Regulation rod control method and apparatus, electronic device, nuclear power plant system, and medium

Abstract

A regulation rod control method and apparatus, an electronic device, a nuclear power plant system, and a medium, relating to the technical field of nuclear power plant safety. The method comprises: in response to operating condition information of a nuclear power plant system being a load rejection condition, acquiring a target power of a reactor; determining a secondary loop load demand signal on the basis of the target power and an initial correction factor; on the basis of the secondary loop load demand signal and a first initial position of power regulation rods, controlling the power regulation rods to move; adjusting the initial correction factor on the basis of a second initial position of temperature regulation rods to obtain a target correction factor; on the basis of the target correction factor, the target power, a measured temperature of a primary loop subsystem, and a measured power of the reactor, controlling the temperature regulation rods to move to an intermediate position; and injecting demineralized water into the primary loop subsystem on the basis of the intermediate position and a preset safe position until the temperature regulation rods reach the safe position, thereby quickly improving the safety of the nuclear power plant under the load rejection condition.

Description

Control rod control methods and devices, electronic equipment, nuclear power plant systems and media Technical Field

[0001] This application relates to the field of nuclear power plant safety technology, and in particular to a regulating rod control method and device, electronic equipment, nuclear power plant system and medium. Background Technology

[0002] A load shedding transient condition refers to a situation where a nuclear power plant suddenly loses part or all of its electrical load during operation. This situation can lead to xenon poisoning. In this case, the reactor's reactivity can be controlled by adjusting the positions of the temperature and power control rods within the reactor core. During a load shedding transient condition, the power control rods are typically inserted into the reactor to reduce power. However, the rapid accumulation of xenon poisoning causes the temperature control rods to move out of their safe operating range.

[0003] In related technologies, strategies include continuous dilution of boric acid by injecting demineralized water into the primary loop of a nuclear power plant, or staged dilution. However, the former may lead to over-dilution, causing the temperature control rods to be positioned too low, while the latter is too time-consuming. Therefore, how to rapidly improve the safety of nuclear power plants under load shedding conditions has become an urgent technical problem to be solved. Summary of the Invention

[0004] The main objective of this application is to provide a regulating rod control method and device, electronic equipment, nuclear power plant system and medium, which aims to rapidly improve the safety of nuclear power plants under load shedding conditions.

[0005] To achieve the above objectives, a first aspect of this application proposes a regulating rod control method applied to a nuclear power plant system. The nuclear power plant system includes a power regulating rod, a temperature regulating rod, a primary loop subsystem, and a secondary loop subsystem. The primary loop subsystem includes a reactor, and the power regulating rod and the temperature regulating rod are respectively inserted into the reactor. The method includes:

[0006] Obtain the operating status information of the nuclear power plant system;

[0007] In response to the operating condition information being a load shedding condition, the target power of the reactor matching the load shedding condition is obtained;

[0008] The second-loop load demand signal of the second-loop subsystem is determined based on the target power and the preset initial correction factor.

[0009] Based on the secondary loop load demand signal and the first initial position of the power regulating rod in the reactor, the power regulating rod is controlled to move to adjust the reactor power to the target power;

[0010] The second initial position of the temperature regulating rod in the reactor is obtained, and the initial correction factor is numerically adjusted according to the second initial position to obtain the target correction factor;

[0011] Based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor, the temperature regulating rod is controlled to move to the middle position.

[0012] The target amount of demineralized water required to dilute boric acid is calculated based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem. The target amount of demineralized water is then injected into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position.

[0013] In some embodiments, controlling the movement of the power regulating rod based on the secondary loop load demand signal and the first initial position of the power regulating rod within the reactor to adjust the reactor power to the target power includes:

[0014] The target position of the power regulating rod within the reactor is determined based on the secondary loop load demand signal.

[0015] The position error is determined based on the current first initial position of the power regulating rod within the reactor and the target position;

[0016] A first rod position adjustment signal is generated based on the position error, and the power adjustment rod is moved according to the first rod position adjustment signal until the power adjustment rod reaches the target position, so as to adjust the power of the reactor to the target power.

[0017] In some embodiments, controlling the temperature regulating rod to move to the intermediate position based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor includes:

[0018] The second-loop load demand signal is corrected according to the target correction factor and the target power, and the target temperature of the first-loop subsystem is determined according to the corrected second-loop load demand signal.

[0019] Based on the measured temperature of the primary loop subsystem, the target temperature of the primary loop subsystem, the load demand signal of the secondary loop, and the measured power of the reactor, the temperature regulating rod is controlled to move to the intermediate position.

[0020] In some embodiments, the step of correcting the secondary loop load demand signal based on the target correction factor and the target power, and determining the target temperature of the primary loop subsystem based on the corrected secondary loop load demand signal, includes:

[0021] The intermediate load demand signal is obtained by superimposing the target power and the target correction factor.

[0022] The intermediate load demand signal is subjected to first-order filtering to obtain a candidate load demand signal, and the second-loop load demand signal is replaced with the candidate load demand signal.

[0023] The target temperature of the primary loop subsystem is determined based on the preset load-temperature mapping relationship and the corrected secondary loop load demand signal.

[0024] In some embodiments, controlling the temperature regulating rod to move to the intermediate position based on the measured temperature of the primary loop subsystem, the target temperature of the primary loop subsystem, the secondary loop load demand signal, and the measured power of the reactor includes:

[0025] Based on the load demand signal of the two-loop circuit and the measured power generated power deviation signal;

[0026] The power deviation signal is differentiated to obtain the power mismatch feedforward signal;

[0027] A temperature deviation signal is generated based on the measured temperature and the target temperature of the primary loop subsystem.

[0028] The temperature deviation signal and the power deviation signal are superimposed to obtain the second rod position adjustment signal;

[0029] The temperature regulating rod is moved according to the second rod position adjustment signal until it reaches the intermediate position.

[0030] In some embodiments, the step of calculating the target amount of demineralized water required to dilute the boric acid based on the middle position of the temperature regulating rod, a preset safe position, and a preset initial boric acid concentration of the primary loop subsystem, and injecting the target amount of demineralized water into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position, includes:

[0031] The target amount of demineralized water required to dilute boric acid is calculated based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem.

[0032] The target amount of demineralized water required to dilute boric acid with demineralized water is divided into multiple sub-water volumes;

[0033] According to the second preset time period, the demineralized water volume of each sub-water is injected into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem in stages until the temperature regulating rod reaches the safe position.

[0034] In some embodiments, the method further includes: calculating the target amount of demineralized water required to dilute boric acid with demineralized water based on the middle position of the temperature regulating rod, a preset safe position, and a preset initial boric acid concentration of the primary loop subsystem; injecting the target amount of demineralized water into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position;

[0035] Obtain a first preset position and a second preset position; wherein, the first preset position is the maximum value of the preset safety adjustment band of the temperature adjustment rod, and the second preset position is the minimum value of the preset safety adjustment band of the temperature adjustment rod;

[0036] Obtain the lowest position of the temperature regulating rod in the reactor;

[0037] The safe position is determined based on the first preset position, the second preset position, and the lower limit position, wherein the safe position is lower than the first preset position, higher than the second preset position, and higher than the lower limit position.

[0038] In some embodiments, obtaining a second initial position of the temperature regulating rod within the reactor, and numerically adjusting the initial correction factor based on the second initial position to obtain a target correction factor, includes:

[0039] The initial correction factor and the preset increment are integrated and calculated in the first preset time period to obtain the candidate correction factor;

[0040] If the second initial position remains unchanged or increases, then in the next first preset time period, the candidate correction factor and the preset increment are integrated and calculated to obtain an intermediate correction factor, and the intermediate correction factor replaces the candidate correction factor.

