until the main steam pressure returns to the first dead zone range.

[0034] In the above steps, the main steam pressure is selected as the controlled parameter of the secondary loop steam generator system 120 because it directly reflects the energy output status of the secondary loop and is a key indicator for measuring the operating condition of the steam generator. A dead-zone control range is established using a first predetermined value and a second predetermined value. When the controlled parameter is within the dead zone, no adjustment action is performed, reducing the frequency of operation of the main regulating valve 131 and avoiding frequent adjustments and equipment wear caused by small fluctuations near the setpoint, thus extending the valve's service life. The main regulating valve 131 is selected as the actuator because it is located on the main pipeline 130 of the primary loop reactor coolant system 110. It regulates pressure by directly changing the coolant discharge rate, resulting in a fast response speed and avoiding interference with the primary loop reactivity, thus avoiding the reactivity disturbance problems caused by control rod adjustment.

[0035] S2, adjusting the coolant flow rate of the primary coolant system, including: Obtain the coolant flow rate of the primary coolant system; The upper and lower limits of the second dead zone range are determined based on the third and fourth predetermined values, wherein the third predetermined value is the target set value of the coolant flow rate and the second predetermined value is the dead zone control bandwidth value of the coolant flow rate. A second trigger signal is generated in response to the coolant flow rate exceeding the second dead zone range; The second deviation signal is selected based on the second trigger signal; The valve opening of the bypass regulating valve of the primary coolant system is adjusted based on the second deviation signal until the coolant flow rate returns to the second dead zone range.

[0036] In the above steps, the coolant flow rate is chosen as the controlled parameter of the primary coolant system 110 because it directly affects the heat carrying capacity and heat transfer conditions of the primary circuit. Stable flow rate helps maintain a stable primary circuit temperature. Similarly, a dead-zone control strategy is employed to reduce unnecessary operation of the bypass regulating valve 141. The bypass regulating valve 141 is chosen as the actuator because it is located on the bypass pipe 140 of the primary coolant system 110. By adjusting the bypass flow rate, it distributes the coolant share between the main circuit and the bypass, thereby controlling the total circulation flow rate. This method does not rely on main pump speed regulation and does not change reactivity, avoiding the reactivity disturbances introduced by temperature regulation via control rods in existing technologies. The two control loops independently perform dead-zone control on their respective controlled parameters. At the same time, the operating states of the two loops affect each other through the thermal coupling relationship between the primary and secondary loops. When the main steam pressure changes and causes a change in the heat transfer temperature difference, the corresponding adjustment of the coolant flow rate can compensate for the impact of this change on the temperature of the primary loop, and vice versa. Thus, the thermal parameters of the primary and secondary loops are coordinated and matched within the full power operating range.

[0037] Specifically, the pressure of the steam generator is affected by its operating temperature, which is directly related to the heat transfer conditions of the primary reactor coolant system. The principle of controlling the steam generator temperature by adjusting the reactor coolant flow rate can be described by the following equation: ; ; ; ; in, The average temperature of the reactor coolant. This is the total flow rate of the reactor coolant (i.e., the sum of the main flow rate and the bypass flow rate). This refers to the temperature of the hot section of the reactor coolant. This refers to the temperature of the cold section of the reactor coolant. For the enthalpy of the reactor coolant thermal section, For the enthalpy of the reactor coolant cold section, For reactor power, This refers to the main flow rate of the reactor coolant. The heat transfer coefficient of the heat transfer tubes in the steam generator. The heat exchange area of ​​the heat transfer tubes in the steam generator. This refers to the temperature of the main coolant path cold section of the reactor. The enthalpy of the main cooling section of the reactor coolant. This refers to the secondary side temperature of the steam generator.

[0038] When the main regulating valve changes its opening, the reactor coolant main flow rate... It changes accordingly. As can be seen from the above equation, The change will cause the temperature of the main coolant path cold section of the reactor to change. The change, and at the same time the heat transfer coefficient of the steam generator heat transfer tubes Also follow The changes in main steam pressure lead to corresponding adjustments, ultimately controlling the temperature and pressure of the steam generator. Therefore, when changes in main steam pressure cause changes in the heat transfer temperature difference, the corresponding adjustment of the coolant flow rate can compensate for the impact of this change on the primary loop temperature; conversely, when changes in coolant flow rate cause changes in the primary loop temperature, the corresponding adjustment of the main steam pressure can maintain stable pressure in the secondary loop. Thus, the two control loops operate collaboratively across the entire power operating range, achieving coordinated matching of the thermal parameters of the primary and secondary loops.

