Nuclear power plant unit operation control method and device, electronic equipment and storage medium

Abstract

The embodiment of the invention provides a nuclear power plant unit operation control method and device, electronic equipment and a storage medium, and belongs to the technical field of nuclear power plant safety. The method comprises the following steps: firstly, acquiring working condition information of the nuclear power plant unit; when the working condition information is responded to be a fault operation working condition, equipment fault information is obtained, then a unit fault type is determined according to the equipment fault information and preset fault correlation reference information, then a target control strategy is determined according to the unit fault type, and then the target control strategy is executed. The equipment fault information is updated, and finally, according to the updated equipment fault information and a preset normal operation recovery condition, it is determined that the nuclear power plant unit is controlled according to a preset normal operation regulation. The embodiment of the invention can reduce the fault operation time of the unit.

Description

Technical Field

[0001] The present application relates to the field of nuclear power plant safety technology, and in particular to a method and device for controlling the operation of a nuclear power plant unit, electronic equipment, and storage medium. Background Art

[0002] In the field of nuclear power plant safety technology, nuclear power plants handle normal operation events according to normal operation procedures and handle related accident events according to accident operation procedures. However, nuclear power plants may experience equipment or functional failures that cause the unit to deviate from normal operation. This state is called unit fault operation condition. At this time, the nuclear power plant has not yet reached the conditions for automatically triggering accident operation procedures, but it is also impossible to ensure the long-term stable operation of the unit by running normal operation procedures.

[0003] In the related art, when faced with a unit fault, the unit will be backed off to manually reduce the power or jump the reactor. However, this solution can easily lead to the unit backing off too far, increasing the time it takes for the unit to return to normal operation after the fault is resolved.

[0004] Therefore, how to reduce the unit failure operation time has become an urgent problem to be solved. Summary of the invention

[0005] The main purpose of the embodiments of the present application is to provide a nuclear power plant unit operation control method and device, electronic equipment and storage medium, aiming to reduce the unit failure operation time.

[0006] To achieve the above-mentioned purpose, a first aspect of an embodiment of the present application provides a method for controlling operation of a nuclear power plant unit, the method comprising:

[0007] Obtaining operating condition information of the nuclear power plant unit;

[0008] In response to the operating condition information being a faulty operating condition, acquiring equipment fault information;

[0009] Determining the unit fault type according to the equipment fault information and preset fault association reference information;

[0010] Determining a target control strategy according to the type of unit failure;

[0011] Executing the target control strategy and updating the device fault information;

[0012] Based on the updated equipment fault information and the preset conditions for resuming normal operation, it is determined that the nuclear power plant unit is controlled according to the preset normal operation procedures.

[0013] In some embodiments, determining the unit fault type according to the device fault information and preset fault association reference information includes:

[0014] Performing fault type analysis on the equipment fault information based on the fault association reference information to obtain a fault risk analysis result;

[0015] In response to the fault risk analysis result indicating that the nuclear power plant unit has at least one of a radioactive leakage risk, a heat removal function failure risk, and a circulation function failure risk, the unit fault type is determined to be a first fault type.

[0016] In some embodiments, determining a target control strategy according to the unit fault type includes:

[0017] In response to the unit fault type being the first fault type, determining an emergency fault operating procedure corresponding to the first fault type from preset accident operating procedures;

[0018] The target control strategy is determined according to the emergency fault operation procedure and a preset nuclear reaction power threshold.

[0019] In some embodiments, determining the unit fault type according to the device fault information and preset fault association reference information includes:

[0020] In response to the fault risk analysis result indicating that the nuclear power plant unit does not have the risk of radioactive leakage, the risk of heat removal function failure, and the risk of circulation function failure, a stability assessment is performed on the equipment fault information based on the fault-related reference information to obtain a stability assessment result;

[0021] In response to the stability assessment result indicating that the nuclear power plant unit interrupts stable operation of the unit within a preset time period, or an abnormality occurs when the nuclear power plant unit enters a fallback mode, determining the unit fault type as a second fault type;

[0022] or,

[0023] In response to the stability assessment result indicating that the nuclear power plant unit maintains stable operation within a preset time period, or the nuclear power plant unit normally enters a fallback mode, it is determined that the unit fault type is a third fault type.