[0041] If the second initial position decreases, then the candidate correction factor is used as the target correction factor.

[0042] In some embodiments, the primary loop subsystem includes multiple thermal loops; before controlling the temperature regulating rod to move to the intermediate position based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor, the measured temperature of the primary loop subsystem is obtained through the following steps:

[0043] For each of the aforementioned thermal circuits, the inlet temperature and the outlet temperature of the thermal circuit are obtained.

[0044] The average temperature is calculated by averaging the inlet temperature and the outlet temperature.

[0045] The average temperature is filtered to obtain the measured temperature of the primary loop subsystem.

[0046] To achieve the above objectives, a second aspect of this application provides an electronic device, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the method described in the first aspect.

[0047] To achieve the above objectives, a third aspect of this application provides a nuclear power plant system, the nuclear power plant system comprising:

[0048] The electronic equipment described in the second aspect above;

[0049] The system includes a power regulating rod, a temperature regulating rod, a primary loop subsystem, and a secondary loop subsystem, wherein the primary loop subsystem includes a reactor.

[0050] To achieve the above objectives, a fourth aspect of the embodiments of this application provides an adjusting rod control device, the device comprising:

[0051] Operating condition information acquisition module, used to acquire operating condition information of the nuclear power plant system;

[0052] The target power acquisition module is used to acquire the target power of the reactor matching the load shedding condition in response to the operating condition information being a load shedding condition.

[0053] The load demand signal acquisition module is used to determine the second-loop load demand signal of the second-loop subsystem based on the target power and the preset initial correction factor.

[0054] The first rod position control module is used to control the movement of the power regulating rod according to the secondary loop load demand signal and the first initial position of the power regulating rod in the reactor, so as to adjust the power of the reactor to the target power.

[0055] The correction factor adjustment module is used to obtain the second initial position of the temperature regulating rod in the reactor, and to adjust the initial correction factor according to the second initial position to obtain the target correction factor;

[0056] The second rod position control module is used to control the temperature regulating rod to move to the middle position based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor.

[0057] The dilution adjustment module is used to calculate the target amount of demineralized water required to dilute boric acid based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem. The module then injects the target amount of demineralized water into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position.

[0058] To achieve the above objectives, a fifth aspect of the present application provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the method described in the first aspect.

[0059] The regulating rod control method, device, electronic equipment, nuclear power plant system, and medium proposed in this application first determine the operating conditions of the nuclear power plant system in real time, identify the target power corresponding to the load shedding condition, and use the target power and initial correction factor to determine the secondary loop load demand signal. Then, the rod position is precisely controlled by the secondary loop load demand signal and the initial position of the power regulating rod, ensuring that the reactor power is quickly adjusted to the expected level and avoiding potential safety risks caused by excessive or insufficient power. Next, the initial correction factor is adjusted to modify the secondary loop load demand, thereby adjusting the position of the temperature regulating rod. Because xenon poison accumulates rapidly under load shedding conditions, the temperature regulating rod may remain at the top of the reactor. Modifying the correction factor is simple and quick, and compared to existing technologies that directly dilute the poison, this embodiment can avoid the temperature regulating rod remaining at the top of the reactor for a long time. Then, combining the target correction factor, measured temperature, and measured power, the temperature regulating rod is moved to the intermediate position, and demineralized water is injected to dilute boric acid according to the intermediate position and a preset safety position, ensuring that the temperature regulating rod can smoothly reach the safety position. Compared to existing technologies that calculate the required volume of demineralized water by predicting the trend of xenon toxicity, this embodiment calculates the required volume of demineralized water based on rod position and boric acid concentration, resulting in a more accurate assessment. Therefore, this embodiment can rapidly improve the safety of nuclear power plants under load shedding conditions. Attached Figure Description

[0060] Figure 1 is a flowchart of the regulating rod control method provided in an embodiment of this application;

[0061] Figure 2 is a schematic diagram of a nuclear power plant system provided in an embodiment of this application;

[0062] Figure 3 is a flowchart of step S104 in Figure 1;

[0063] Figure 4 is a flowchart of step S105 in Figure 3;

[0064] Figure 5 is another flowchart of the regulating rod control method provided in an embodiment of this application;

[0065] Figure 6 is a flowchart of step S106 in Figure 1;

[0066] Figure 7 is a flowchart of step S601 in Figure 6;

[0067] Figure 8 is a flowchart of step S602 in Figure 6;

[0068] Figure 9 is a flowchart of step S107 in Figure 1;

[0069] Figure 10 is another flowchart of the regulating rod control method provided in an embodiment of this application;

[0070] Figure 11 is a graph showing the relationship between the position of an adjusting rod and time according to an embodiment of this application.

[0071] Figure 12 is a graph showing the relationship between a correction factor and time according to an embodiment of this application.

[0072] Figure 13 is a graph showing the relationship between dilution flow rate and time according to an embodiment of this application;

[0073] Figure 14 is a schematic diagram of the structure of the regulating rod control device provided in an embodiment of this application;

[0074] Figure 15 is a schematic diagram of the hardware structure of the electronic device provided in an embodiment of this application. Detailed Implementation

[0075] To make the objectives, technical solutions, and advantages of this application clearer, the following detailed description is provided in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the scope of this application.

[0076] It should be noted that although functional modules are divided in the device schematic diagram and a logical order is shown in the flowchart, in some cases, the steps shown or described may be performed in a different order than the module division in the device or the order in the flowchart. The terms "first," "second," etc., in the specification, claims, and the aforementioned drawings are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence.

[0077] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs. The terminology used herein is for the purpose of describing embodiments of this application only and is not intended to limit this application.

[0078] First, let's analyze some of the terms used in this application:

[0079] Pressurized water reactor (PWR) nuclear power plants mainly consist of a nuclear steam supply system (primary loop), a turbine generator system (secondary loop), and other auxiliary systems. Their working principle is as follows: The main pump delivers high-pressure coolant into the reactor. In the reactor, the coolant absorbs the heat released from nuclear fuel fission and then transfers this heat to the secondary loop via a steam generator to produce steam. This steam then enters the turbine to perform work, driving the generator to produce electricity. The exhaust steam condenses into water in the condenser, and the condensate feedwater is pumped to the heater, reheated, and then returned to the steam generator. This is the secondary loop system.

[0080] Load shedding condition: In the embodiments of this application, the load shedding condition of a nuclear power plant usually refers to the condition in which a nuclear power plant or other power plant suddenly loses part or all of its power load during operation.

[0081] Xenon poisoning: Xenon (135Xe) is the most potent known neutron absorber. It acts like a "poison," slowing or stopping chain reactions. Reactors operating at constant power for extended periods maintain a stable steady-state xenon concentration. However, when reactor power is reduced, the xenon concentration can increase to a level sufficient to shut down the reactor. In this state, the reactor cannot be restarted. This shutdown caused by high xenon concentration, making restarting difficult, is called xenon poisoning. The reactivity deficit caused by the equilibrium xenon concentration is called equilibrium xenon poisoning.

[0082] Load shedding transient conditions refer to situations where a nuclear power plant suddenly loses part or all of its electrical load during operation. This situation can lead to xenon poisoning. In such cases, the reactivity of the reactor can be controlled by adjusting the positions of temperature and power control rods within the reactor core. Both temperature and power control rods are made of absorbent materials (such as boron and cadmium), which absorb neutrons in the reactor, thereby regulating the rate of nuclear fission reactions and ultimately adjusting the reactor's power and temperature. The deeper the rods are inserted into the core, the more neutrons are absorbed. A decrease in the number of neutrons reduces the reaction rate, and consequently, the reactor's power and temperature decrease.