[0039] In some examples, the first predetermined value is 5.5 MPa to 6.5 MPa, and the second predetermined value is 0.05 MPa to 0.15 MPa. This range is determined based on the actual engineering requirements of the main steam pressure of the steam generator within the full power operating range of a pressurized water reactor nuclear power plant. The range of 5.5 MPa to 6.5 MPa covers a reasonable setting range of steam pressure from low power to full power conditions, while the deadband bandwidth of 0.05 MPa to 0.15 MPa balances control accuracy and valve operation frequency. Too small a bandwidth can lead to frequent adjustments, while too large a bandwidth results in insufficient control accuracy.

[0040] In some examples, the third predetermined value is 90% to 100%, and the fourth predetermined value is 0.05% to 0.15%. The third predetermined value of 90% to 100% corresponds to the rated flow condition and serves as the reference setpoint for coolant flow control. The fourth predetermined value range of 0.05% to 0.15% is consistent with the second predetermined value in terms of engineering magnitude, ensuring that the response characteristics of the control loops on both sides are matched.

[0041] In some examples, determining the upper and lower limits of the first dead zone range includes: performing addition and subtraction operations on a first predetermined value and a second predetermined value to generate a high steam pressure setpoint and a low steam pressure setpoint, i.e., the upper and lower limits of the first dead zone range; generating a first trigger signal in response to the main steam pressure exceeding the first dead zone range includes: comparing the main steam pressure with the upper and lower limits of the first dead zone range respectively; if the main steam pressure is higher than the high steam pressure setpoint, generating a first high-value trigger signal; if the main steam pressure is lower than the low steam pressure setpoint, generating a first low-value trigger signal; selecting a first deviation signal based on the first trigger signal includes: when the first... When the high-value trigger signal is valid, the positive deviation between the main steam pressure and the upper limit of the first dead zone range is calculated as the first deviation signal. When the low-value trigger signal is valid, the absolute value of the negative deviation between the main steam pressure and the lower limit of the first dead zone range is selected as the first deviation signal. When both trigger signals are invalid, the zero signal is selected. Adjusting the valve opening of the main control valve based on the first deviation signal includes: performing PID control processing on the first deviation signal, performing proportional, integral, and derivative operations in sequence and superimposing them to generate a valve opening adjustment command, which is output to the main control valve 131 of the primary circuit reactor coolant system 110 to adjust its valve opening so that the main steam pressure returns to the first dead zone range.

[0042] In the above signal processing, addition and subtraction operations are used to calculate the upper and lower boundaries of the first dead zone, respectively, forming a clear pressure judgment benchmark. The controlled parameter is compared with the dead zone boundary; when the controlled parameter exceeds the dead zone, a trigger signal is generated, providing a conditional judgment for subsequent control actions. Based on the state of the trigger signal, the corresponding deviation signal is selected for output. Within the dead zone, a zero signal is selected to suppress the adjustment action; outside the dead zone, an actual deviation signal is selected to drive the adjustment. PID control processing utilizes a linear combination of proportional, integral, and derivative terms to calculate the deviation signal. The proportional term makes the adjustment proportional to the deviation, the integral term eliminates steady-state error, and the derivative term improves dynamic response, thereby enabling the main steam pressure to be more accurately stabilized near the target value within the first dead zone.

[0043] In some examples, determining the upper and lower limits of the second dead zone range includes: performing addition and subtraction operations based on a third and a fourth predetermined value to generate a high coolant flow rate setting value and a low coolant flow rate setting value, i.e., the upper and lower limits of the second dead zone range. Generating a second trigger signal in response to the coolant flow rate exceeding the second dead zone range includes: comparing the acquired coolant flow rate with the high coolant flow rate setting value and the low coolant flow rate setting value respectively; if the coolant flow rate is higher than the high coolant flow rate setting value, generating a second high-value trigger signal; if the coolant flow rate is lower than the low coolant flow rate setting value, generating a second low-value trigger signal. Selecting a second deviation signal based on the second trigger signal includes: when the second high-value trigger signal is valid, selecting a positive deviation between the coolant flow rate and the upper limit of the second dead zone range as the second deviation signal. When the second low-value trigger signal is valid, the absolute value of the negative deviation between the coolant flow rate and the lower limit of the second dead zone range is selected as the second deviation signal. When both trigger signals are invalid, the zero signal is selected. Adjusting the valve opening of the bypass regulating valve based on the second deviation signal includes: performing PID control processing on the second deviation signal, performing proportional, integral and derivative operations in sequence and superimposing them to generate a valve opening adjustment command, which is output to the bypass regulating valve 141 of the primary reactor coolant system 110 to adjust its valve opening so that the coolant flow rate returns to the dead zone range.

