Nuclear power feed pump control system, control method and electronic equipment

Abstract

The invention is suitable for the technical field of nuclear power equipment management, and provides a nuclear power feed pump control system and method and electronic equipment, and the system comprises a control module which is used for executing a speed raising control sequence which comprises the control steps of starting a nuclear power feed pump and controlling the rotating speed of the nuclear power feed pump to reach the speed raising control of a target rotating speed; the interaction module is used for obtaining and displaying actual state information of target components of the nuclear power feed pump in the process that the control module executes the speed raising control sequence, the target components at least comprise components involved in the control step, and the actual state information reflects current state information of the target components; and the monitoring module is used for monitoring the actual state information of the target component and generating first alarm information based on the abnormal actual state information when it is monitored that the actual state information is abnormal, and the first alarm information is used for indicating that the state of the target component is abnormal. According to the invention, the manual dependence of the speed raising control of the nuclear power feed pump can be reduced.

Description

Technical Field

[0001] The present application belongs to the technical field of nuclear power equipment management, and in particular to a nuclear power feed water pump control system, control method and electronic equipment. Background Art

[0002] The nuclear power feed water pump is one of the core equipment in the cooling system of a nuclear power plant. It is responsible for pumping the reactor coolant from the low-pressure area to the high-pressure area, and then taking away the heat generated by the nuclear reactor through the heat exchange process to maintain the safe and stable operation of the nuclear reaction. Since the speed of the nuclear power feed water pump is a key factor affecting the operating efficiency and safety of the nuclear power plant, when starting the nuclear power feed water pump, the nuclear power feed water pump is usually finely controlled to accelerate the nuclear power feed water pump from a stationary state to the operating speed as smoothly and safely as possible, so as to meet the needs of the nuclear power plant and ensure the stable operation and safety of the nuclear power plant.

[0003] Currently, the GEM80 system is usually used to control the speed of nuclear power feed water pumps. However, it requires operators to call up various information indicator panels of the nuclear power feed water pumps for monitoring at the panel, which is highly dependent on manual work. In addition, when an abnormality occurs during the speed control process, the GEM80 system can usually only indicate the type of abnormality such as valve abnormality or temperature abnormality, but cannot locate the specific abnormal component. It requires experienced users to shut down the nuclear power feed water pump for inspection, which has a great impact on the operating efficiency of the nuclear power plant. Summary of the invention

[0004] The embodiments of the present application provide a nuclear power feed water pump control system, a control method and an electronic device, which can reduce the manual dependence of the nuclear power feed water pump speed increase control.

[0005] In a first aspect, an embodiment of the present application provides a nuclear power feedwater pump control system, comprising:

[0006] A control module, used to execute a speed increase control sequence, wherein the speed increase control sequence includes a control step of speed increase control for starting a nuclear power feed water pump and controlling the speed of the nuclear power feed water pump to reach a target speed;

[0007] An interactive module, used for acquiring and displaying actual status information of target components of the nuclear power feed water pump when the control module executes the speed increase control sequence, wherein the target components at least include components involved in the control steps, and the actual status information reflects the current status information of the target components;

[0008] The monitoring module is used to monitor the actual status information of the target component, and when the actual status information is detected to be abnormal, generate first alarm information based on the abnormal actual status information, wherein the first alarm information is used to indicate that the target component has an abnormal status.

[0009] In a second aspect, an embodiment of the present application provides a nuclear power feedwater pump control method, comprising:

[0010] Executing a speed increase control sequence, the speed increase control sequence comprising a speed increase control control step for starting a nuclear power feed water pump and controlling the speed of the nuclear power feed water pump to reach a target speed;

[0011] During the execution of the speed increase control sequence, actual state information of a target component of the nuclear power feed water pump is acquired and displayed, wherein the target component at least includes the component involved in the control step, and the actual state information reflects the current state information of the target component;

[0012] The actual status information of each of the target components is monitored, and when the actual status information is detected to be abnormal, first alarm information is generated based on the abnormal actual status information, wherein the first alarm information is used to indicate that the target component has an abnormal status.

[0013] In a third aspect, an embodiment of the present application provides an electronic device comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the processor implements the steps of the nuclear power feed water pump control method described in the second aspect when executing the computer program.

[0014] In a fourth aspect, an embodiment of the present application provides a computer-readable storage medium, wherein the computer storage medium stores a computer program, and when the computer program is executed by a processor, the steps of the nuclear power feed water pump control method described in the second aspect are implemented.

[0015] In a fifth aspect, an embodiment of the present application provides a computer program product. When the computer program product is run on an electronic device, the electronic device executes the nuclear power feed water pump control method described in the second aspect above.

[0016] Compared with the prior art, the embodiments of the present invention have the following beneficial effects:

[0017] In the embodiment of the present application, the control module of the nuclear power feed water pump control system executes the speed control sequence to start the nuclear power feed water pump and control its speed to reach the target speed. The interactive module will obtain the actual state information of the target component of the nuclear power feed water pump. Since the target component at least includes the components involved in the control steps in the speed control sequence, and the actual state information can reflect the current state information of the target component, the actual state information of the target component is displayed by the interactive module, so that the staff can clearly understand the state of the target component of the nuclear power feed water pump during the speed control process. At the same time, the monitoring module can automatically monitor the actual state information of the target component without relying on manual monitoring. When an abnormality is detected in a certain actual state information, the monitoring module will generate a first alarm information according to the abnormal actual state information, so that the user can better determine the abnormal target component according to the first alarm information, and then the user can quickly and accurately process the abnormal target component, reducing the impact of the abnormality in the speed control process of the nuclear power feed water pump on the operating efficiency and safety of the nuclear power plant. BRIEF DESCRIPTION OF THE DRAWINGS

[0018] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the following briefly introduces the drawings required for use in the embodiments or descriptions of the prior art.

[0019] Figure 1 It is a structural schematic diagram of a nuclear power feed water pump control system provided by an embodiment of the present application;

[0020] Figure 2 is a schematic diagram of an interactive module provided in an embodiment of the present application displaying actual status information of a target component;

[0021] Figure 3 It is a flow chart of a nuclear power feed water pump control method provided in an embodiment of the present application;

[0022] Figure 4 It is a schematic diagram of the structure of an electronic device provided in an embodiment of the present application. DETAILED DESCRIPTION

[0023] In the following description, specific details such as specific system structures, technologies, etc. are provided for the purpose of illustration rather than limitation, so as to provide a thorough understanding of the embodiments of the present application. However, it should be clear to those skilled in the art that the present application may also be implemented in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted to prevent unnecessary details from obstructing the description of the present application.