[0024] In some embodiments, the nuclear power plant unit includes a primary cooling system, a residual heat removal system, a reactor and a control rod, wherein the control rod is used to be inserted into the reactor; and determining the target control strategy according to the fault type of the unit includes:

[0025] In response to the unit fault type being the second fault type, determining a movement control strategy of the control rods according to a preset target power and a preset power threshold of the reactor;

[0026] Determining the heat removal start-up condition of the waste heat removal system according to the preset boric acid concentration, preset temperature data and preset pressure data of the primary cooling system;

[0027] The target control strategy is determined according to the movement control strategy and the heat removal starting condition.

[0028] In some embodiments, executing the target control strategy and updating the device fault information includes:

[0029] obtaining an initial power of the reactor;

[0030] moving the control rod according to the preset power threshold, the initial power and the movement control strategy until the initial power reaches the preset target power;

[0031] Performing boronization, temperature reduction and pressure reduction operations on the primary cooling system, and updating the equipment fault information;

[0032] When the current boric acid concentration, current temperature data and current pressure data of the primary cooling system meet the heat removal start condition, it is determined to start the waste heat removal system.

[0033] In some embodiments, the moving the control rod according to the preset power threshold, the initial power and the movement control strategy until the initial power reaches the preset target power comprises:

[0034] When the initial power is greater than the preset power threshold, an automatic load reduction operation is performed until the initial power reaches the preset power threshold, and the device fault information is updated;

[0035] When the initial power is less than or equal to the preset power threshold, the control rod is moved according to the movement control strategy until the initial power reaches the preset target power.

[0036] In some embodiments, before executing the target control strategy and updating the device fault information, the method further includes:

[0037] Generate an early warning display interface according to the unit fault type, the equipment fault information and the target control strategy;

[0038] In response to a confirmation operation performed by a target object on the early warning display interface, it is determined to execute the target control strategy; wherein the target object is an operator of the nuclear power plant unit.

[0039] In some embodiments, before determining the unit fault type according to the equipment fault information and preset fault association reference information, the method includes:

[0040] Obtaining equipment function failure information of the nuclear power plant unit;

[0041] Performing system failure risk analysis on the equipment function failure information to obtain subsystem level risk information;

[0042] Performing unit failure risk analysis according to the subsystem level risk information to obtain unit level risk information;

[0043] The fault-related reference information is determined according to the equipment function fault information, the subsystem level risk information and the unit level risk information.

[0044] In some embodiments, after acquiring the operating condition information of the nuclear power plant unit, the method further includes:

[0045] In response to the operating condition information being a normal operating condition, controlling the nuclear power plant unit according to the normal operating procedure;

[0046] or,

[0047] In response to the operating condition information being an accident operating condition, the nuclear power plant unit is controlled according to a preset accident operating procedure.

[0048] To achieve the above-mentioned purpose, a second aspect of an embodiment of the present application provides a nuclear power plant unit operation control device, the device comprising:

[0049] A first acquisition module, used to acquire the operating condition information of the nuclear power plant unit;

[0050] A second acquisition module, configured to acquire equipment fault information in response to the operating condition information being a faulty operating condition;

[0051] A fault type determination module, used to determine the unit fault type according to the equipment fault information and preset fault association reference information;

[0052] A control strategy formulation module, used to determine a target control strategy according to the type of unit failure;

[0053] A control strategy execution module, used to execute the target control strategy and update the device fault information;

[0054] The normal operation recovery module is used to determine, based on the updated equipment fault information and the preset normal operation recovery conditions, to control the nuclear power plant unit according to the preset normal operation procedures.

[0055] To achieve the above objectives, a third aspect of an embodiment of the present application proposes an electronic device, which includes a memory and a processor, wherein the memory stores a computer program, and when the processor executes the computer program, the method described in the first aspect is implemented.