[0044] In the aforementioned signal processing, addition and subtraction operations determine the upper and lower boundaries of the second dead zone range, respectively, forming a clear flow judgment benchmark. The controlled parameter is compared with the dead zone boundary; when the controlled parameter exceeds the dead zone range, a trigger signal is generated, providing a conditional judgment for subsequent control actions. Based on the state of the trigger signal, the corresponding second deviation signal is output: a zero signal is selected within the dead zone range to suppress the adjustment action, and an actual deviation signal is selected outside the dead zone range to drive the adjustment. The PID control process calculates the second deviation signal and generates a valve opening adjustment command for the bypass regulating valve 141. The two control loops operate independently, achieving closed-loop control of the controlled parameter through their respective complete signal processing links, while simultaneously achieving mutual coordination of operating states through thermal coupling between the first and second loops.

[0045] Figure 3 A schematic diagram of a cooperative control system 300 according to an embodiment of the present invention is shown. As shown in the figure, the present invention also provides a cooperative control system 300. A pressurized water reactor nuclear power plant 100 includes a primary loop reactor coolant system 110 and a secondary loop steam generator system 120. The cooperative control system 300 includes: Pressure sensor 301 is connected to the secondary loop steam generator system 120 and is used to acquire the main steam pressure of the secondary loop steam generator system 120. Pressure sensor 301 is selected as the signal input terminal because the main steam pressure is a key parameter reflecting the operating status of the secondary loop steam generator system 120, converting the physical pressure signal into an electrical signal that can be recognized by the control unit 305.

[0046] The main regulating valve 302 is installed on the main pipeline 130 of the primary coolant system 110. This valve acts as an actuator on the primary coolant system 110 side, directly regulating the steam discharge in the main pipeline 130 by changing the valve opening, thereby controlling the main steam pressure of the secondary steam generator system 120. Installing it on the main pipeline 130, rather than elsewhere, shortens the response time of the control channel.

[0047] Flow meter 303, connected to the primary coolant system 110, is used to acquire the coolant flow rate of the primary coolant system 110. This coolant flow rate is the total coolant flow rate, which is the sum of the coolant flows in the main pipeline 130 and the bypass pipeline 140. This module serves as the signal input terminal on the primary coolant system 110 side, converting the physical quantity of coolant flow rate into an electrical signal, providing a data basis for subsequent control decisions.

[0048] A bypass regulating valve 304 is installed on the bypass pipe 140 of the primary coolant system 110. This valve acts as an actuator on the primary coolant system 110 side, adjusting the flow distribution between the main circuit and the bypass by changing the coolant flow rate in the bypass pipe 140, thereby controlling the total circulating flow rate of the primary coolant system 110. By using bypass regulation instead of directly adjusting the main pump speed, flow regulation can be achieved without changing the main pump's operating conditions, reducing interference with the primary main circulation system.

[0049] Control unit 305 is connected to pressure sensor 301, main regulating valve 302, flow meter 303 and bypass regulating valve 304 respectively. Control unit 305 is configured as follows: A first deviation signal is obtained based on the main steam pressure and a first dead zone range determined by a first predetermined value and a second predetermined value. Based on the first deviation signal, a valve opening signal for regulating the main control valve 302 is obtained to bring the main steam pressure back to the first dead zone range. Specifically, the upper limit of the first dead zone range is obtained based on the sum of the first and second predetermined values, and the lower limit of the first dead zone range is obtained based on the difference between the first and second predetermined values. The first predetermined value is the target setpoint value for the main steam pressure, and the second predetermined value is the dead zone control bandwidth value for the main steam pressure. A second deviation signal is obtained based on the coolant flow rate and the second dead zone range determined by the third and fourth predetermined values. Based on the second deviation signal, a valve opening signal for the regulating bypass valve 304 is obtained to bring the coolant flow rate back to the second dead zone range. Specifically, the upper limit of the second dead zone range is obtained based on the sum of the third and fourth predetermined values, and the lower limit of the second dead zone range is obtained based on the difference between the third and fourth predetermined values. The third predetermined value is the target setpoint for the coolant flow rate, and the fourth predetermined value is the dead zone control bandwidth value for the coolant flow rate.

[0050] The control unit 305 receives input signals from the sensor modules on both sides, performs dead-zone determination and control calculations, and outputs valve opening adjustment commands to the actuators on both sides. The signal connections between the above five functional modules can be achieved through the input / output channels of the distributed control system of the pressurized water reactor nuclear power plant. The functions of the control unit 305 are completed by the control processor of the distributed control system executing the corresponding control algorithms. Integrating the dual-dead-zone control function into the existing distributed control system platform eliminates the need for additional independent control hardware, improving engineering feasibility.

[0051] In some examples, the control unit 305 includes a PID controller, which controls the main control valve 302 to increase or decrease its valve opening based on the valve opening signal of the main control valve 302, and controls the bypass control valve 304 to increase or decrease its valve opening based on the valve opening signal of the bypass control valve 304.