[0024] It should be understood that when used in the present specification and the appended claims, the term "comprising" indicates the presence of described features, wholes, steps, operations, elements and / or components, but does not exclude the presence or addition of one or more other features, wholes, steps, operations, elements, components and / or combinations thereof.

[0025] It should also be understood that the term “and / or” used in the specification and appended claims refers to any and all possible combinations of one or more of the associated listed items, and includes these combinations.

[0026] In addition, in the description of the present application specification and the appended claims, the terms "first", "second", "third", etc. are only used to distinguish the descriptions and cannot be understood as indicating or implying relative importance.

[0027] References to "one embodiment" or "some embodiments" etc. described in the specification of this application mean that one or more embodiments of the present application include specific features, structures or characteristics described in conjunction with the embodiment. Therefore, the phrases "in one embodiment", "in some embodiments", "in some other embodiments", "in some other embodiments", etc. appearing in different places in this specification do not necessarily refer to the same embodiment, but mean "one or more but not all embodiments", unless otherwise specifically emphasized in other ways.

[0028] Figure 1 The structural block diagram of a nuclear power feedwater pump control system provided by an embodiment of the present application is shown. For ease of description, only the parts related to the embodiment of the present application are shown.

[0029] Reference Figure 1 The nuclear power feed water pump control system includes: a control module 11, an interaction module 12 and a monitoring module 13. Among them,

[0030] The control module 11 is used to execute a speed increase control sequence, wherein the speed increase control sequence includes a speed increase control step for starting a nuclear power feed water pump and controlling the speed of the nuclear power feed water pump to reach a target speed.

[0031] The above-mentioned speed increase control sequence is a control step set according to the production process and safety requirements of the nuclear power feed water pump, which is used to start the nuclear power feed water pump and control the speed of the nuclear power feed water pump to reach the target speed during the startup process to ensure that the nuclear power feed water pump can be put into operation safely and orderly. Among them, the speed control of the nuclear power feed water pump usually includes two control stages. The first control stage is usually the startup speed increase control stage, that is, the speed of the nuclear power feed water pump is increased from 0 to the target speed during the startup process. Assuming that the target speed is the first speed, such as 4300 revolutions per minute, it can be set by the user. The second control stage is usually the load control adjustment stage, which mainly adjusts the speed of the nuclear power feed water pump from the first speed to the second speed corresponding to the load demand (such as 6300 revolutions per minute) according to the load demand. The execution of the speed increase control sequence of this application corresponds to the above-mentioned first control stage.

[0032] Since the startup speed control stage is usually implemented through the GEM80 system, the embodiments of the present application mainly focus on the startup speed control stage of the nuclear power feed water pump, that is, the target speed in the embodiments of the present application is determined according to the first speed in the startup speed control stage. In other embodiments, since the load control and adjustment stage of the nuclear power feed water pump is usually implemented through an on-site speed control cabinet, the operation is relatively complicated and the efficiency is low. Therefore, the load control and adjustment stage of the nuclear power feed water pump can also be implemented through a nuclear power feed water pump control system. At this time, the target speed can be the above-mentioned second speed, and the speed control sequence can include a speed control step for starting the nuclear power feed water pump and controlling the speed of the nuclear power feed water pump to increase from 0 to the target speed, or a speed control step for controlling the speed of the nuclear power feed water pump to increase from the first speed to the target speed.

[0033] As an example, the control module 11 can execute a speed increase control sequence when an execution instruction is detected. The execution instruction can be input by the user or automatically triggered by a preset time such as a timed start, and is used to instruct the start of the nuclear power feed water pump and control the speed of the nuclear power feed water pump to reach the target speed.

[0034] As another example, the control module 11 can execute the speed-up control sequence when it detects the execution instruction and detects that the nuclear power feed water pump meets the execution conditions, thereby reducing the risk of abnormalities in the nuclear power feed water pump during the startup and speed-up process, which is beneficial to ensuring the safety of nuclear power. Among them, since the operating status of the nuclear power feed water pump will directly affect the safety and benefits of the nuclear power plant, in order to fully ensure the safety and benefits of the nuclear power plant, in the embodiment of the present application, the execution conditions of the nuclear power feed water pump can be determined in combination with the safety requirements of the nuclear power plant. As an example, the execution conditions include but are not limited to: the relevant nuclear protection systems (such as the reactor emergency shutdown system and the safety injection system) are in an available state; the relevant auxiliary systems (such as the cooling water system, the lubricating oil system, and the sealing water system) are in normal operating state; the radiation level in the operating area meets the standard, etc.

[0035] The interactive module 12 is used to obtain and display the actual status information of the target components of the nuclear power feed water pump when the control module 11 executes the speed increase control sequence. The target components at least include the components involved in the control steps. The actual status information reflects the current status information of the target components.

[0036] The above-mentioned status information includes but is not limited to one or more information of switch status, temperature, valve opening, speed, pressure and vibration.

[0037] The above-mentioned components may include various components of the equipment itself. For example, the components of a nuclear power feed water pump may include an inlet valve, an outlet valve, a pump casing, an impeller, a pump shaft, bearings and a coupling.

[0038] It should be noted that the above-mentioned target components may include components involved in the control steps in the nuclear power feed water pump, and may also include components involved in the control steps in the associated equipment of the nuclear power feed water pump. The associated equipment of the nuclear power feed water pump is equipment that has an associated relationship with the nuclear power feed water pump, such as heat exchangers, decoupling devices, emergency cooling systems and lubrication systems.

[0039] At the same time, the target component can be a component involved in the control step currently being executed by the control module 11, or the target component can be a component involved in the control step currently being executed by the control module 11 and the control step that has been executed, or a component involved in all control steps, which can be set according to the actual application scenario. For example, the target component can be a component involved in all control steps. During the process of the control module 11 executing the speed-up start sequence, the interactive module 12 will display the actual status information of all target components involved, so that the user can monitor the actual status information of all target components related to each control step, thereby improving the comprehensiveness of abnormal monitoring during the speed-up control process.

[0040] Optionally, the interaction module 12 can monitor whether the control module 11 starts to execute the speed-up control sequence, or the control module 11 can actively send a start execution notification to the interaction module 12 when starting to execute the speed-up control sequence, indicating that the control module 11 has started to execute the speed-up control sequence, so that the interaction module 12 can obtain the actual status information of the target component in time when the control module 11 starts to execute the speed-up control sequence.