[0083] During load shedding transients, the power regulating rods are typically inserted into the reactor to reduce power. The rapid accumulation of xenon toxicity causes the regulating rods to move out of the safe operating range. Related technologies employ a strategy of continuously diluting or periodically diluting boric acid by injecting demineralized water into the primary coolant loop of the nuclear power plant to compensate for the negative reactivity introduced by xenon toxicity and achieve xenon toxicity balance. Boric acid (H3BO3) is a neutron absorber commonly used in reactor coolants. It absorbs neutrons, thereby regulating reactor reactivity. The higher the concentration of boric acid, the more neutrons are absorbed, and the lower the reactor reactivity. Boric acid is diluted by injecting demineralized water into the primary coolant loop to reduce its concentration. Demineralized water does not contain neutron-absorbing substances and does not absorb additional neutrons. When the boric acid concentration decreases, the total amount of neutrons absorbed decreases, allowing more neutrons to participate in nuclear fission reactions, thereby improving reactor reactivity.

[0084] Specifically, the trend of xenon toxicity during the load shedding transient is predicted based on the core operating status. Then, the negative reactivity introduced by xenon toxicity is calculated, followed by the total volume of demineralized water needed to balance this negative reactivity. One existing approach involves continuously diluting the demineralized water by injecting the total volume into the coolant at once, observing the position of the temperature regulating rod to a preset adjustment zone. Since the reactivity introduced by dilution typically takes 3 to 5 minutes to determine its effect, there is a significant hysteresis effect. Furthermore, the inability to accurately predict core xenon toxicity leads to certain deviations in the dilution calculation. Therefore, this approach easily results in over-dilution, causing the temperature regulating rod to be inserted below the lower limit, triggering the Limiting Condition of Operation (LCO) event specified in the technical specifications, thus compromising the safety of the nuclear power plant.

[0085] Another approach is to inject the demineralized water in stages, waiting 3 to 5 minutes after each injection to observe whether the temperature regulating rods return to the preset regulating zone. While this approach can prevent excessive dilution, it significantly increases the time required, and keeping the temperature regulating rods on top of the reactor for too long is also detrimental to the safety of the nuclear power plant.

[0086] Therefore, how to rapidly improve the safety of nuclear power plants under load shedding conditions has become an urgent technical problem to be solved.

[0087] Based on this, embodiments of this application provide a regulating rod control method and apparatus, electronic equipment, nuclear power plant system and medium, aiming to rapidly improve the safety of nuclear power plants under load shedding conditions.

[0088] The methods, apparatus, electronic devices, and storage media provided in the embodiments of this application are specifically described through the following embodiments. First, the methods in the embodiments of this application are described.

[0089] The regulating rod control method provided in this application relates to the field of nuclear power plant safety technology. The regulating rod control method provided in this application can be applied to a terminal, a server, or software running on either a terminal or a server. In some embodiments, the terminal can be a smartphone, tablet, laptop, desktop computer, etc.; the server can be configured as an independent physical server, a server cluster or distributed system composed of multiple physical servers, or a cloud server providing basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communication, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application implementing the regulating rod control method, but is not limited to the above forms.

[0090] This application can be used in a wide variety of general-purpose or special-purpose computer system environments or configurations. Examples include: personal computers, server computers, handheld or portable devices, tablet devices, multiprocessor systems, microprocessor-based systems, set-top boxes, programmable consumer electronics, network PCs, minicomputers, mainframe computers, and distributed computing environments including any of the above systems or devices. This application can be described in the general context of computer-executable instructions executed by a computer, such as program modules. Generally, program modules include routines, programs, objects, components, data structures, etc., that perform specific tasks or implement specific abstract data types. This application can also be practiced in distributed computing environments where tasks are performed by remote processing devices connected via a communication network. In distributed computing environments, program modules can reside in local and remote computer storage media, including storage devices.

[0091] Figure 1 is an optional flowchart of the regulating rod control method provided in the embodiment of this application. The method in Figure 1 is applied to a nuclear power plant system and may include, but is not limited to, steps S101 to S107.

[0092] Step S101: Obtain the operating status information of the nuclear power plant system.

[0093] Step S102: In response to the operating condition information being a load shedding condition, obtain the target power of the reactor that matches the load shedding condition.

[0094] Step S103: Determine the second-loop load demand signal of the second-loop subsystem based on the target power and the preset initial correction factor.

[0095] Step S104: Based on the secondary loop load demand signal and the first initial position of the power regulating rod in the reactor, control the movement of the power regulating rod to adjust the reactor power to the target power.

[0096] Step S105: Obtain the second initial position of the temperature regulating rod in the reactor, and adjust the initial correction factor according to the second initial position to obtain the target correction factor.

[0097] Step S106: Based on the target correction factor, target power, measured temperature of the primary loop subsystem, and measured power of the reactor, control the temperature regulating rod to move to the middle position.

[0098] Step S107: Calculate the target amount of demineralized water required to dilute the boric acid based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem. Inject the target amount of demineralized water into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position.

[0099] Steps S101 to S107 of this embodiment first determine the operating conditions of the nuclear power plant system in real time, identify the target power corresponding to the load shedding condition, and use the target power and initial correction factor to determine the secondary loop load demand signal. Then, the position of the temperature regulating rod is precisely controlled by the secondary loop load demand signal and the initial position of the temperature regulating rod to ensure that the reactor power is quickly adjusted to the expected level, avoiding potential safety risks caused by excessive or insufficient power. Next, the initial correction factor is adjusted to modify the secondary loop load demand, thereby adjusting the position of the temperature regulating rod. Because xenon poison accumulates rapidly under the load shedding condition, the temperature regulating rod may remain at the top of the reactor. Modifying the correction factor is simple and quick, and compared with the prior art of direct dilution, this embodiment can avoid the temperature regulating rod remaining at the top of the reactor for a long time. Then, combining the target correction factor, measured temperature, and measured power, the temperature regulating rod is moved to the intermediate position, and demineralized water is injected to dilute boric acid according to the intermediate position and the preset safety position to ensure that the temperature regulating rod can smoothly reach the safety position. Compared to existing technologies that calculate the required volume of demineralized water by predicting the trend of xenon toxicity, this embodiment calculates the required volume of demineralized water based on rod position and boric acid concentration, resulting in a more accurate assessment. Therefore, this embodiment can rapidly improve the safety of nuclear power plants under load shedding conditions.

[0100] It should be noted that the regulating rod control method provided in this application embodiment needs to be implemented based on a nuclear power plant system. Therefore, the nuclear power plant system provided in this application embodiment will be introduced first. Please refer to Figure 2, which is a structural schematic diagram of the nuclear power plant system provided in this application embodiment. The nuclear power plant system provided in this application embodiment can be a pressurized water reactor nuclear power plant using a reactor-following mode, including power regulating rods, temperature regulating rods, a primary loop subsystem and a secondary loop subsystem, as well as an electronic device provided in this application embodiment. This electronic device will be described in detail in subsequent related embodiments.