[0052] The purpose of using a PID controller to process the deviation signal is to utilize the operational characteristics of its proportional, integral, and derivative components to make the adjustment proportional to the deviation, thereby eliminating steady-state error and improving the dynamic response characteristics of the system. Independent PID controllers can be configured on the main steam pressure side and the coolant flow side respectively. The two controllers can operate independently or simultaneously, allowing for flexible configuration based on actual operating conditions.

[0053] In some examples, control unit 305 includes a first control subunit. Figure 4 A control principle diagram of a first control subunit according to an embodiment of the present invention is shown. As shown in the figure, the first control subunit includes a first addition logic unit 401, a first subtraction logic unit 402, a first high-value trigger logic unit 403, a first low-value trigger logic unit 404, and a first switching logic unit 405.

[0054] The first addition logic unit 401 is used to obtain and calculate the sum of the first predetermined value and the second predetermined value as the upper limit of the first dead zone range. The first subtraction logic unit 402 is used to obtain and calculate the difference between the first predetermined value and the second predetermined value as the lower limit of the first dead zone range. After processing, the first addition logic unit 401 generates an intermediate signal for the high steam pressure setting value, and after processing, the first subtraction logic unit 402 generates an intermediate signal for the low steam pressure setting value. The upper and lower boundaries of the dead zone are generated by addition and subtraction operations, respectively, forming a clear pressure judgment benchmark, so that the dead zone range has a definite numerical boundary, which facilitates the accurate comparison of subsequent triggering logic. The main steam pressure and the intermediate signal for the high steam pressure setting value are then subtracted to generate an intermediate signal for the high steam pressure deviation, and the main steam pressure and the intermediate signal for the low steam pressure setting value are then subtracted to generate an intermediate signal for the low steam pressure deviation.

[0055] The first high-value trigger logic unit 403 processes the high-deviation intermediate signal of steam pressure to determine whether the main steam pressure exceeds the upper limit of the first dead zone range. The first low-value trigger logic unit 404 processes the low-deviation intermediate signal of steam pressure to determine whether the main steam pressure exceeds the lower limit of the first dead zone range. The first high-value trigger logic unit 403 and the first low-value trigger logic unit 404 generate trigger signals respectively. Specifically, the two trigger logic units respectively complete the boundary judgment of the controlled parameter and the dead zone boundary. The high-value trigger logic detects whether it exceeds the upper boundary of the dead zone, and the low-value trigger logic detects whether it is below the lower boundary of the dead zone. The two judgment results are output as trigger signals to provide input conditions for the switching logic.

[0056] The first switching logic unit 405 generates a first deviation signal based on the trigger signal. The PID controller generates a valve opening adjustment command for the main control valve 302 of the primary reactor coolant system 110 based on the first deviation signal. If the intermediate signal indicating that the main steam pressure is lower than the difference between the first and second predetermined values ​​is true, the first switching logic unit 405 outputs a low deviation steam pressure intermediate signal. If the intermediate signal indicating that the main steam pressure is higher than the sum of the first and second predetermined values ​​is true, the first switching logic unit 405 outputs a high deviation steam pressure intermediate signal. If both trigger signals are false, the first switching logic unit 405 outputs a zero signal. The first switching logic unit 405 selects a signal based on the state of the two trigger signals. When the controlled parameter is within the dead zone, it outputs a zero signal to suppress the adjustment action. When the controlled parameter exceeds the dead zone, it outputs a corresponding deviation signal for the PID controller to process. After calculation, the PID controller generates a valve opening adjustment command to drive the main control valve 302 to perform adjustment.

[0057] In some examples, the control unit 305 also includes a second control subunit. Figure 5A control principle diagram of the second control subunit according to an embodiment of the present invention is shown. As shown in the figure, the second control subunit includes a second addition logic unit 501, a second subtraction logic unit 502, a second high-value trigger logic unit 503, a second low-value trigger logic unit 504, and a second switching logic unit 505.

[0058] The second addition logic unit 501 is used to obtain and calculate the sum of the third predetermined value and the fourth predetermined value to generate the upper limit value of the second dead zone range. The second subtraction logic unit 502 is used to obtain and calculate the difference between the third predetermined value and the fourth predetermined value to generate the lower limit value of the second dead zone range. After processing, the second addition logic unit 501 generates an intermediate signal for the high coolant flow setting value, and after processing, the second subtraction logic unit 502 generates an intermediate signal for the low coolant flow setting value. The second addition logic unit 501 and the second subtraction logic unit 502 respectively determine the upper and lower boundaries of the coolant flow dead zone, forming a clear flow judgment benchmark. The coolant flow rate and the intermediate signal for the high coolant flow setting value are then subtracted to generate an intermediate signal for the high coolant flow deviation, and the coolant flow rate and the intermediate signal for the low coolant flow setting value are then subtracted to generate an intermediate signal for the low coolant flow deviation.