[0041] Optionally, after determining that the control module 11 has started to execute the speed increase control sequence, the interactive module 12 can obtain the actual status information of the target components of the nuclear power feed water pump based on fixed time intervals (such as 10 seconds) or random time intervals during the process of the control module 11 executing the speed increase control sequence, and display the latest actual status information obtained.

[0042] As an example, the interaction module 12 may obtain the first state information of the target component through measurement devices (such as pressure sensors or flow meters, etc.) installed at various locations of the nuclear power feed water pump.

[0043] Optionally, the interaction module 12 can display the actual status information of the target component through a touch screen integrated machine, a smart terminal (such as a smart phone) or a wearable smart device (such as augmented reality glasses).

[0044] Figure 2 FIG. 1 shows a schematic diagram of actual status information of each target component displayed by the interaction module 12 in some embodiments, such as Figure 2 As shown, when displaying the actual status information of each target component, the interactive interface can indicate information such as the temperature or flow rate of the target component, and can also indicate the switch status of the target component through different colors.

[0045] In the embodiment of the present application, the interactive module 12 will obtain and display the actual status information of the target components of the nuclear power feed water pump during the process of the control module 11 executing the speed increase control sequence, so that the user can quickly and clearly understand the status information of each component during the start-up and speed increase process of the nuclear power feed water pump without manually calling up various information indicator panels of the nuclear power feed water pump, which is conducive to improving the user experience.

[0046] The monitoring module 13 is used to monitor the actual status information of the target component, and when the actual status information is detected to be abnormal, generate first alarm information based on the abnormal actual status information, wherein the first alarm information is used to indicate that the target component has an abnormal status.

[0047] Optionally, the actual status information of the target component acquired by the monitoring module 13 may be actively sent by the interaction module 12, or may be automatically acquired from the interaction module 12 through methods such as subscription services, or may be directly acquired from a nuclear power feed water pump through measuring devices such as temperature sensors. The embodiment of the present application does not impose any specific restrictions on the manner in which the monitoring module 13 acquires the actual status information of the target component.

[0048] In the embodiment of the present application, when the control module 11 executes the speed-up control sequence, the interactive module 12 will obtain the actual state information of the target component. Since the target component at least includes the components involved in the control step, and the actual state information can reflect the current state information of the target component, the interactive module 12 displays the actual state information of the target component, so that the staff can quickly and clearly understand the state of the target component of the nuclear power feed water pump during the speed-up control process. At the same time, the monitoring module 13 can automatically monitor the actual state information of the target component without relying on manual monitoring, which can reduce the manual dependence in the process of starting and speeding up the nuclear power feed water pump. When an abnormality is detected in a certain actual state information, the monitoring module 13 will generate a first alarm information according to the abnormal actual state information, so that the user can better determine the abnormal target component according to the first alarm information, and then the user can quickly and accurately process the abnormal target component, which can better reduce the impact of the abnormality in the process of starting and speeding up the nuclear power feed water pump on the operating efficiency and safety of the nuclear power plant.

[0049] In some embodiments, the speed increase control sequence includes a plurality of the control steps, and the interaction module 12, when acquiring and displaying the actual status information of each target component of the nuclear power feed water pump, includes:

[0050] After the control module 11 executes one of the control steps, the actual state information of the target component involved in the control step currently being executed is obtained.

[0051] Display the above actual status information obtained.

[0052] When monitoring the actual status information of the target component, the monitoring module 13 includes:

[0053] After the control module 11 executes one of the control steps, the actual status information of the target component involved in the control step currently being executed is monitored.

[0054] In order to improve the user experience, during the process of the control module 11 executing the speed-up control sequence, the interactive module 12 can monitor the execution progress of the control module 11. Since the monitoring control usually executes the next execution step after executing a control step, the monitoring can obtain the actual state information of the target components involved in the currently executed control step every time the control module 11 is detected to execute a control step during the monitoring process, and display the latest actual state information of the target components through a display unit (such as a touch screen), so that the user can timely understand the execution progress of the speed-up control sequence (i.e., the start-up speed-up progress of the nuclear power feed water pump) and the current state information of the target components involved in the currently executed control step through the interactive module 12, and it is beneficial for the user to perform abnormal monitoring of the nuclear power feed water pump.

[0055] It should be noted that the target components involved in the currently executed control step may also include one or more target components corresponding to other control steps. For example, assuming that the speed increase control sequence includes control step 1, control step 2, and control step 3, control step 1 needs to control its corresponding components A1 and A2, control step 2 needs to control its corresponding components B1 and B2, and control step 3 needs to control its corresponding component C1; assuming that the currently executed control step is control step 2, and assuming that when component B2 is controlled, it may affect the status information of component A1, at this time, the target components involved in the currently executed control step 2 may include its corresponding components B1, component B2, and component A1 corresponding to control step 1.

[0056] As an example, the control module 11 may send a step execution notification to the interaction module 12 (used to notify the interaction module 12 that the control module 11 has executed a new control step) and obtain the actual status information of the target component from the nuclear power feed water pump after each control step is executed and when a new control step is executed; if the interaction module 12 receives the step execution notification, it can be determined that it has detected that the control module 11 has executed a new control step. At this time, an information request can be sent to the control module 11 (used to instruct the control module 11 to send the actual status information of the target component); after receiving the information request, the control module 11 can send the obtained actual status information of the target component to the interaction module 12.

[0057] As another example, the interaction module 12 may directly obtain the actual status information of the required target component from the nuclear power feed water pump through a measuring device such as a sensor every time it detects that the control module 11 executes a control step.

[0058] In an embodiment of the present application, the interactive module 12 monitors the progress of the control module 11 in executing the speed-up control sequence, and after detecting that the control module 11 executes a control step, it obtains and displays the latest actual status information of the target components involved in the currently executed control step, so that the user can promptly know the start-up speed-up progress of the nuclear power feed water pump and the status information of related components, which is beneficial for the user to monitor the abnormality of the nuclear power feed water pump.

[0059] In some embodiments, the monitoring module 13 detects the actual status information of the target component involved in the control step currently being executed, including:

[0060] Whether the actual state information is abnormal is determined based on the first state information corresponding to the control step currently being executed and the actual state information of the target component, wherein the first state information reflects the state information that the target component should currently meet.

[0061] It can be understood that when executing different control steps, the first state information corresponding to each target component may be different. The first state information corresponding to the target component in each control step may be determined based on the control step, or may be determined based on the control step and all previous control steps or control steps related to the control step, the process of the nuclear power feed water pump and other information. It can be specifically set according to the actual application scenario.