[0101] In the nuclear power plant system provided in this application embodiment, the primary loop subsystem includes a reactor, and the regulating rod assembly includes temperature regulating rods and power regulating rods, which are inserted into the reactor. The reactor's function is to perform nuclear fission, converting nuclear energy into the thermal energy of the coolant. The coolant, in liquid form, absorbs the thermal energy generated by nuclear fission in the reactor, becoming a high-temperature, high-pressure liquid. It then flows through pipes into the U-tube of the steam generator, transferring heat to the water outside the U-tube and turning it into saturated steam. The cooled coolant is then pumped back into the reactor by the main pump for reheating, thus forming a closed heat absorption and release cycle. This cycle is the primary loop subsystem, also known as the nuclear steam supply system.

[0102] Steam generated by the steam generator enters the steam turbine, expands, and performs work, converting thermal energy into mechanical energy from the rotation of the turbine rotor. The turbine rotor and generator rotor are rigidly connected on their two shafts, so the turbine directly drives the generator to generate electricity, converting mechanical energy into electrical energy. After performing its work, the steam is discharged into the condenser, where it is cooled by circulating cooling water (such as seawater). The steam is condensed into water, which is then pumped back into the steam generator by the feedwater pump. This loop is a secondary loop subsystem.

[0103] In step S101 of some embodiments, the operating condition information of the nuclear power plant can be either a load shedding condition or a normal operating condition. When a turbine trips, experiences no-load shedding, or sheds plant power, the nuclear power plant can be in a load shedding condition. When the nuclear power plant operates normally as expected, such as with stable reactor power and temperature, balanced xenon concentration, and normal water pump operation, it can be determined that the nuclear power plant is in a normal operating condition.

[0104] In step S102 of some embodiments, in response to the operating condition information indicating a load shedding condition, the target power of the reactor matching the load shedding condition is obtained. This target power refers to the power value that the reactor is expected to achieve. It should be noted that in some embodiments, when the nuclear power plant is in normal operating condition, the final power setting value of the nuclear power plant system is 0. When the nuclear power plant is in a load shedding condition, this final power setting value is set to be greater than the turbine load power; at this time, the final power setting value is the aforementioned target power. This is because when the nuclear power plant is in a load shedding condition, the turbine bypass system starts operating, bypassing the turbine with high-temperature, high-pressure steam and directly introducing it into the condenser or other cooling devices, thereby preventing steam from entering the turbine system. If the total load of the secondary loop system is determined based on the turbine inlet steam pressure signal at this time, it will cause a deviation between the load data and the actual total load of the secondary loop system. Therefore, setting a power setting value greater than the turbine load allows the reactor to generate a power greater than the turbine load, enabling rapid tracking when the turbine load increases, thereby improving the system's dynamic response capability.

[0105] In step S103 of some embodiments, it can be understood that the maximum value of the final power setting value and the turbine load is selected as the basis for generating the secondary loop load demand signal. When the operating condition information is a load shedding condition, the final power setting value is greater than the turbine load, and is used as the target power in this embodiment. It is then superimposed with a preset initial correction factor, and the secondary loop load demand signal of the secondary loop subsystem is determined based on the superimposed result.

[0106] In other embodiments, when the operating condition information is normal operating condition, the final power setting value is 0. The turbine load reference value is obtained by selecting the maximum value, and then filtered and superimposed with a correction factor to obtain the secondary loop load demand signal of the secondary loop subsystem.

[0107] Understandably, the correction factor can be set manually.

[0108] In some embodiments, step S104, referring to FIG3, may include, but is not limited to, steps S301 to S303:

[0109] Step S301: Determine the target position of the power regulating rod within the reactor based on the secondary loop load demand signal.

[0110] Step S302: Determine the position error based on the current initial position and target position of the power regulating rod within the reactor.

[0111] Step S303: Generate a first rod position adjustment signal based on the position error, and control the movement of the power adjustment rod according to the first rod position adjustment signal until the power adjustment rod reaches the target position, so as to adjust the reactor power to the target power.

[0112] In step S301 of some embodiments, the secondary loop load demand signal can be calculated using a preset interpolation function to obtain the expected position of the power regulating rod within the reactor, i.e., the target position. In the embodiments of this application, the position of the regulating rod is usually represented by a number of steps, for example, the target position is 350.

[0113] In step S302 of some embodiments, the position of the power regulating rod in the reactor at the current moment is obtained, and the difference between the current position and the target position is calculated. The difference obtained is the position error.

[0114] In step S303 of some embodiments, the first rod position adjustment signal is a control command that indicates how the power regulating rod should move to eliminate errors. It may include an insertion / removal signal and a movement speed signal. It is understood that the insertion / removal signal is determined based on the sign of the position error, thus determining whether the power regulating rod needs to be inserted or removed. The expected speed of the regulating rod can be directly obtained from the position error through an interpolation function, thereby determining the movement speed. The first rod position adjustment signal controls the motor or control rod drive mechanism (CRDM) of the power regulating rod, causing the rod position to move gradually until the actual position of the power regulating rod matches the target position, meaning the position error is 0, and indicating that the reactor power at this point is the target power.

[0115] Steps S301 to S303, as illustrated in the embodiments of this application, automate power regulation, improve the accuracy and real-time response capability of power regulation, and reduce manual intervention and operational errors. Furthermore, they effectively avoid load fluctuations and system instability caused by power output lag or inaccuracy, thereby enhancing the stability and reliability of the nuclear reactor.

[0116] It should be noted that during the control process of the power regulating rod, due to the rapid accumulation of xenon poison, the temperature regulating rod will gradually rise to the top of the reactor. After the power regulating rod can stabilize at the target position, the initial correction factor will be adjusted.

[0117] In step S105 of some embodiments, after controlling the power regulating rod, the position of the temperature regulating rod is obtained as the second initial position. Referring to Figure 4, in some embodiments, step S105 may include, but is not limited to, steps S401 to S403:

[0118] Step S401: In the first preset time period, the initial correction factor and the preset increment are integrated and calculated to obtain the candidate correction factor.

[0119] In step S402, if the second initial position remains unchanged or increases, the candidate correction factor and the preset increment are integrated and calculated in the next first preset time period to obtain the intermediate correction factor, and the intermediate correction factor replaces the candidate correction factor.

[0120] Step S403: If the second initial position decreases, the candidate correction factor is used as the target correction factor.

[0121] In step S401 of some embodiments, the first preset time period is a time period used to adjust the initial correction factor, which can be 30 seconds. The preset increment is the amount of adjustment to the initial correction factor each time, which can be 20 megawatts. The specific values ​​of the first preset time period and the preset increment can be adjusted according to the actual nuclear power project, and the embodiments of this application do not strictly limit this. The candidate correction factor is the adjusted initial correction factor, which is calculated by adding the initial correction factor to the preset increment. It should be noted that adding the initial correction factor will cause the power regulating rod to rise. In order to prevent the position of the power regulating rod from deviating too much, the adjustment of the correction factor is stopped once the temperature regulating rod begins to fall.

[0122] In step S402 of some embodiments, if the second initial position remains unchanged or increases, the candidate correction factors are continued to be superimposed, and the result is the intermediate correction factor. For example, the initial correction factor is 0, the first preset time period is 30 seconds, and the preset increment is 20 megawatts (MW). At 30 seconds, the candidate correction factor is 20 MW, and the temperature regulating rod does not decrease. At 1 minute, the preset increment is continued to be superimposed on the candidate correction factor, resulting in an intermediate correction factor of 40 MW, which is then used as the new candidate correction factor.

[0123] In step S403 of some embodiments, if the temperature regulating rod begins to descend, the candidate correction factor at this time is used as the target correction factor. In short, the correction factor is increased by a preset amount every first preset time period until the temperature regulating rod begins to descend.