[0059] The second high-value trigger logic unit 503 processes the intermediate signal of the high setpoint of the coolant flow rate to determine whether the coolant flow rate exceeds the upper limit of the second dead zone range. The second low-value trigger logic unit 504 processes the intermediate signal of the low setpoint of the coolant flow rate to determine whether the coolant flow rate exceeds the lower limit of the second dead zone range. The second high-value trigger logic unit 503 and the second low-value trigger logic unit 504 generate trigger signals respectively. The two trigger logic units respectively complete the boundary judgment of coolant flow rate and dead zone boundary.

[0060] The second switching logic unit 505 generates a second deviation signal based on the trigger signal. The PID controller generates a valve opening adjustment command for the bypass regulating valve 304 of the primary reactor coolant system 110 based on the second deviation signal. If the coolant flow rate is lower than the difference between the third and fourth predetermined values, the second switching logic unit 505 outputs a low deviation intermediate signal for the coolant flow rate; if the coolant flow rate is higher than the sum of the third and fourth predetermined values, it outputs a high deviation intermediate signal for the coolant flow rate; if the coolant flow rate is within the dead zone, it outputs a zero signal. The second switching logic unit 505 outputs a zero signal within the dead zone to suppress the regulation action, and outputs a corresponding deviation signal outside the dead zone for the PID controller to calculate and generate a valve opening adjustment command for the bypass regulating valve 304, thereby driving the bypass regulating valve 304 to perform regulation.

[0061] The second control subunit forms a symmetrical dual-loop control architecture with the first control subunit. The second addition logic unit 501 and the second subtraction logic unit 502 determine the upper and lower boundaries of the coolant flow dead zone, respectively. The second high-value trigger logic unit 503 and the second low-value trigger logic unit 504 complete the boundary judgment. The second switching logic unit 505 implements the deviation signal selection. After the PID controller calculates the deviation signal, it generates a valve opening adjustment command for the bypass regulating valve 304, driving the bypass regulating valve 304 to perform regulation. The two control subunits operate independently, each forming a complete signal processing link. The thermal coupling between the first and second loops achieves mutual coordination of the operating states.

[0062] Figure 6 A system block diagram of a coordinated control device for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant, according to an embodiment of the present invention, is shown. As shown, the coordinated control device 600 may include an internal communication bus 601, a processor 602, a read-only memory (ROM) 603, a random access memory (RAM) 604, and a communication port 605. When applied to a personal computer, the coordinated control device 600 may also include a hard disk 606. The internal communication bus 601 enables data communication between the components of the coordinated control device 600. The processor 602 can perform judgments and issue prompts. In some embodiments, the processor 602 may consist of one or more processors. The communication port 605 enables data communication between the coordinated control device 600 and external systems. In some embodiments, the coordinated control device 600 can send and receive information and data from a network through the communication port 605. The collaborative control device 600 may also include different forms of program storage units and data storage units, such as a hard disk 606, a read-only memory (ROM) 603, and a random access memory (RAM) 604, capable of storing various data files used for computer processing and / or communication, as well as possible program instructions executed by the processor 602. The processor 602 executes these instructions to implement the main part of the method. The results processed by the processor 602 are transmitted to the user equipment via the communication port 605 and displayed on the user interface.

[0063] The aforementioned method for coordinated control of the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant can be implemented as a computer program, stored in hard disk 606, and loaded into processor 602 for execution, in order to implement the method for coordinated control of the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant as described in this application.

[0064] The present invention also provides a computer-readable storage medium storing a computer program thereon, wherein the computer program, when executed by a processor, implements the steps of any of the aforementioned methods for coordinated control of the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant.

[0065] The specific implementation methods and technical effects of the collaborative control equipment and computer-readable storage medium for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant can be found in the embodiments of the collaborative control method for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant provided by the present invention, and will not be repeated here.

[0066] The method, control system, control equipment, and readable storage medium for coordinated control of primary and secondary thermal parameters in pressurized water reactor nuclear power plants provided by this invention have the following advantages compared with the prior art: 1. By using a dual-dead-zone parallel control strategy, the control valve does not perform any action when the controlled parameter is within the dead zone range, which reduces the frequency of action of the main control valve and the bypass control valve and reduces valve mechanical wear.

[0067] 2. The main steam pressure is directly regulated by the main regulating valve and the coolant flow rate is directly regulated by the bypass regulating valve, which avoids the defect in the prior art that the steam pressure cannot be effectively controlled after the average temperature of the coolant is controlled.