[0062] Specifically, since the speed-up control sequence usually includes multiple control steps in order, the execution of new control steps may cause changes in the states of various target components of the nuclear power feed water pump, making them fail to meet the expected requirements, that is, there is an abnormality in the actual state information of the target components. Therefore, in the process of the control module 11 executing each control step in the startup sequence, the monitoring module 13 can obtain the current actual state information of the target components involved in the currently executed control step after the control module 11 executes a control step, and judge whether there is an abnormality in the target component based on the actual state information corresponding to the currently executed control step and the first state information corresponding to the currently executed control step.

[0063] That is, after acquiring the actual state information corresponding to the currently executed control step of the target component, the monitoring module 13 determines whether there is an abnormality in each target component according to the first state information corresponding to the currently executed control step and the actual state information.

[0064] At this time, the first status information corresponding to the target component in the control step currently being executed may be the status information that reflects the target component should satisfy after executing the previous control step, that is, to determine whether the execution of the currently executed control step affects the status information that the target component has previously satisfied, causing the state of the target component to become abnormal.

[0065] Among them, in the process of the control module 11 executing each control step in the startup sequence, the actual status information of each target component corresponding to the currently executed control step can be actively obtained by the monitoring module 13 from the control module 11, the interaction module 12 or the nuclear power feed water pump, or it can be sent to the monitoring module 13 by the control module 11 or the interaction module 12. The embodiment of the present application does not impose any specific restrictions on the manner in which the monitoring module 13 obtains the actual status information corresponding to the currently executed control step.

[0066] As an example, the monitoring module 13 may monitor the control module 11 , and obtain first state information corresponding to the control step currently being executed for each target component after detecting that the control module 11 executes a control step.

[0067] As another example, since the interaction module 12 obtains the actual status information of each target component each time it detects that the control module 11 executes a control step, in order to reduce resource consumption, the interaction module 12 can directly send the actual status information corresponding to the currently executed control step to the monitoring module 13 when it obtains it, and the monitoring module 13 does not need to monitor the execution progress of the control module 11 and other devices to start the control sequence.

[0068] In the embodiment of the present application, during the process of the control module 11 executing each control step of the speed-up control sequence, the actual state information corresponding to the target component in each control step and its corresponding first state information are judged to be abnormal. When it is judged that a certain target component is abnormal, the cause of the abnormal state of the target component can be better determined according to the corresponding control step, so that the user can handle the abnormality of the target component. At the same time, the control module 11 judges the abnormal state when executing each control step, and can timely discover the abnormality of the target component, reduce the probability of executing subsequent control steps when there is an abnormal target component, thereby reducing the impact of the abnormal target component, which is conducive to improving the safety of the nuclear power plant.

[0069] In some embodiments, after determining whether the actual state information is abnormal according to the first state information corresponding to the control step currently being executed and the actual state information of the target component, the monitoring module 13 further includes:

[0070] Determine whether the actual status information of all the target components involved in each of the control steps is abnormal.

[0071] When it is determined that there is no abnormality in the actual status information of all the above-mentioned target components, it is determined whether the target components involved in the above-mentioned control step currently being executed satisfy the corresponding second status information. The above-mentioned second status information reflects the status information that the target components involved in the above-mentioned control step currently being executed should satisfy before executing the target control step. The above-mentioned target control step is the next control step of the above-mentioned control step currently being executed.

[0072] When it is determined that the target component involved in the control step currently being executed satisfies the corresponding second state information, an execution notification is sent to the control module 11, and the execution notification is used to instruct the control module 11 to execute the next control step.

[0073] The second state information reflects the state information that the target component involved in the currently executed control step should satisfy before executing the target control step. Optionally, the second state information may be determined based on the completion condition corresponding to the currently executed control step, or the second state information may be determined based on the completion condition corresponding to the currently executed control step and the previously executed control step.

[0074] In order to improve the starting and speed-up efficiency of nuclear power feed water pumps while ensuring nuclear power safety, the monitoring module 13 can determine whether the target component meets its corresponding second state information when it is determined that there is no abnormality in the actual state information of all target components involved in the currently executed control step, that is, whether the target control step (that is, the next control step) can be executed based on the actual state information of each target component and its second state information.

[0075] Among them, if the monitoring module 13 determines that the actual status information of all target components has satisfied their corresponding second status information, it indicates that the target control step can be executed. At this time, the monitoring module 13 can send an execution notification to the control module 11, and use the execution notification to instruct the control module 11 to execute the next control step.

[0076] If the actual status information of any target component does not satisfy the corresponding second status information, subsequent processing can be performed according to the requirements of the actual application scenario.

[0077] As an example, after a second preset time (such as 10 seconds), it can be determined again whether each target component or candidate target component (i.e., a target component that did not satisfy the second state information in the previous determination process) involved in the currently executed control step satisfies the second state information. Optionally, after the second preset time, it can be determined first whether the candidate target component satisfies its corresponding second state information. When it is determined that the candidate target component has satisfied its second state information, it is determined again whether other target components involved in the currently executed control step still satisfy their corresponding second state information, and it is determined whether the actual state information of all target components satisfies their corresponding first state information. That is, it fully considers the situation in which the state of the components that have previously satisfied the corresponding state information in the time period corresponding to the second preset time has changed or is abnormal. When it is ensured that each target satisfies the corresponding state information, the control module 11 is notified to execute the next control step to further ensure nuclear power safety.

[0078] As another example, the monitoring module 13 may also continue to monitor the actual status information of each target component after first determining that any target component does not satisfy its corresponding second status information, so as to promptly notify the control module 11 to execute the next control step when it is detected that all target components have satisfied their corresponding second status information. When it is detected that all target components have satisfied their corresponding second status information, the first status information of each target component may be determined again, that is, whether the actual status information of each target component is abnormal at present, so as to ensure that the control module 11 executes the next control step when there is no abnormality in each target component, thereby fully ensuring the safety of nuclear power.

[0079] In an embodiment of the present application, when the control module 11 executes the current control step, the monitoring module 13 will promptly determine whether each target component corresponding to the currently executed control step satisfies the corresponding second status information after determining that there is no abnormality in the actual status information of all target components, that is, determine whether the conditions for executing the next control step are met, so that when the conditions are met, the control module 11 can be promptly notified to execute the next control step, so as to improve the starting and speed-up efficiency of the nuclear power feed water pump as much as possible while ensuring the safety of nuclear power.