[0124] Steps S401 to S403, as illustrated in this embodiment, determine the degree of adjustment to the initial correction factor by observing the positional changes of the temperature regulating rod. This ensures that the most suitable correction factor can be locked in a timely manner during operation, avoiding system instability caused by over- or under-adjustment, and improving the operating efficiency and safety of the nuclear power plant. The method for modifying the correction factor is simple and quick; each adjustment only requires a 30-second wait before the effect on the position of the temperature regulating rod becomes apparent. Compared to existing technologies, this avoids the temperature regulating rod remaining at the reactor top for too long.

[0125] Please refer to Figure 5. In some embodiments, prior to step S106, the primary loop subsystem includes multiple thermal loops for the flow of coolant. The method provided in this application embodiment also includes, but is not limited to, steps S501 to S503:

[0126] Step S501: For each thermal circuit, obtain the inlet temperature and outlet temperature of the thermal circuit.

[0127] Step S502: Calculate the average temperature by averaging the inlet and outlet temperatures.

[0128] Step S503: Filter the average temperature to obtain the measured temperature of the primary loop subsystem.

[0129] In step S501 of some embodiments, the inlet temperature of the thermal circuit is the temperature at which the coolant enters the reactor core, and the outlet temperature of the thermal circuit is the temperature at which the coolant flows out of the reactor core.

[0130] In step S502 of some embodiments, an average temperature is obtained by calculating the average value based on the inlet temperature and the outlet temperature. Since the primary loop subsystem may have multiple parallel thermal loops, there will be multiple average temperatures.

[0131] In step S503 of some embodiments, the highest temperature among multiple average temperatures is the measured temperature in this embodiment. In some embodiments, the signal containing the highest temperature value information is further subjected to first-order filtering and lead / lag processing, and the processing result is transmitted as a signal containing the measured temperature.

[0132] Steps S501 to S503 as shown in the embodiments of this application, by selecting the highest value among multiple average temperatures as the measured temperature of the primary loop subsystem, can effectively capture the hottest area in the reactor, providing reliable data for subsequent reactor temperature regulation, and ensuring the safe operation of the reactor.

[0133] Please refer to Figure 6. In some embodiments, step S106 may also include, but is not limited to, steps S601 to S602:

[0134] Step S601: Correct the secondary loop load demand signal according to the target correction factor and the target power, and determine the target temperature of the primary loop subsystem according to the corrected secondary loop load demand signal.

[0135] Step S602: Based on the measured temperature of the primary loop subsystem, the target temperature of the primary loop subsystem, the secondary loop load demand signal, and the measured power of the reactor, control the temperature regulating rod to move to the middle position.

[0136] In some embodiments, step S601, as shown in FIG7, includes, but is not limited to, steps S701 to S703:

[0137] Step S701: The intermediate load demand signal is obtained by superimposing the target power and the target correction factor.

[0138] Step S702: Perform first-order filtering on the intermediate load demand signal to obtain the candidate load demand signal, and replace the second-loop load demand signal with the candidate load demand signal.

[0139] Step S703: Determine the target temperature of the primary loop subsystem based on the preset load temperature mapping relationship and the corrected secondary loop load demand signal.

[0140] In step S701 of some embodiments, the target power and the target correction factor are superimposed to obtain the intermediate load demand signal.

[0141] In step S702 of some embodiments, the intermediate load demand signal may contain some unnecessary high-frequency components or noise, which may cause the system to be overly sensitive to signal changes, resulting in unstable or overly drastic power adjustment. First-order filtering smooths the intermediate load demand signal, removes high-frequency noise, and makes the processed candidate load demand signal more stable, which is then used as the new second-loop load demand signal.

[0142] In step S703 of some embodiments, the preset load-temperature mapping relationship can be represented by a pre-determined interpolation function. The target temperature is the expected temperature corresponding to the reactor and secondary loop load demand signals. Substituting the secondary loop load demand signal into the interpolation function yields the target temperature of the corresponding primary loop subsystem.

[0143] Steps S701 to S703, as illustrated in the embodiments of this application, combine power demand with temperature regulation. This allows the system to maintain reactor temperature stability while meeting grid load requirements, ensuring the safe and efficient operation of the entire nuclear power plant. The technical effect of this series of steps is to ensure that the system can precisely control power and temperature under complex operating conditions, while optimizing responsiveness and safety.

[0144] In some embodiments, step S602, referring to FIG8, may include, but is not limited to, steps S801 to S805:

[0145] Step S801: Generate a power deviation signal based on the load demand signal of the second loop and the measured power.

[0146] Step S802: Differentiate the power deviation signal to obtain the power mismatch feedforward signal.

[0147] Step S803: Generate a power deviation signal based on the load demand signal of the second loop and the measured power.

[0148] Step S804: The temperature deviation signal and the power deviation signal are superimposed to obtain the second rod position adjustment signal.

[0149] Step S805: Control the temperature regulating rod to move according to the second rod position adjustment signal until the temperature regulating rod moves to the middle position.

[0150] In step S801 of some embodiments, the measured power is the power of the reactor. The difference between the secondary loop load demand signal and the measured power is calculated, and the difference is the power deviation. The signal reflecting the power deviation information is the power deviation signal.

[0151] In step S802 of some embodiments, the power deviation signal is processed by inertial differentiation to obtain a power mismatch feedforward signal. Power mismatch refers to a deviation between the measured power and the load demand. The power mismatch feedforward signal reflects the dynamic rate of change of power mismatch, allowing for early prediction of future power demand changes and corresponding system adjustments, thus significantly reducing hysteresis.

[0152] In step S803 of some embodiments, the difference between the measured temperature and the target temperature is calculated, and the difference is the temperature deviation. The signal reflecting the temperature deviation is the temperature deviation signal.

[0153] In step S804 of some embodiments, the second rod position adjustment signal is used to indicate how the temperature adjustment rod should move to eliminate temperature deviation, and it may include an insertion / removal signal and a movement speed signal.

[0154] In step S805 of some embodiments, it is understood that the expected speed of the temperature regulating rod can be directly obtained from the temperature deviation and power mismatch feedforward signal through a pre-determined interpolation function, thereby determining the movement speed.

[0155] Understandably, the adjusted correction factor alters the secondary loop load demand signal, thus affecting the position of the temperature control rod. When the target correction factor is obtained, the temperature control rod begins its descent from the top of the reactor; its position after stabilization is the intermediate position.

[0156] Steps S801 to S805, as shown in the embodiments of this application, combine multidimensional signal processing with feedback control to achieve efficient and precise control of the temperature regulating rods in nuclear power plants.

[0157] Steps S601 to S602, as illustrated in the embodiments of this application, coordinate the dual feedback signals of power and temperature to ensure that the nuclear reactor can meet load requirements while ensuring that its temperature regulation function can respond quickly.

[0158] In some embodiments, step S107, referring to FIG9, may include, but is not limited to, steps S901 to S903:

[0159] Step S901: Calculate the target amount of demineralized water required to dilute boric acid with demineralized water based on the middle position of the temperature regulating rod, the preset safety position, and the preset initial boric acid concentration of the primary loop subsystem.

[0160] Step S902: Divide the target amount of demineralized water required to dilute boric acid into multiple sub-water volumes.

[0161] Step S903: According to the second preset time period, the demineralized water volume of each sub-water is injected into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem in stages until the temperature regulating rod reaches the safe position.