[0056] To achieve the above-mentioned purpose, the fourth aspect of an embodiment of the present application proposes 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 method described in the first aspect is implemented.

[0057] The nuclear power plant unit operation control method and device, electronic equipment and storage medium proposed in this application implement targeted control strategies by accurately obtaining the operating conditions and equipment fault information of the nuclear power plant unit, so as to help the unit quickly return to normal operation. First, by obtaining the operating condition information of the unit, when it is confirmed that it has entered the fault operating condition, the specific fault type is further analyzed through the equipment fault information and the preset fault association reference information. Then, the corresponding target control strategy is formulated according to different fault types. Then, the control strategy is executed, and the equipment fault information is dynamically responded and continuously updated, so that the strategy can be adjusted according to the progress of fault recovery to avoid unnecessary operation delays. Finally, according to the change of fault information, when it is determined that the unit reaches the preset recovery condition, the unit can be returned to the normal operating condition and operated according to the normal operating procedures. This scheme effectively reduces the problem of excessive retreat caused by improper handling of accident operation procedures through faster fault location and adjustment strategies, reduces the frequency of unit shutdown transients, and thus reduces the difficulty of the unit returning to normal operation, thereby reducing the fault operation time of the unit. BRIEF DESCRIPTION OF THE DRAWINGS

[0058] Figure 1 is a flow chart of a method for controlling operation of a nuclear power plant unit provided in an embodiment of the present application;

[0059] Figure 2 is another flow chart of the nuclear power plant unit operation control method provided in an embodiment of the present application;

[0060] Figure 3 yes Figure 1 Flow chart of step S103 in FIG.

[0061] Figure 4 yes Figure 1 Flow chart of step S104 in FIG.

[0062] Figure 5 yes Figure 1 Another flowchart of step S104 in;

[0063] Figure 6is another flow chart of the nuclear power plant unit operation control method provided in an embodiment of the present application;

[0064] Figure 7 This is a schematic diagram of an early warning display interface provided by an embodiment of the present application;

[0065] Figure 8 This is another schematic diagram of a warning display interface provided in an embodiment of the present application;

[0066] Fig. 9 This is another schematic diagram of a warning display interface provided in an embodiment of the present application;

[0067] Fig.10 yes Figure 1 Flow chart of step S105 in FIG.

[0068] Fig.11 It is a structural schematic diagram of a nuclear power plant unit operation control device provided in an embodiment of the present application;

[0069] Fig.12 It is a schematic diagram of the hardware structure of the electronic device provided in the embodiment of the present application. DETAILED DESCRIPTION

[0070] In order to make the purpose, technical solution and advantages of the present application more clearly understood, the present application is further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application and are not used to limit the present application.

[0071] It should be noted that, although the functional modules are divided in the device schematic diagram and the 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 above drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence.

[0072] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as those commonly understood by those skilled in the art to which this application belongs. The terms used herein are only for the purpose of describing the embodiments of this application and are not intended to limit this application.

[0073] First, some nouns involved in this application are analyzed:

[0074] Unit: In the field of nuclear power plants, a unit is a basic power generation unit consisting of a reactor and its supporting steam turbine generator set as well as the systems and facilities required to maintain their normal operation and ensure safety. It usually includes a nuclear reactor, a steam generator, a primary cooling system, and a waste heat removal system.

[0075] Backoff mode: Backoff mode refers to an emergency operation to quickly terminate the nuclear chain reaction in a nuclear reactor. It is usually initiated automatically or manually when the reactor is potentially dangerous or exceeds normal operating parameters. Backoff mode involves quickly inserting all control rods into the reactor core to stop the nuclear fission reaction and ensure the safety of the nuclear power plant.

[0076] Operating Procedures: Written documents used to guide nuclear power plant operators to perform various operations and monitoring on unit systems, and to handle system and equipment failures and various accidents. They consist of overall operating procedures, system operating procedures, refueling and overhaul operating procedures, system alarm manuals, fault handling procedures, accident handling procedures, administrative isolation procedures, and periodic test procedures.