[0080] In some embodiments, after determining whether the target component involved in the control step currently being executed satisfies the corresponding second state information, the monitoring module 13 further includes:

[0081] If at the end of the target time period, any target component involved in the above-mentioned control step currently being executed does not satisfy the corresponding second status information, a second alarm information is generated according to the above-mentioned control step currently being executed and sent to the above-mentioned control module 11, and the above-mentioned target time period is determined according to the time of executing the current control step and the preset execution time. The above-mentioned second alarm information is used to indicate that the above-mentioned nuclear power feed water pump has an execution abnormality in the above-mentioned control step currently being executed.

[0082] Correspondingly, the control module 11 is also used for:

[0083] When the second warning information is received, the control step currently being executed is suspended or terminated.

[0084] The above-mentioned preset execution time refers to the maximum execution time of the pre-set control step. It should be noted that due to certain differences in the complexity of different control steps, when setting the preset execution time, the corresponding preset execution time can be set for each control step according to the complexity of the control step.

[0085] Specifically, in order to reduce the impact of control step execution timeout, the target time period corresponding to the currently executed control step may be determined according to the execution time of the currently executed control step and its preset execution duration.

[0086] At the end of the target time period, that is, when the end time of the target time period is reached, if any target component involved in the currently executed control step does not satisfy its corresponding second status information, then it can be considered that the currently executed control step has timed out and there is an execution abnormality. At this time, a second alarm information can be generated based on the currently executed execution step to inform the user that the nuclear power feed water pump has an execution abnormality in the currently executed control step.

[0087] Optionally, after the second alarm information is generated, the second alarm information can be sent to the interactive module 12. The interactive module 12 displays the second alarm information through its display unit (such as a display screen or a touch screen, etc.), or sends the second alarm information to the target terminal, etc., to promptly inform the user of the abnormal execution of the nuclear power feed water pump.

[0088] At the same time, in order to reduce the risk caused by abnormal execution of the control step, the control module 11 can suspend or terminate the execution of the currently executed control step, reduce the probability of damage to the nuclear power feed water pump and ensure nuclear power safety. Among them, the currently executed control step can be suspended or terminated according to the actual application scenario to maximize the actual application effect.

[0089] For example, when the impact of the currently executed control step is greater than the impact threshold, you can choose to terminate the execution of the currently executed control step. After the user handles the execution exception, the control module 11 needs to re-execute the control step or re-execute the speed-up control sequence; when the impact of the currently executed control step is less than or equal to the impact threshold, you can choose to suspend the execution of the currently executed control step. After the user handles the execution exception, the control module 11 can continue to execute based on the previous execution progress of the control step. Among them, the impact of the control step can be determined according to the number and importance of the components it affects, etc., and no specific restrictions are made here.

[0090] For example, assuming that the time to start executing control step 3 is 9:30:00, and the preset execution time corresponding to control step 3 is 60 seconds, then the target time period corresponding to control step 3 is: 9:30:00-9:31:00.

[0091] Assume that the target components involved in control step 3 include target component A and target component B, and assume that the actual status information of all target components is obtained at 9:30:10, and it is determined that there is no abnormality in the actual status information of all target components. At this time, the monitoring module 13 can respectively determine whether the target components A and target components B meet their corresponding second status information based on the actual status information of the target components A and the target components B obtained from the interaction module 12.

[0092] Assuming that at 9:30:10 it is determined that target component A satisfies its second state information and target component B does not satisfy its second state information, the actual state information of target component B may be acquired every 5 seconds to determine whether target component B satisfies its second state information.

[0093] If during the period of 9:30:10-9:31:00, if it is determined based on the actual status information of target component B that target component B satisfies the second status information, then at this time, when it is determined that target component B satisfies the second status information, the latest actual status information of target component A can be obtained to determine whether target component A currently also satisfies its second status information, and, based on the latest actual status information of each target component, it can be determined again whether the nuclear power feed water pump has any abnormal status.

[0094] If the nuclear power feed water pump does not have abnormal state at the end of the target time period, and the target component A and the target component B also meet their corresponding second state information, the next control step (control step 4) can be executed. If it is determined that there is an abnormal state, the first alarm information can be generated, and control step 4 is not executed temporarily.

[0095] If during the period from 9:30:10 to 9:31:00, target component A and / or target component B do not satisfy their corresponding second status information, that is, the latest actual status information of target component A and target component B obtained at 9:31:00 still does not meet their second status information, it can be considered that there is an execution abnormality in control step 3. At this time, a second alarm information can be generated based on control step 3 and sent to the target terminal, and the execution of control step 3 can be suspended.

[0096] In the embodiment of the present application, a target time period is set as the execution time period of the control step. If the target component involved in the currently executed control step does not meet the corresponding second state information at the end of the target time period, it is considered that the control step execution has timed out, there is an execution abnormality, and the execution of the currently executed control step is suspended or terminated to reduce the risk caused by the execution abnormality. At the same time, the corresponding second alarm information is generated according to the currently executed control step so that the user can be informed of the abnormal situation of the nuclear power feed water pump in time.

[0097] In some embodiments, when executing the speed increase control sequence, the control module 11 includes:

[0098] When it is detected that the shaft vibration of the nuclear power feed water pump is greater than or equal to the shaft vibration threshold, the execution of the speed increase control sequence is suspended, and the speed of the nuclear power feed water pump is adjusted to a preset speed.

[0099] After controlling the nuclear power feed water pump to run for a preset time based on the preset speed, continue to execute the speed increase control sequence.

[0100] The shaft vibration (also called shaft vibration) refers to the lateral or axial movement of the rotating shaft of a rotating machine (such as a pump or motor, etc.) that deviates from the ideal center position during operation. The shaft vibration can be described by vibration displacement or vibration velocity. Optionally, the shaft vibration of a nuclear power feedwater pump may include at least one of pump shaft vibration, turbine shaft vibration, and coupler shaft vibration.

[0101] Since shaft vibration may cause fluctuations in the speed of the nuclear power feed water pump and affect the stability of the speed control of the nuclear power feed water pump, in order to ensure the stability of the speed control of the nuclear power feed water pump, the control module 11 can detect the shaft vibration of the nuclear power feed water pump by means such as a vibration sensor during the execution of the speed increase control sequence.