[0162] In step S901 of some embodiments, the coolant in the primary loop subsystem includes a certain concentration of boric acid. Diluting the boric acid concentration can improve the reactor's reactivity, thereby balancing xenon toxicity. The boric acid concentration before the dilution operation is the preset initial boric acid concentration. At this time, the volume of demineralized water required for the temperature control rod to move from the intermediate position to the safe position is calculated. Specifically, the amount of reactivity change caused by the temperature control rod moving from the intermediate position to the safe position is determined. The reactivity change caused by the xenon toxicity change during this process should also be considered. Then, the amount of change in boric acid concentration is determined based on the amount of reactivity change. Finally, the target amount of demineralized water, which is the volume of demineralized water required for the dilution operation, is calculated based on the amount of change in boric acid concentration, the initial boric acid concentration, and the total volume of coolant in the primary loop.

[0163] In step S902 of some embodiments, the demineralized water is then diluted in stages. This can be done by dividing the required dilution amount into equal portions or by splitting it into different data volumes, such that the amount diluted in the earlier stages is greater than the amount diluted in the later stages. The data obtained after splitting the required dilution amount is the sub-water volume. In this embodiment, the required dilution amount is divided into four equal parts to obtain the sub-water volume.

[0164] In step S903 of some embodiments, the second preset time period is the time period for waiting for the position of the temperature regulating rod to become apparent, and its duration can be 3 to 5 minutes. This embodiment does not strictly limit this. Every second preset time period, demineralized water with a volume equal to that of the sub-water is injected into the primary loop subsystem to gradually control the temperature regulating rod to a safe position.

[0165] Steps S901 to S903, as illustrated in the embodiments of this application, achieve precise adjustment of the position of the temperature regulating rod and the reactor reactivity through accurate volume calculation, phased injection, and time control, ensuring the safe and efficient operation of the nuclear power plant under load changes and xenon toxicity effects.

[0166] In some embodiments, referring to FIG10, before step S106, the adjusting rod control method provided in this application embodiment can also obtain a safe position through steps S1001 to S1003:

[0167] Step S1001: Obtain the first preset position and the second preset position.

[0168] Step S1002: Obtain the low-low limit position of the temperature regulating rod in the reactor.

[0169] Step S1003: Determine the safe position based on the first preset position, the second preset position, and the lower limit position.

[0170] In step S1001 of some embodiments, the first preset position is the maximum value of the preset safety adjustment range of the temperature regulating rod, and the second preset position is the minimum value of the preset safety adjustment range of the temperature regulating rod. The range of temperature regulating rod positions that can ensure safe operation in the reactor of this nuclear power plant is the preset safety adjustment range. This range can be designed according to different nuclear power plants, and this embodiment does not strictly limit its specific data.

[0171] In step S1002 of some embodiments, the low-low limit position refers to the position of the regulating rod in the nuclear power plant, which describes its operating position, falling below the minimum permissible limit for operation. It is understood that if the regulating rod position reaches the minimum permissible limit, it will trigger an LCO (Low-Cost Operation) event, thereby affecting the safety of the nuclear power plant.

[0172] In step S1003 of some embodiments, it can be understood that the safe position is lower than the first preset position, higher than the second preset position, and higher than the lower limit position. The safe position is the position that the temperature regulating rod is expected to reach, and is usually the midpoint between the first preset position and the second preset position.

[0173] Steps S1001 to S1003, as illustrated in the embodiments of this application, accurately determine the safe position of the temperature regulating rod, thereby improving the operational safety and control precision of the nuclear power plant reactor.

[0174] The following specific embodiments will describe the regulating rod control method under load shedding conditions. Please refer to Figures 11, 12, and 13. Figure 11 is a graph showing the relationship between the regulating rod position and time; Figure 12 is a graph showing the relationship between the correction factor and time; and Figure 13 is a graph showing the relationship between the dilution flow rate and time. The time axes of Figures 11, 12, and 13 correspond. In Figure 11, the lower black line reflects the actual position of the temperature regulating rod (R rod), the middle black line reflects the actual position of the power regulating rod (G rod), and the upper gray line reflects the required position of the power regulating rod (G rod).

[0175] For example, when the turbine of a nuclear power plant's 100% full power (FP) platform trips, the plant's operating condition abruptly changes to a load shedding condition. In response to this load shedding condition, a final power setpoint of 30% FP, i.e., the target power, is generated. The target position of the G rod abruptly changes from step 615 to step 350, controlling the G rod to gradually insert into the core until the target position is reached. Simultaneously with the load shedding condition, the primary loop system overheats in the initial stage of the load shedding transient, causing the measured temperature to exceed the temperature reference value, resulting in a temperature deviation. Additionally, a sudden load drop in the secondary loop subsystem causes a power mismatch feedforward signal to be output. The combined effect of these two factors creates a large negative composite temperature deviation signal, causing the R rod to insert into the core from step 197 to step 115. During the period AC in which the G rod is gradually inserted into the reactor core, the primary loop power gradually decreases as the G rod is inserted, the power mismatch feedforward signal changes from positive to negative, and the overall temperature deviation changes from negative to positive. The R rod gradually rises during period AB, eventually reaching the top position at 225 steps. At this point, due to the drastic change in core power and the gradual accumulation of xenon poison, the primary loop exhibits a supercooling trend, and the R rod remains at the top for an extended period. After the G rod reaches the target position, a period of waiting is observed. During period CD, the position of the G rod is confirmed to be stable, and the correction factor is gradually increased hourly. Figure 12 illustrates the relationship between the value of the correction factor and time. The initial correction factor is 0, accumulating 20 MW every time period, with each increase causing the G rod to rise by 5 steps. When the correction factor reaches 60 MW, the G rod rises to 365 steps, and the R rod begins to decrease from 225 steps, reaching 210 steps at time E. After waiting 1 to 2 minutes (period EF) to observe the stability of the R rod position, the intermediate position of the R rod can be determined to be 210 steps. Starting at time F, the primary loop is diluted in stages, with a dilution flow rate set at 25 cubic meters per hour. After the first dilution is completed, the R-bar descends and waits for it to stabilize (time G), confirming its position at step 198. A second dilution operation is then performed, with the R-bar descending to step 186. If the R-bar has not yet reached the expected position, dilution continues until the R-bar returns to the center of the regulating band.

[0176] Please refer to Figure 14. This application embodiment also provides an adjusting rod control device that can implement the above-described adjusting rod control method. The device includes:

[0177] Operating condition information acquisition module, used to acquire operating condition information of nuclear power plant system;

[0178] The target power acquisition module is used to acquire the target power of the reactor that matches the load shedding condition in response to the operating condition information being a load shedding condition.

[0179] The load demand signal acquisition module is used to determine the second-loop load demand signal of the second-loop subsystem based on the target power and the preset initial correction factor.

[0180] The first rod position control module is used to control the movement of the power regulating rod according to the secondary loop load demand signal and the first initial position of the power regulating rod in the reactor, so as to adjust the reactor power to the target power.

[0181] The correction factor adjustment module is used to obtain the second initial position of the temperature regulating rod in the reactor, and to adjust the initial correction factor according to the second initial position to obtain the target correction factor.

[0182] The second rod position control module is used to control the temperature regulating rod to move to the middle position based on the target correction factor, target power, measured temperature of the primary loop subsystem, and measured power of the reactor.

[0183] The dilution adjustment module is used to calculate the target amount of demineralized water required to dilute boric acid based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem. The target amount of demineralized water is injected into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position.

[0184] The specific implementation of the regulating rod control device is basically the same as the specific embodiment of the regulating rod control method described above, and will not be repeated here.