[0077] In the field of nuclear power plant safety technology, operating procedures are guidance documents for operating personnel to operate power plant systems or equipment. Regardless of whether the nuclear power plant is in normal operation or accident state, there are clear operating documents to guide operators to control the unit and ensure the safety of the nuclear power plant. According to the different operating conditions of the nuclear power plant, the digital operating document system currently used can be divided into normal operating procedures and accident operating procedures according to the corresponding operating procedures. Among them, the normal operating procedures are used to guide the operation of the unit during steady-state operation, startup, and shutdown, as well as to handle some normal operating transient events. Normal operating procedures include normal start and shutdown procedures for the unit, alarm cards, system fault operating procedures, and abnormal operation procedures for the unit. Accident operating procedures are used to handle expected operating events, design basis operating condition accidents, and design extension operating condition accidents that cannot be handled by normal operating procedures.

[0078] However, in nuclear power plants, equipment or functional failures may cause the unit to deviate from normal operation. At this time, the unit has not tripped and the dedicated protection equipment has not been activated. This state is called the unit fault operation condition. At this time, in the nuclear power plant, the reactor protection and dedicated safety functions may not be automatically triggered, so the conditions for automatically triggering the accident operation procedures have not been met, but it may not be possible to ensure the long-term stable operation of the unit by running the normal operation procedures.

[0079] In the relevant technologies of the third generation nuclear power plant, when there is a faulty operating condition in the unit equipment of the nuclear power plant, there are two existing solutions. In the first solution, the normal operating procedures of the third generation nuclear power plant include general operating procedures (General Operating Procedures, GOP), abnormal operating procedures (Abnormal Operating Procedures, AOP), system operating procedures (System Operating Procedures, SOP), and alarm response procedures (Alarm Response Procedures, ARP). The accident operating procedures include emergency operating procedures (Emergency Operating Procedures, EOP), 72-hour post-accident operating procedures, and severe accident management guidelines (Severe Accident Management Guidelines, SAMG), etc. In the early stage of an event or accident, when the unit has not tripped and the dedicated protection equipment has not been activated, the nuclear power plant is in a faulty operating condition. At this time, it is handled through the general operating procedures or abnormal operating procedures, but as the severity of the fault and the degree of impact on the unit further deepen, the unit trips or the dedicated protection equipment is triggered to automatically start, and the accident operation procedures are transferred to be processed.

[0080] In the process of executing the abnormal operation procedure (AOP), the specific operation of the system equipment is completed by calling the system operation procedure (SOP), and the unit retreat operation is completed by calling the general operation procedure (GOP). In this way, all accident conditions, fault conditions and disasters that have not jumped the reactor are handled in the abnormal operation procedure (AOP). The range of conditions covered by the abnormal operation procedure (AOP) is relatively wide, which leads to a large AOP file structure. In addition, during the execution of the procedure, the general operation procedure (GOP) and the system operation procedure (SOP) are frequently called each other, which increases the human risk.

[0081] In the second scheme, the normal operating procedures of the third-generation nuclear power plant include general operating procedures (GOP), special operating guidelines (POR), system operating procedures (SOP), and alarm response procedures (ARP). Accident operating procedures include emergency operating procedures (EOP) and severe accident management guidelines (SAMG). In this scheme, the emergency operating procedures include both accident and event handling when the unit has not tripped and the dedicated protection equipment has not been activated, and the unit evacuation when the normal operating function of the unit is unavailable. Therefore, this scheme manages most of the fault operating conditions through the accident operating procedures. When the operating personnel cannot maintain the stable operation of the unit through the normal operating function of the unit, the accident operating procedures are called through the technical specification or technical requirements manual to control the unit. In the accident operation procedures, the accident operation procedures can only be terminated and returned to normal operation when the unit status is restored to a safe and stable state and the reactor thermal hydraulic parameters and nuclear parameters meet the requirements of the technical specifications or technical requirements manual. Moreover, the accident handling process of the accident operation procedures is relatively complicated and cumbersome. Manual reactor tripping is required when performing power reduction operations, which increases the shutdown transient. In addition, the retreat state of the accident operation is too deep, which increases the recovery time of the unit after the fault handling is completed.