[0102] If the control module 11 detects that the shaft vibration of the nuclear power feed water pump is greater than or equal to the shaft vibration threshold (such as 80 microns), it can be considered that the shaft vibration of the nuclear power feed water pump is too large. At this time, the control module 11 can adjust the speed of the nuclear power feed water pump to a preset speed (such as 700 revolutions per minute).

[0103] After the control module 11 adjusts the speed of the nuclear power feed water pump to the preset speed, it can control the nuclear power feed water pump to maintain the preset speed for a preset time (such as 15 minutes), that is, to make the nuclear power feed water pump run stably based on the preset speed for a period of time, increase the heating time of its shaft system, so that all parts of the shaft system can be heated evenly, thereby reducing the shaft vibration caused by the temperature imbalance of the shaft system.

[0104] In some embodiments, the preset speed may be a smaller speed (such as one sixth of the target speed) set according to the target speed to avoid excessive speed causing excessive local temperature of the shaft system, thereby causing greater shaft vibration, etc. It should be noted that the preset speed is smaller than the target speed.

[0105] In some embodiments, after controlling the nuclear power feed water pump to maintain a preset speed and run for a preset time, the control module 11 can first determine whether the real-time shaft vibration of the nuclear power feed water pump is less than the shaft vibration threshold, and continue to execute the speed-up control sequence when it is determined that the real-time shaft vibration is less than the shaft vibration threshold. If it is determined that the real-time shaft vibration is greater than or equal to the shaft vibration threshold, at this time, the nuclear power feed water pump can continue to be controlled to run for a preset time based on the preset speed, and then it can be determined whether the speed-up control sequence can continue to be executed. If the nuclear power feed water pump maintains the preset speed and runs for a preset time after reaching the time threshold, and the latest shaft vibration of the nuclear power feed water pump is still greater than or equal to the shaft vibration threshold, the control module 11 can terminate the execution of the speed-up control sequence.

[0106] Optionally, after terminating the execution of the speed-up control sequence, the control module 11 may also generate an abnormal termination notification and send it to the interactive module 12. The abnormal termination notification is used to indicate that the nuclear power feed water pump has abnormally terminated due to abnormal shaft vibration during the startup and speed-up process, so that the user can deal with the abnormal shaft vibration of the nuclear power feed water pump in a timely manner, thereby reducing the impact of the nuclear power feed water pump being unable to be put into operation.

[0107] In the embodiment of the present application, when the control module 11 is executing the speed increase control sequence, if it is detected that the shaft vibration of the nuclear power feed water pump is too large, the execution of the speed increase control sequence will be suspended first, and then the speed of the nuclear power feed water pump will be adjusted to a preset speed and the nuclear power feed water pump will be controlled to maintain the preset speed for a certain period of time. By the above processing, the heating time of the shaft system of the nuclear power feed water pump is prolonged so that all parts of the shaft system can be heated evenly, thereby reducing the shaft vibration caused by reasons such as temperature imbalance of the shaft system, and then the speed increase control sequence will continue to be executed to avoid excessive shaft vibration affecting the speed stability of the nuclear power feed water pump.

[0108] In some embodiments, the control module 11 is further used for:

[0109] After continuing to execute the above speed increase control sequence, if it is detected again that the above shaft vibration is greater than or equal to the above shaft vibration threshold, the process returns to the step of pausing execution of the above speed increase control sequence.

[0110] When it is determined that the number of times the execution of the speed increase control sequence is suspended does not reach the number threshold, the step of adjusting the rotation speed of the nuclear power feed water pump to the rotation speed threshold until the execution of the speed increase control sequence continues is performed.

[0111] When it is determined that the number of times reaches the number threshold, the execution of the speed increase control sequence is terminated.

[0112] Considering that when the shaft vibration of a nuclear power feed water pump exceeds the shaft vibration threshold multiple times, it may be a problem of excessive shaft vibration caused by reasons such as bearing failure. Therefore, in an embodiment of the present application, the number of times the execution of the speed increase control sequence is suspended during the execution of the speed increase control sequence can be recorded.

[0113] It should be noted that since the execution of the speed increase control sequence may be suspended due to other reasons, in some embodiments, the recorded number of times (which may be called the reference number) may be the number of times the speed increase control sequence is suspended due to excessive shaft vibration (i.e., the shaft vibration is greater than or equal to the shaft vibration threshold).

[0114] It can be understood that during the first suspension of execution, the control module 11 controls the nuclear power feed water pump to maintain the preset speed for the preset time, and then continues to execute the speed increase control sequence. During the process of continuing to execute the speed increase control sequence, if the control module 11 again detects that the shaft vibration of the nuclear power feed water pump is greater than or equal to the shaft vibration threshold, at this time, it will return to the step of suspending the execution of the speed increase control sequence.

[0115] After pausing the execution of the speed-up control sequence again, the control module 11 will first determine whether the recorded reference number has reached the number threshold. If the recorded reference number has reached the number threshold (such as 3), at this time, considering the high possibility of failure of the bearings and other components of the nuclear power feed water pump, the current speed-up control sequence can be directly terminated to avoid continuing to run the nuclear power feed water pump and causing more abnormal situations, thereby reducing the safety risk of nuclear power.

[0116] Optionally, after terminating the execution of the speed increase control sequence, the control module 11 can generate an abnormal termination notification and send it to the interactive module 12, and can also send the abnormal termination notification to the target terminal (i.e., the terminal corresponding to the user) so as to promptly notify the user to check the cause of the excessive shaft vibration of the nuclear power feed water pump.

[0117] If the number of times the speed increase control sequence is currently suspended has not reached the number threshold (such as 3), at this time, there is no need to terminate the execution of the speed increase control sequence. The speed of the nuclear power feed water pump can be adjusted to the preset speed until the speed increase control sequence is continued.

[0118] In the embodiment of the present application, during the execution of the speed-up control sequence, when the shaft vibration of the nuclear power feed water pump is too large, the execution of the speed-up control sequence will be suspended, and the shaft vibration will be reduced through speed regulation and other processing, and then the speed-up control sequence will be continued. If the shaft vibration of the nuclear power feed water pump is too large, resulting in the suspension of the speed-up control sequence for the number of times reaching the number threshold, considering that there is a high probability that the shaft vibration is too large due to the failure of the bearing and other components of the nuclear power feed water pump, at this time, the execution of the speed-up control sequence is directly terminated to avoid the situation where the fault worsens due to the continued operation of the nuclear power feed water pump, thereby reducing the safety risk of nuclear power and reducing unnecessary resource consumption.