[0185] This application also provides an electronic device, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the above-described lever control method. This electronic device can be any smart terminal, including tablet computers, in-vehicle computers, etc.

[0186] Please refer to Figure 15, which illustrates the hardware structure of an electronic device according to another embodiment. The electronic device includes:

[0187] The processor 1501 can be implemented using a general-purpose CPU (Central Processing Unit), microprocessor, application-specific integrated circuit (ASIC), or one or more integrated circuits, and is used to execute relevant programs to implement the technical solutions provided in the embodiments of this application.

[0188] The memory 1502 can be implemented as a read-only memory (ROM), static storage device, dynamic storage device, or random access memory (RAM). The memory 1502 can store the operating system and other application programs. When the technical solutions provided in the embodiments of this specification are implemented through software or firmware, the relevant program code is stored in the memory 1502 and is called and executed by the processor 1501 to execute the adjustment rod control method of the embodiments of this application.

[0189] The input / output interface 1503 is used to implement information input and output;

[0190] The communication interface 1504 is used to enable communication and interaction between this device and other devices. Communication can be achieved through wired means (such as USB, Ethernet cable, etc.) or wireless means (such as mobile network, WIFI, Bluetooth, etc.).

[0191] Bus 1505 transmits information between various components of the device (e.g., processor 1501, memory 1502, input / output interface 1503, and communication interface 1504);

[0192] The processor 1501, memory 1502, input / output interface 1503 and communication interface 1504 are connected to each other within the device via bus 1505.

[0193] This application also provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the above-described regulating rod control method.

[0194] Memory, as a non-transitory computer-readable storage medium, can be used to store non-transitory software programs and non-transitory computer-executable programs. Furthermore, memory may include high-speed random access memory, and may also include non-transitory memory, such as at least one disk storage device, flash memory device, or other non-transitory solid-state storage device. In some embodiments, memory may optionally include memory remotely located relative to the processor, and these remote memories can be connected to the processor via a network. Examples of such networks include, but are not limited to, the Internet, intranets, local area networks, mobile communication networks, and combinations thereof.

[0195] The regulating rod control method, regulating rod control device, electronic equipment, and storage medium provided in this application first determine the operating conditions of the nuclear power plant system in real time, identify the target power corresponding to the load shedding condition, and use the target power and initial correction factor to determine the secondary loop load demand signal. Then, the rod position is precisely controlled by the secondary loop load demand signal and the initial position of the power regulating rod to ensure that the reactor power is quickly adjusted to the expected level, avoiding potential safety risks caused by excessive or insufficient power. Next, the initial correction factor is adjusted to modify the secondary loop load demand, thereby adjusting the position of the temperature regulating rod. Because xenon poison accumulates rapidly under load shedding conditions, the temperature regulating rod may remain at the top of the reactor. Modifying the correction factor is simple and quick, and compared to existing technologies that directly dilute the poison, this embodiment can avoid the temperature regulating rod remaining at the top of the reactor for a long time. Then, combining the target correction factor, measured temperature, and measured power, the temperature regulating rod is moved to the intermediate position, and demineralized water is injected to dilute boric acid according to the intermediate position and a preset safety position, ensuring that the temperature regulating rod can smoothly reach the safety position. Compared to existing technologies that calculate the required volume of demineralized water by predicting the trend of xenon toxicity, this embodiment calculates the required volume of demineralized water based on rod position and boric acid concentration, resulting in a more accurate assessment. Therefore, this embodiment can rapidly improve the safety of nuclear power plants under load shedding conditions.

[0196] The embodiments described in this application are for the purpose of more clearly illustrating the technical solutions of the embodiments of this application, and do not constitute a limitation on the technical solutions provided by the embodiments of this application. As those skilled in the art will know, with the evolution of technology and the emergence of new application scenarios, the technical solutions provided by the embodiments of this application are also applicable to similar technical problems.

[0197] Those skilled in the art will understand that the technical solutions shown in the figures do not constitute a limitation on the embodiments of this application, and may include more or fewer steps than shown, or combine certain steps, or different steps.

[0198] The device embodiments described above are merely illustrative. The units described as separate components may or may not be physically separate; that is, they may be located in one place or distributed across multiple network units. Some or all of the modules can be selected to achieve the purpose of this embodiment according to actual needs.

[0199] Those skilled in the art will understand that all or some of the steps in the methods disclosed above, as well as the functional modules / units in the systems and devices, can be implemented as software, firmware, hardware, or suitable combinations thereof.

[0200] The terms “first,” “second,” “third,” “fourth,” etc. (if present) in the specification and accompanying drawings of this application are used to distinguish similar objects and are not necessarily used to describe a specific order or sequence. It should be understood that such data can be interchanged where appropriate so that the embodiments of this application described herein can be implemented in orders other than those illustrated or described herein. Furthermore, the terms “comprising” and “having,” and any variations thereof, are intended to cover non-exclusive inclusion; for example, a process, method, system, product, or apparatus that comprises a series of steps or units is not necessarily limited to those steps or units explicitly listed, but may include other steps or units not explicitly listed or inherent to such processes, methods, products, or apparatus.

[0201] It should be understood that in this application, "at least one (item)" means one or more, and "more than" means two or more. "And / or" is used to describe the relationship between related objects, indicating that three relationships can exist. For example, "A and / or B" can represent three cases: only A exists, only B exists, and both A and B exist simultaneously, where A and B can be singular or plural. The character " / " generally indicates that the preceding and following related objects are in an "or" relationship. "At least one (item) of the following" or similar expressions refer to any combination of these items, including any combination of single or plural items. For example, at least one (item) of a, b, or c can represent: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, and c can be single or multiple.

[0202] In the several embodiments provided in this application, it should be understood that the disclosed apparatus and methods can be implemented in other ways. For example, the apparatus embodiments described above are merely illustrative; for instance, the division of the units described above is only a logical functional division, and in actual implementation, there may be other division methods. For example, multiple units or components may be combined or integrated into another system, or some features may be ignored or not executed. Furthermore, the coupling or direct coupling or communication connection shown or discussed may be through some interfaces; the indirect coupling or communication connection between apparatuses or units may be electrical, mechanical, or other forms.

[0203] The units described above as separate components may or may not be physically separate. The components shown as units may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the units can be selected to achieve the purpose of this embodiment according to actual needs.

[0204] Furthermore, the functional units in the various embodiments of this application can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or as a software functional unit.

[0205] If the integrated unit is implemented as a software functional unit and sold or used as an independent product, it can be stored in a computer-readable storage medium. Based on this understanding, the technical solution of this application, in essence, or the part that contributes to the prior art, or all or part of the technical solution, can be embodied in the form of a software product. This computer software product is stored in a storage medium and includes multiple instructions to cause a computer device (which may be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of the various embodiments of this application. The aforementioned storage medium includes various media capable of storing programs, such as USB flash drives, portable hard drives, read-only memory (ROM), random access memory (RAM), magnetic disks, or optical disks.

[0206] The preferred embodiments of the present application have been described above with reference to the accompanying drawings, but this does not limit the scope of the claims of the present application. Any modifications, equivalent substitutions, and improvements made by those skilled in the art without departing from the scope and substance of the embodiments of the present application shall be within the scope of the claims of the present application.