[0082] Therefore, how to reduce the unit failure operation time has become an urgent problem to be solved.

[0083] Based on this, the embodiments of the present application provide a nuclear power plant unit operation control method and device, electronic equipment and storage medium, aiming to reduce the unit fault operation time.

[0084] The nuclear power plant unit operation control method and device, electronic device and storage medium provided in the embodiments of the present application are specifically described through the following embodiments. First, the nuclear power plant unit operation control method in the embodiments of the present application is described.

[0085] The nuclear power plant unit operation control method provided in the embodiment of the present application relates to the field of nuclear power plant safety technology. The nuclear power plant unit operation control method provided in the embodiment of the present application can be applied to a terminal, can also be applied to a server side, and can also be software running in a terminal or a server side. In some embodiments, the terminal can be a smart phone, a tablet computer, a laptop computer, a desktop computer, etc.; the server side can be configured as an independent physical server, or a server cluster or a distributed system composed of multiple physical servers, and can also be configured as a cloud server that provides basic cloud computing services such as cloud services, cloud databases, cloud computing, cloud functions, cloud storage, network services, cloud communications, middleware services, domain name services, security services, CDN, and big data and artificial intelligence platforms; the software can be an application that implements the nuclear power plant unit operation control method, etc., but is not limited to the above forms.

[0086] The present application can be used in many general or special computer system environments or configurations. For example: 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, distributed computing environments including any of the above systems or devices, etc. The present 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. The present application can also be practiced in distributed computing environments, in which tasks are performed by remote processing devices connected through a communication network. In a distributed computing environment, program modules can be located in local and remote computer storage media including storage devices.

[0087] Figure 1 is an optional flow chart of the nuclear power plant unit operation control method provided in the embodiment of the present application, Figure 1 The method may include but is not limited to steps S101 to S106.

[0088] Step S101, obtaining operating information of nuclear power plant units.

[0089] Step S102, in response to the operating condition information being a faulty operating condition, obtaining equipment fault information.

[0090] Step S103, determining the unit fault type according to the equipment fault information and preset fault association reference information.

[0091] Step S104, determining a target control strategy according to the type of unit failure.

[0092] Step S105, executing the target control strategy and updating the equipment fault information.

[0093] Step S106, based on the updated equipment fault information and the preset normal operation recovery conditions, determine to control the nuclear power plant units according to the preset normal operation procedures.

[0094] Steps S101 to S106 shown in the embodiment of the present application implement targeted control strategies to help the unit quickly return to normal operating conditions by accurately acquiring the operating conditions and equipment fault information of the nuclear power plant unit. First, by acquiring the operating condition information of the unit, when it is confirmed that it has entered the fault operating condition, the specific fault type is further analyzed through the equipment fault information and the preset fault association reference information. Then, a corresponding target control strategy is formulated according to different fault types. Then, the control strategy is executed, and the equipment fault information is dynamically responded and continuously updated, so that the strategy can be adjusted according to the progress of fault recovery to avoid unnecessary operation delays. Finally, according to the changes in the fault information, when it is determined that the unit has reached the preset recovery conditions, the unit can be returned to the normal operating condition and operated according to the normal operating procedures. This scheme effectively reduces the problem of excessive retreat caused by improper handling of accident operating procedures through faster fault location and adjustment strategies, reduces the frequency of unit shutdown transients, and thus reduces the difficulty of the unit returning to normal operation, thereby reducing the fault operation time of the unit.