[0119] It should be understood that the size of the serial numbers of the steps in the above embodiments does not mean the order of execution. The execution order of each process should be determined by its function and internal logic, and should not constitute any limitation on the implementation process of the embodiments of the present application.

[0120] Corresponding to the nuclear power feed water pump control system described in the above embodiment, Figure 3 A flow chart of a nuclear power feed water pump control method provided in an embodiment of the present application is shown. For ease of explanation, only the parts related to the embodiment of the present application are shown.

[0121] The above-mentioned nuclear power feed water pump control method is described in detail as follows:

[0122] Step S301, executing a speed increase control sequence, the speed increase control sequence including a speed increase control step for starting a nuclear power feed water pump and controlling the speed of the nuclear power feed water pump to reach a target speed.

[0123] Step S302, during the execution of the above speed increase control sequence, the actual status information of the target components of the above nuclear power feed water pump is obtained and displayed, the above target components at least include the components involved in the above control steps, and the above actual status information reflects the current status information of the above target components.

[0124] Step S303, monitoring the actual status information of each of the target components, and when detecting that the actual status information is abnormal, generating first alarm information based on the abnormal actual status information, wherein the first alarm information is used to indicate that the target component is abnormal.

[0125] In the embodiment of the present application, when the control module executes the speed-up control sequence, the interactive module will obtain the actual state information of the target component. Since the target component at least includes the components involved in the control step, and the actual state information can reflect the current state information of the target component, the actual state information of the target component is displayed by the interactive module, so that the staff can quickly and clearly understand the state of the target component of the nuclear power feed water pump during the speed-up control process. At the same time, the monitoring module can automatically monitor the actual state information of the target component without relying on manual monitoring, which can reduce the manual dependence in the process of starting and speeding up the nuclear power feed water pump. When an abnormality is detected in a certain actual state information, the monitoring module will generate a first alarm information according to the abnormal actual state information, so that the user can better determine the abnormal target component according to the first alarm information, and then the user can quickly and accurately process the abnormal target component, which can better reduce the impact of the abnormality in the process of starting and speeding up the nuclear power feed water pump on the operating efficiency and safety of the nuclear power plant.

[0126] It should be noted that the information interaction, execution process, etc. between the above-mentioned devices / units are based on the same concept as the method embodiment of the present application. Their specific functions and technical effects can be found in the method embodiment part and will not be repeated here.

[0127] Figure 4 This is a schematic diagram of the structure of an electronic device provided by an embodiment of the present application. Figure 4 As shown, the electronic device 4 of this embodiment includes: at least one processor 40 ( Figure 4 Only one processor is shown in the figure), a memory 41, and a computer program 42 stored in the memory 41 and executable on the at least one processor 40, wherein the processor 40 implements the steps in any of the above-mentioned method embodiments when executing the computer program 42.

[0128] The electronic device 4 may be a computing device such as a desktop computer, a notebook, a PDA, or a cloud server. The electronic device may include, but is not limited to, a processor 40 and a memory 41. Those skilled in the art will appreciate that Figure 4 It is only an example of the electronic device 4 and does not constitute a limitation on the electronic device 4. It may include more or fewer components than shown in the figure, or a combination of certain components, or different components. For example, it may also include input and output devices, network access devices, etc.

[0129] The processor 40 may be a central processing unit (CPU), or other general-purpose processors, digital signal processors (DSP), application-specific integrated circuits (ASIC), field-programmable gate arrays (FPGA) or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. A general-purpose processor may be a microprocessor or any conventional processor, etc.

[0130] In some embodiments, the memory 41 may be an internal storage unit of the electronic device 4, such as a hard disk or memory of the electronic device 4. In other embodiments, the memory 41 may also be an external storage device of the electronic device 4, such as a plug-in hard disk, a smart memory card (Smart Media Card, SMC), a secure digital (Secure Digital, SD) card, a flash card (Flash Card), etc. equipped on the electronic device 4. Further, the memory 41 may also include both an internal storage unit of the electronic device 4 and an external storage device. The memory 41 is used to store an operating system, an application program, a boot loader (BootLoader), data, and other programs, such as the program code of the computer program, etc. The memory 41 may also be used to temporarily store data that has been output or is to be output.

[0131] The technicians in the relevant field can clearly understand that for the convenience and simplicity of description, only the division of the above-mentioned functional units and modules is used as an example for illustration. In practical applications, the above-mentioned function allocation can be completed by different functional units and modules as needed, that is, the internal structure of the device can be divided into different functional units or modules to complete all or part of the functions described above. The functional units and modules in the embodiment can be integrated in a processing unit, or each unit can exist physically separately, or two or more units can be integrated in one unit. The above-mentioned integrated unit can be implemented in the form of hardware or in the form of software functional units. In addition, the specific names of the functional units and modules are only for the convenience of distinguishing each other, and are not used to limit the scope of protection of this application. The specific working process of the units and modules in the above-mentioned system can refer to the corresponding process in the aforementioned method embodiment, which will not be repeated here.

[0132] An embodiment of the present application also provides a network device, which includes: at least one processor, a memory, and a computer program stored in the memory and executable on the at least one processor, wherein the processor implements the steps in any of the above-mentioned method embodiments when executing the computer program.

[0133] An embodiment of the present application further provides a computer-readable storage medium, wherein the computer-readable storage medium stores a computer program, and when the computer program is executed by a processor, the steps in the above-mentioned method embodiments can be implemented.

[0134] An embodiment of the present application provides a computer program product. When the computer program product runs on an electronic device, the electronic device can implement the steps in the above-mentioned method embodiments when executing the computer program product.

[0135] If the integrated unit is implemented in the form of 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 present application implements all or part of the processes in the above-mentioned embodiment method, which can be completed by instructing the relevant hardware through a computer program. The computer program can be stored in a computer-readable storage medium, and the computer program can implement the steps of the above-mentioned various method embodiments when executed by the processor. Among them, the computer program includes computer program code, and the computer program code can be in source code form, object code form, executable file or some intermediate form. The computer-readable medium may at least include: any entity or device that can carry the computer program code to the camera / electronic device, recording medium, computer memory, read-only memory (ROM, Read-Only Memory), random access memory (RAM, Random Access Memory), electric carrier signal, telecommunication signal and software distribution medium. For example, a USB flash drive, a mobile hard disk, a magnetic disk or an optical disk. In some jurisdictions, according to legislation and patent practice, computer-readable media cannot be electric carrier signals and telecommunication signals.