[0068] 3. The two control loops operate in coordination through the thermal coupling relationship between the primary and secondary loops, so that the main steam pressure and coolant flow rate are stabilized within their respective dead zones, thereby achieving coordinated matching of the thermal parameters of the primary and secondary loops.

[0069] 4. By adopting dead-zone control, the main steam pressure of the secondary loop steam generator system is limited to the range determined by the first and second predetermined values. This eliminates the need to maintain excessively high main steam pressure during low-power operation. Consequently, the internal and external pressure difference borne by pressure-bearing equipment such as the steam generator shell, main steam pipeline, and valves is reduced under low-load conditions, the mechanical stress level decreases, the rate of fatigue damage accumulation slows down, and this helps to extend the design service life of the equipment.

[0070] 5. By using a bypass regulating valve, the coolant flow rate of the primary coolant system is stabilized within the range determined by the third and fourth predetermined values, thereby maintaining stable heat transfer conditions in the primary loop. This reduces the temperature change rate of key components such as the reactor pressure vessel, main pipelines, and steam generator shell, and consequently decreases the frequency and amplitude of thermal stress cycles. This mitigates thermal fatigue effects and enhances the structural integrity and long-term operational reliability of the primary loop system.

[0071] 6. As the average temperature fluctuation of the primary coolant system decreases, the temperature change of the moderator (i.e., coolant water) weakens accordingly. The magnitude of reactivity change caused by the moderator temperature coefficient decreases, the reactivity feedback disturbance in the core weakens, the amount of compensation and adjustment required by the reactor power control system decreases, the adjustment burden is reduced, thereby improving the accuracy of automatic control and operational stability.

[0072] Those skilled in the art will further appreciate that the various illustrative logic blocks, modules, circuits, and algorithm steps described in conjunction with the embodiments disclosed herein can be implemented as electronic hardware, computer software, or a combination of both. To clearly illustrate this interchangeability between hardware and software, the various illustrative components, blocks, modules, circuits, and steps are described above in a generalized manner in terms of their functionality. Whether such functionality is implemented as hardware or software depends on the specific application and the design constraints imposed on the overall system. Those skilled in the art may implement the described functionality in different ways for each specific application, but such implementation decisions should not be construed as departing from the scope of the invention.

[0073] The various illustrative logic modules and circuits described in conjunction with the embodiments disclosed herein may be implemented or performed using a general-purpose processor, a digital signal processor (DSP), an application-specific integrated circuit (ASIC), a field-programmable gate array (FPGA) or other programmable logic device, discrete gate or transistor logic, discrete hardware components, or any combination thereof designed to perform the functions described herein. The general-purpose processor may be a microprocessor, but in alternatives, it may be any conventional processor, controller, microcontroller, or state machine. The processor may also be implemented as a combination of cooperating control devices, such as a combination of a DSP and a microprocessor, multiple microprocessors, one or more microprocessors cooperating with a DSP core, or any other such configuration.

[0074] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of both. The software module may reside in RAM memory, flash memory, ROM memory, EPROM memory, EEPROM memory, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art. An exemplary storage medium is coupled to a processor such that the processor can read and write information to / from the storage medium. In an alternative, the storage medium may be integrated into the processor. The processor and storage medium may reside in an ASIC. The ASIC may reside in a user terminal. In an alternative, the processor and storage medium may reside as discrete components in the user terminal.

[0075] In one or more exemplary embodiments, the described functionality may be implemented in hardware, software, firmware, or any combination thereof. If implemented in software as a computer program product, the functionality may be stored or transmitted as one or more instructions or code on or through a computer-readable medium. A computer-readable medium includes both computer storage media and communication media, encompassing any medium that facilitates the transfer of a computer program from one location to another. A storage medium may be any available medium accessible to a computer. By way of example and not limitation, such a computer-readable medium may include RAM, ROM, EEPROM, CD-ROM or other optical disc storage, disk storage or other magnetic storage devices, or any other medium that can be used to carry or store desired program code in the form of instructions or data structures and is accessible to a computer. Any connection is also legitimately referred to as a computer-readable medium. For example, if the software is transmitted from a website, server, or other remote source using coaxial cable, fiber optic cable, twisted pair, digital subscriber line (DSL), or wireless technologies such as infrared, radio, and microwave, then the coaxial cable, fiber optic cable, twisted pair, DSL, or wireless technologies such as infrared, radio, and microwave are included in the definition of a medium. As used in this article, disk and disc include compact discs (CDs), laser discs, optical discs, digital multi-purpose discs (DVDs), floppy disks, and Blu-ray discs. Disks typically reproduce data magnetically, while discs reproduce data optically using lasers. Combinations of these should also be included within the scope of computer-readable media.