[0095] In step S101 of some embodiments, the operating condition information may be normal operating conditions, accident operating conditions, and fault operating conditions. Specifically, normal operating conditions refer to that all systems and equipment operate in accordance with normal design specifications, relevant parameters are controlled within a safe range, and daily operations such as steady-state operation, startup, and shutdown of the reactor all belong to normal operating conditions. Accident operating conditions refer to accident operating conditions when a design basis accident or a non-design basis accident occurs in a nuclear power plant, or when equipment fails, the reactor power is out of control, or serious problems occur in system operation. Fault operating conditions refer to the deviation of a nuclear power plant unit from a normal operating state due to equipment or function failure, but it has not yet developed to the severity of an accident. At this time, the reactor protection and safety functions may not be automatically triggered, and the unit can continue to operate.

[0096] Different operating procedures need to be selected for different operating conditions of nuclear power plants. In some embodiments, after step S101, the nuclear power plant unit operation control method provided by the present application may also include: in response to the operating condition information being a normal operating condition, the nuclear power plant unit is controlled according to the normal operating procedure. Or, in response to the operating condition information being an accident operating condition, the nuclear power plant unit is controlled according to the preset accident operating procedure. It can be understood that the above-mentioned normal operating procedures and accident operating procedures are pre-written before the nuclear power plant is put into operation, and can be directly imported and called in actual application scenarios.

[0097] In step S102 of some embodiments, the faulty operation condition refers to a situation where a nuclear power plant has an equipment or functional failure that causes the unit to deviate from normal operation. Equipment failure information refers to equipment information of a nuclear power plant unit that has a fault in a faulty operation condition, as well as related information of a unit function failure, such as: loss of a main pump, abnormal boron concentration of a primary coolant, unavailability of a normal boronization function, and unavailability of a primary coolant chemical and volume control system (RCV) high pressure discharge function. The specific content that may be included in the equipment failure information may vary according to the structure of the nuclear power plant, and the embodiments of the present application do not strictly limit this.

[0098] It should be noted that after confirming that the nuclear power plant unit has entered a faulty operating condition, the embodiment of the present application needs to further classify the faulty operating condition in which it is located. This process needs to consider the impact of equipment fault information on the operation of the unit. In the embodiment of the present application, the type of faulty operating condition is the unit fault type. Fault-related reference information refers to the impact and risk on the operating status and safety of the unit when a specific equipment fails, including equipment function failure information, subsystem-level risk information, and unit-level risk information. The fault-related reference information can be obtained by relying on manual experience or in advance through a pre-trained artificial intelligence model.

[0099] Next, the determination of fault-related reference information will be described in detail in conjunction with the following embodiments. Figure 2 In some embodiments, before step S103, the nuclear power plant unit control operation method provided in the embodiment of the present application may include but is not limited to steps S201 to S204:

[0100] Step S201, obtaining equipment function failure information of a nuclear power plant unit.

[0101] Step S202: Perform system failure risk analysis on the equipment function failure information to obtain subsystem level risk information.

[0102] Step S203, performing unit failure risk analysis according to the subsystem level risk information to obtain unit level risk information.

[0103] Step S204, determining fault-related reference information according to the equipment function fault information, the subsystem level risk information and the unit level risk information.

[0104] In step S201 of some embodiments, the equipment function failure information is a faulty equipment or functional failure that may occur in a nuclear power plant unit. Usually, the equipment to be analyzed is first selected in the unit, such as: main pump, primary coolant chemistry and volume control system, and spent fuel pool cooling pump, etc. Then, a fault analysis is performed on these equipment to determine the possibility of failure of each equipment to be analyzed, such as: loss of one main pump, loss of two main pumps, unavailability of the high-pressure discharge function of the primary coolant chemistry and volume control system, failure and shutdown of the spent fuel pool cooling pump, and unavailability of the normal boronization function. The specific content of the equipment function failure information is not strictly limited in the embodiments of the present application. The equipment of the standby unit can be selected from the nuclear power plant unit based on experience feedback or the specific needs of the nuclear power plant.