[0136] In the above embodiments, the description of each embodiment has its own emphasis. For parts that are not described or recorded in detail in a certain embodiment, reference can be made to the relevant descriptions of other embodiments.

[0137] Those of ordinary skill in the art will appreciate that the units and algorithm steps of each example described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, or a combination of computer software and electronic hardware. Whether these functions are performed in hardware or software depends on the specific application and design constraints of the technical solution. Professional and technical personnel can use different methods to implement the described functions for each specific application, but such implementation should not be considered to be beyond the scope of this application.

[0138] In the embodiments provided in the present application, it should be understood that the disclosed devices / network equipment and methods can be implemented in other ways. For example, the device / network equipment embodiments described above are merely schematic. For example, the division of the modules or units is only a logical function division. There may be other division methods in actual implementation, such as multiple units or components can be combined or integrated into another system, or some features can be ignored or not executed. Another point is that the mutual coupling or direct coupling or communication connection shown or discussed can be through some interfaces, indirect coupling or communication connection of devices or units, which can be electrical, mechanical or other forms.

[0139] The units described as separate components may or may not be physically separated, and the components shown as units may or may not be physical units, that is, they may be located in one place or distributed on multiple network units. Some or all of the units may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0140] The embodiments described above are only used to illustrate the technical solutions of the present application, rather than to limit them. Although the present application has been described in detail with reference to the aforementioned embodiments, a person skilled in the art should understand that the technical solutions described in the aforementioned embodiments may still be modified, or some of the technical features may be replaced by equivalents. Such modifications or replacements do not deviate the essence of the corresponding technical solutions from the spirit and scope of the technical solutions of the embodiments of the present application, and should all be included in the protection scope of the present application.

Claims

1. A nuclear power feed water pump control system, characterized in that: include: A control module, used to execute a speed increase control sequence, wherein the speed increase control sequence includes a control step of speed increase control for starting a nuclear power feed water pump and controlling the speed of the nuclear power feed water pump to reach a target speed; An interactive module, used for acquiring and displaying actual status information of target components of the nuclear power feed water pump when the control module executes the speed increase control sequence, wherein the target components at least include components involved in the control steps, and the actual status information reflects the current status information of the target components; The monitoring module is used to monitor the actual status information of the target component, and when the actual status information is detected to be abnormal, generate first alarm information based on the abnormal actual status information, wherein the first alarm information is used to indicate that the target component has an abnormal status.

2. The nuclear power feed water pump control system according to claim 1, characterized in that: The speed increase control sequence includes a plurality of control steps, and the interactive module, when acquiring and displaying the actual status information of the target component of the nuclear power feed water pump, includes: After the control module executes one of the control steps, obtaining actual state information of the target component involved in the control step currently being executed; Displaying the acquired actual status information; When the monitoring module monitors the actual status information of the target component, the monitoring module includes: After the control module executes one of the control steps, the actual state information of the target component involved in the control step currently being executed is monitored.

3. The nuclear power feed water pump control system according to claim 2, characterized in that: The monitoring module detects actual status information of the target component involved in the control step currently being executed, including: Whether the actual state information is abnormal is determined based on the first state information corresponding to the control step currently being executed and the actual state information of the target component, wherein the first state information reflects the state information that the target component should currently meet.

4. The nuclear power feed water pump control system according to claim 3, characterized in that: After the monitoring module determines whether the actual state information is abnormal according to the first state information corresponding to the currently executed control step and the actual state information of the target component, the monitoring module further includes: Determining whether the actual status information of all the target components involved in each of the control steps is abnormal; In the case where it is determined that the actual state information of all the target components does not have an abnormality, it is determined whether the target component involved in the control step currently being executed satisfies the corresponding second state information, the second state information reflects the state information that the target component involved in the control step currently being executed should satisfy before executing the target control step, the target control step being the next control step of the control step currently being executed; When it is determined that the target component involved in the control step currently being executed satisfies the corresponding second state information, an execution notification is sent to the control module, where the execution notification is used to instruct the control module to execute the next control step.

5. The nuclear power feed water pump control system according to claim 4, characterized in that: After determining whether the target component involved in the currently executed control step satisfies the corresponding second state information, the monitoring module further includes: If at the end of the target time period, any target component involved in the control step currently being executed does not satisfy the corresponding second state information, a second alarm message is generated according to the control step currently being executed and sent to the control module, the target time period is determined according to the time of executing the current control step and the preset execution time, and the second alarm message is used to indicate that the nuclear power feed water pump has an execution abnormality in the control step currently being executed; Correspondingly, the control module is also used for: When the second alarm information is received, the control step currently being executed is suspended or terminated.

6. The nuclear power feed water pump control system according to any one of claims 1 to 5, characterized in that: When executing the speed increase control sequence, the control module includes: When it is detected that the shaft vibration of the nuclear power feed water pump is greater than or equal to the shaft vibration threshold, suspending the execution of the speed increase control sequence and adjusting the speed of the nuclear power feed water pump to a preset speed; After controlling the nuclear power feed water pump to run for a preset time based on the preset speed, the speed increase control sequence continues to be executed.

7. The nuclear power feed water pump control system according to claim 6, characterized in that: The control module is also used for: After continuing to execute the speed increase control sequence, if it is detected again that the shaft vibration is greater than or equal to the shaft vibration threshold, returning to the step of pausing execution of the speed increase control sequence; When it is determined that the number of times the execution of the speed increase control sequence is suspended does not reach the number threshold, the step of adjusting the rotation speed of the nuclear power feed water pump to the preset rotation speed until the execution of the speed increase control sequence is continued; When it is determined that the number of times reaches the number threshold, the execution of the speed increase control sequence is terminated.

8. A nuclear power feed water pump control method, characterized in that: Applied to nuclear power feed water pump control system, including: Executing a speed increase control sequence, the speed increase control sequence comprising a speed increase control control step for starting a nuclear power feed water pump and controlling the speed of the nuclear power feed water pump to reach a target speed; During the execution of the speed increase control sequence, actual state information of the target component of the nuclear power feed water pump is obtained and displayed, wherein the target component at least includes the component involved in the control step, and the actual state information reflects the current state information of the target component; The actual status information of each of the target components is monitored, and when the actual status information is detected to be abnormal, first alarm information is generated based on the abnormal actual status information, wherein the first alarm information is used to indicate that the target component has an abnormal status.

9. An electronic device 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, the method according to claim 8 is implemented.

10. A computer program product, characterized in that When the computer program product runs on an electronic device, the electronic device is caused to execute the method as claimed in claim 8.

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