Claims

1. A method for controlling an adjusting rod, characterized in that, The method is applied to a nuclear power plant system, the nuclear power plant system including a power conditioning rod, a temperature conditioning rod, a primary loop subsystem, and a secondary loop subsystem, the primary loop subsystem including a reactor, the power conditioning rod and the temperature conditioning rod being respectively inserted into the reactor; the method includes: Obtain the operating status information of the nuclear power plant system; In response to the operating condition information being a load shedding condition, the target power of the reactor matching the load shedding condition is obtained; The second-loop load demand signal of the second-loop subsystem is determined based on the target power and the preset initial correction factor. Based on the secondary loop load demand signal and the first initial position of the power regulating rod in the reactor, the power regulating rod is controlled to move to adjust the reactor power to the target power; The second initial position of the temperature regulating rod in the reactor is obtained, and the initial correction factor is numerically adjusted according to the second initial position to obtain the target correction factor; Based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor, the temperature regulating rod is controlled to move to the middle position. The target amount of demineralized water required to dilute boric acid is calculated based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem. The target amount of demineralized water is then injected into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position.

2. The method according to claim 1, characterized in that, The step of controlling the movement of the power regulating rod based on the secondary loop load demand signal and the first initial position of the power regulating rod within the reactor to adjust the reactor power to the target power includes: The target position of the power regulating rod within the reactor is determined based on the secondary loop load demand signal. The position error is determined based on the current initial position of the power regulating rod within the reactor and the target position. A first rod position adjustment signal is generated based on the position error, and the power adjustment rod is moved according to the first rod position adjustment signal until the power adjustment rod reaches the target position, so as to adjust the power of the reactor to the target power.

3. The method according to claim 1, characterized in that, The step of controlling the temperature regulating rod to move to the intermediate position based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor includes: The second-loop load demand signal is corrected according to the target correction factor and the target power, and the target temperature of the first-loop subsystem is determined according to the corrected second-loop load demand signal. Based on the measured temperature of the primary loop subsystem, the target temperature of the primary loop subsystem, the load demand signal of the secondary loop, and the measured power of the reactor, the temperature regulating rod is controlled to move to the intermediate position.

4. The method according to claim 3, characterized in that, The step of correcting the secondary load demand signal based on the target correction factor and the target power, and determining the target temperature of the primary subsystem based on the corrected secondary load demand signal, includes: The intermediate load demand signal is obtained by superimposing the target power and the target correction factor. The intermediate load demand signal is subjected to first-order filtering to obtain a candidate load demand signal, and the second-loop load demand signal is replaced with the candidate load demand signal. The target temperature of the primary loop subsystem is determined based on the preset load-temperature mapping relationship and the corrected secondary loop load demand signal.

5. The method according to claim 3, characterized in that, The step of controlling the temperature regulating rod to move to the intermediate position based on the measured temperature of the primary loop subsystem, the target temperature of the primary loop subsystem, the secondary loop load demand signal, and the measured power of the reactor includes: Based on the load demand signal of the two-loop circuit and the measured power generation power deviation signal; The power deviation signal is differentiated to obtain the power mismatch feedforward signal; A temperature deviation signal is generated based on the measured temperature and the target temperature of the primary loop subsystem. The temperature deviation signal and the power deviation signal are superimposed to obtain the second rod position adjustment signal; The temperature regulating rod is moved according to the second rod position adjustment signal until it reaches the intermediate position.

6. The method according to claim 1, characterized in that, The step of calculating the target amount of demineralized water required to dilute boric acid with demineralized water based on the middle position of the temperature regulating rod, a preset safe position, and a preset initial boric acid concentration of the primary loop subsystem, and injecting the target amount of demineralized water into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position, includes: The target amount of demineralized water required to dilute boric acid is calculated based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem. The target amount of demineralized water required to dilute boric acid with demineralized water is divided into multiple sub-water volumes; According to the second preset time period, the demineralized water volume of each sub-water is injected into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem in stages until the temperature regulating rod reaches the safe position.

7. The method according to any one of claims 1 to 6, characterized in that, The method further includes: calculating the target amount of demineralized water required to dilute boric acid using demineralized water based on the middle position of the temperature regulating rod, a preset safe position, and a preset initial boric acid concentration of the primary loop subsystem; injecting the target amount of demineralized water into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position; and injecting the target amount of demineralized water into the primary loop subsystem to dilute the boric acid in the primary loop subsystem. Obtain a first preset position and a second preset position; wherein, the first preset position is the maximum value of the preset safety adjustment band of the temperature adjustment rod, and the second preset position is the minimum value of the preset safety adjustment band of the temperature adjustment rod; Obtain the lowest position of the temperature regulating rod in the reactor; The safe position is determined based on the first preset position, the second preset position, and the lower limit position, wherein the safe position is lower than the first preset position, higher than the second preset position, and higher than the lower limit position.

8. The method according to any one of claims 1 to 6, characterized in that, The process of obtaining the second initial position of the temperature regulating rod within the reactor and adjusting the initial correction factor based on the second initial position to obtain the target correction factor includes: The initial correction factor and the preset increment are integrated and calculated in the first preset time period to obtain the candidate correction factor; If the second initial position remains unchanged or increases, then in the next first preset time period, the candidate correction factor and the preset increment are integrated and calculated to obtain an intermediate correction factor, and the intermediate correction factor replaces the candidate correction factor. If the second initial position decreases, then the candidate correction factor is used as the target correction factor.

9. The method according to any one of claims 1 to 6, characterized in that, The primary loop subsystem includes multiple thermal loops; before controlling the temperature regulating rod to move to the intermediate position based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor, the measured temperature of the primary loop subsystem is obtained through the following steps: For each of the aforementioned thermal circuits, the inlet temperature and the outlet temperature of the thermal circuit are obtained. The average temperature is calculated by averaging the inlet temperature and the outlet temperature. The average temperature is filtered to obtain the measured temperature of the primary loop subsystem.

10. An electronic device, characterized in that, The electronic device includes a memory and a processor, the memory storing a computer program, and the processor executing the computer program to implement the method of any one of claims 1 to 9.

11. A nuclear power plant system, characterized in that, The nuclear power plant system includes: The electronic device as claimed in claim 10; The system includes a power regulating rod, a temperature regulating rod, a primary loop subsystem, and a secondary loop subsystem, wherein the primary loop subsystem includes a reactor.

12. A regulating rod control device, characterized in that, The device includes: Operating condition information acquisition module, used to acquire operating condition information of the nuclear power plant system; The target power acquisition module is used to acquire the target power of the reactor matching the load shedding condition in response to the operating condition information being a load shedding condition. The load demand signal acquisition module is used to determine the second-loop load demand signal of the second-loop subsystem based on the target power and the preset initial correction factor. The first rod position control module is used to control the movement of the power regulating rod according to the secondary loop load demand signal and the first initial position of the power regulating rod in the reactor, so as to adjust the power of the reactor to the target power. The correction factor adjustment module is used to obtain the second initial position of the temperature regulating rod in the reactor, and to adjust the initial correction factor according to the second initial position to obtain the target correction factor; The second rod position control module is used to control the temperature regulating rod to move to the middle position based on the target correction factor, the target power, the measured temperature of the primary loop subsystem, and the measured power of the reactor. The dilution adjustment module is used to calculate the target amount of demineralized water required to dilute boric acid based on the middle position of the temperature regulating rod, the preset safe position, and the preset initial boric acid concentration of the primary loop subsystem. The module then injects the target amount of demineralized water into the primary loop subsystem to adjust the position of the temperature regulating rod by diluting the boric acid in the primary loop subsystem until the temperature regulating rod reaches the safe position.

13. A computer-readable storage medium storing a computer program, characterized in that, When the computer program is executed by a processor, it implements the method of any one of claims 1 to 9.

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