[0076] It will be apparent to those skilled in the art that various modifications and variations can be made to the exemplary embodiments described above without departing from the spirit and scope of the invention. Therefore, it is intended that this invention cover modifications and variations falling within the scope of the appended claims and their equivalents.

Claims

1. A method for coordinated control of thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant, wherein the pressurized water reactor nuclear power plant includes a primary loop reactor coolant system and a secondary loop steam generator system, and the coordinated control method includes the following steps: S1, regulating the main steam pressure of the secondary loop steam generator system, including: Obtain the main steam pressure of the dual-loop steam generator system; The upper and lower limits of the first dead zone range are determined based on a first predetermined value and a second predetermined value, wherein the first predetermined value is the target set value of the main steam pressure and the second predetermined value is the dead zone control bandwidth value of the main steam pressure; A first trigger signal is generated in response to the main steam pressure exceeding the first dead zone range; Select the first deviation signal based on the first trigger signal; Adjust the valve opening of the main regulating valve of the primary coolant system based on the first deviation signal until the main steam pressure returns to the first dead zone range; S2, adjusting the coolant flow rate of the primary coolant system, including: Obtain the coolant flow rate of the primary coolant system; The upper and lower limits of the second dead zone range are determined based on a third predetermined value and a fourth predetermined value, wherein the third predetermined value is the target set value of the coolant flow rate and the second predetermined value is the dead zone control bandwidth value of the coolant flow rate. A second trigger signal is generated in response to the coolant flow rate exceeding the second dead zone range; The second deviation signal is selected based on the second trigger signal; Based on the second deviation signal, adjust the valve opening of the bypass regulating valve of the primary coolant system until the coolant flow rate returns to the second dead zone range.

2. The method for coordinated control of primary and secondary thermal parameters in a pressurized water reactor nuclear power plant as described in claim 1, characterized in that, The first predetermined value is 5.5 MPa to 6.5 MPa, and the second predetermined value is 0.05 MPa to 0.15 MPa.

3. The method for coordinated control of primary and secondary thermal parameters in a pressurized water reactor nuclear power plant as described in claim 2, characterized in that, The third predetermined value is 90% to 100%, and the fourth predetermined value is 0.05% to 0.15%.

4. The method for coordinated control of primary and secondary thermal parameters in a pressurized water reactor nuclear power plant as described in claim 1, characterized in that, Determining the upper and lower limits of the first dead zone range includes: performing addition and subtraction operations on the first predetermined value and the second predetermined value to generate the upper and lower limits of the first dead zone range, respectively. The method of generating a first trigger signal in response to the main steam pressure exceeding the first dead zone range includes: comparing the main steam pressure with the upper limit and lower limit of the first dead zone range respectively; if the main steam pressure is higher than the upper limit of the first dead zone range, generating a first high-value trigger signal; if the main steam pressure is lower than the lower limit of the first dead zone range, generating a first low-value trigger signal. Selecting a first deviation signal based on the first trigger signal includes: when the first high-value trigger signal is valid, calculating the positive deviation between the main steam pressure and the upper limit of the first dead zone range as the first deviation signal; when the first low-value trigger signal is valid, calculating the absolute value of the negative deviation between the main steam pressure and the lower limit of the first dead zone range as the first deviation signal; and selecting a zero signal when both the first high-value trigger signal and the first low-value trigger signal are invalid. Adjusting the valve opening of the main control valve based on the first deviation signal includes: performing PID control processing on the first deviation signal to generate a valve opening adjustment command for the main control valve of the primary reactor coolant system, so as to adjust the valve opening of the main control valve.

5. The method for coordinated control of primary and secondary thermal parameters in a pressurized water reactor nuclear power plant as described in claim 1, characterized in that, Determining the upper and lower limits of the second dead zone range includes: performing addition and subtraction operations on the third predetermined value and the fourth predetermined value to generate the upper and lower limits of the second dead zone range, respectively. The method of generating a second trigger signal in response to the coolant flow rate exceeding the second dead zone range includes: comparing the coolant flow rate with the upper limit and lower limit of the second dead zone range respectively; if the coolant flow rate is higher than the upper limit of the second dead zone range, generating a second high-value trigger signal; if the coolant flow rate is less than the lower limit of the second dead zone range, generating a second low-value trigger signal. Selecting a second deviation signal based on the second trigger signal includes: when the second high-value trigger signal is valid, calculating the positive deviation between the coolant flow rate and the upper limit of the second dead zone range as the second deviation signal; when the second low-value trigger signal is valid, calculating the absolute value of the negative deviation between the coolant flow rate and the lower limit of the second dead zone range as the second deviation signal; and selecting a zero signal when both the second high-value trigger signal and the second low-value trigger signal are invalid. Adjusting the valve opening of the bypass regulating valve based on the second deviation signal includes: performing PID control processing on the second deviation signal to generate a valve opening adjustment command for the bypass regulating valve of the primary reactor coolant system, so as to adjust the valve opening of the bypass regulating valve.

6. A coordinated control system for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant, wherein the pressurized water reactor nuclear power plant includes a primary loop reactor coolant system and a secondary loop steam generator system, and the coordinated control system includes: A pressure sensor, connected to the secondary loop steam generator system, is used to obtain the main steam pressure of the secondary loop steam generator system; The main regulating valve is installed on the main pipeline of the primary coolant system. A flow meter, connected to the primary coolant system, is used to obtain the coolant flow rate of the primary coolant system. A bypass regulating valve is installed on the bypass pipeline of the primary coolant system. The control unit is connected to the pressure sensor, the main regulating valve, the flow meter, and the bypass regulating valve, respectively. The control unit is configured as follows: A first deviation signal is obtained based on the main steam pressure and a first dead zone range determined by a first predetermined value and a second predetermined value; based on the first deviation signal, a valve opening signal for adjusting the main control valve is obtained so that the main steam pressure returns to the first dead zone range; The upper limit of the first dead zone range is obtained based on the sum of the first predetermined value and the second predetermined value, and the lower limit of the first dead zone range is obtained based on the difference between the first predetermined value and the second predetermined value; the first predetermined value is the target set value of the main steam pressure, and the second predetermined value is the dead zone control bandwidth value of the main steam pressure. A second deviation signal is obtained based on the coolant flow rate and the second dead zone range determined by the third and fourth predetermined values; based on the second deviation signal, a valve opening signal for adjusting the bypass regulating valve is obtained so that the coolant flow rate returns to the second dead zone range; Specifically, the upper limit of the second dead zone range is obtained based on the sum of the third predetermined value and the fourth predetermined value, and the lower limit of the second dead zone range is obtained based on the difference between the third predetermined value and the fourth predetermined value; the third predetermined value is the target set value of the coolant flow rate, and the fourth predetermined value is the dead zone control bandwidth value of the coolant flow rate.

7. The coordinated control system for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant as described in claim 6, characterized in that, The control unit includes a PID controller, which is used to control the main regulating valve to increase or decrease its valve opening based on the valve opening signal of the main regulating valve, and to control the bypass regulating valve to increase or decrease its valve opening based on the valve opening signal of the bypass regulating valve.

8. The coordinated control system for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant as described in claim 7, characterized in that, The control unit further includes a first control subunit, which includes a first addition logic unit, a first subtraction logic unit, a first high-value trigger logic unit, a first low-value trigger logic unit, and a first switching logic unit. The first addition logic unit is used to calculate the sum of the first predetermined value and the second predetermined value to obtain the upper limit of the first dead zone range, and the first subtraction logic unit is used to calculate the difference between the first predetermined value and the second predetermined value to obtain the lower limit of the first dead zone range. The first high-value triggering logic unit is used to determine whether the main steam pressure exceeds the upper limit of the first dead zone, and the first low-value triggering logic unit is used to determine whether the main steam pressure exceeds the lower limit of the first dead zone. The first high-value triggering logic unit and the first low-value triggering logic unit generate trigger signals respectively. The first switching logic unit generates the first deviation signal based on the trigger signal. The PID controller generates a valve opening adjustment command for the main regulating valve of the primary loop reactor coolant system based on the first deviation signal.

9. The coordinated control system for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant as described in claim 8, characterized in that, The control unit further includes a second control subunit, which includes a second addition logic unit, a second subtraction logic unit, a second high-value trigger logic unit, a second low-value trigger logic unit, and a second switching logic unit. The second addition logic unit is used to calculate the sum of the third predetermined value and the fourth predetermined value to obtain the upper limit of the second dead zone range; the second subtraction logic unit is used to calculate the difference between the third predetermined value and the fourth predetermined value to obtain the lower limit of the second dead zone range. The second high-value triggering logic unit is used to determine whether the coolant flow rate exceeds the upper limit of the second dead zone range, and the second low-value triggering logic unit is used to determine whether the coolant flow rate exceeds the lower limit of the second dead zone range. The second high-value triggering logic unit and the second low-value triggering logic unit generate trigger signals respectively. The second switching logic unit generates a second deviation signal based on the trigger signal. The PID controller generates a valve opening adjustment command for the bypass regulating valve of the primary reactor coolant system based on the second deviation signal.

10. A collaborative control device for a pressurized water reactor nuclear power plant, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that, When the processor executes the computer program, it implements the steps of the coordinated control method for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant as described in any one of claims 1-5.

11. A computer-readable storage medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, it implements the steps of the coordinated control method for the thermal parameters of the primary and secondary loops of a pressurized water reactor nuclear power plant as described in any one of claims 1-5.

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