[0105] In step S202 of some embodiments, for each device function failure information, its impact on the function of the system is first analyzed, and the risk information obtained is the subsystem level risk information. For example, the impact of losing a main pump on the system is that the circulation flow of the primary coolant is reduced.

[0106] In step S203 of some embodiments, after determining the system level impact corresponding to each device function failure information, the impact of the failure on the normal operation of the unit and the possible risks are analyzed according to the subsystem level risk information, and the obtained risk information is the unit level risk information.

[0107] In step S204 of some embodiments, the equipment function failure information, subsystem level risk information and unit level risk information are matched one by one, and then integrated into failure association reference information and stored in a database, which can be stored in a table form. In some embodiments, the failure association reference information can be as shown in Table 1.

[0108]

[0109] Table 1

[0110] Steps S201 to S204 shown in the embodiment of the present application can identify and respond to faults more quickly through systematic fault information acquisition and risk analysis, thereby significantly improving the safety and reliability of nuclear power plants.

[0111] In step S103 of some embodiments, the unit fault type includes a first fault type, a second fault type, and a third fault type. Figure 3 Step S103 may include but is not limited to steps S301 to S302:

[0112] Step S301: parse the equipment fault information according to the fault type based on the fault association reference information to obtain a fault risk analysis result.

[0113] Step S302, in response to the fault risk analysis result indicating that the nuclear power plant unit has at least one of the risk of radioactive leakage, the risk of heat removal function failure, and the risk of circulation function failure, the unit fault type is determined to be a first fault type.

[0114] In step S301 of some embodiments, the equipment fault information is compared and queried according to the fault-related reference information to obtain subsystem-level risk information and unit-level risk information corresponding to the equipment fault information, that is, the fault risk analysis result.

[0115] In step S302 of some embodiments, the first fault type is a fault operating condition with a relatively high degree of severity. When the unit fault type is determined to be the first fault type condition, it is necessary to introduce the accident operation procedure for processing. It is understandable that the risk of radioactive leakage refers to the risk of possible radioactive consequences, which may be caused by leakage in a loop or other pipelines containing coolant. The risk of heat removal function failure refers to the risk that the residual heat removal system fails to operate, or the residual heat removal system is in operation but the unit equipment fails, resulting in the system being unable to meet the residual heat removal requirements. The risk of circulation function failure refers to the risk of loss of forced circulation in the primary loop system, usually a situation where all main pumps are shut down but the unit does not automatically trip the reactor.

[0116] In other embodiments, in response to the fault risk analysis result indicating that the nuclear power plant unit does not have the risk of radioactive leakage, the risk of heat removal function failure, and the risk of circulation function failure, a stability assessment is performed on the equipment fault information based on the fault-related reference information to obtain a stability assessment result. Specifically, the stability assessment includes determining whether the unit can maintain stable operation within a preset time under the fault operating condition, and whether the normal operating function can be used to retreat. It should be noted that in this embodiment, the preset time refers to the length of time required for the equipment to detect a fault and complete the repair of the fault.

[0117] In some embodiments, in response to the stability assessment result indicating that the nuclear power plant unit interrupts stable operation of the unit within a preset time, or an abnormality occurs when the nuclear power plant unit enters the retreat mode, the unit fault type is determined to be a second fault type. Specifically, the second fault type is a faulty operating condition that poses a moderate risk to the safe operation of the unit. This fault type indicates that some key functions of the unit are damaged, but will not immediately lead to serious safety consequences.

[0118] In other embodiments, in response to the stability assessment result indicating that the nuclear power plant unit maintains stable operation within a preset time, or the nuclear power plant unit enters the retreat mode normally, the unit fault type is determined to be a third fault type. Specifically, the third fault type is a fault operating condition with a relatively low impact severity, which can maintain stable operation of the unit for a certain period of time.

[0119] Steps S301 to S302 shown in the embodiment of the present application, by classifying and processing faulty operating conditions, are conducive to more efficient resource allocation in nuclear power plants, and can also provide a basis for subsequent formulation of corresponding response strategies.

[0120] In some steps S104, different control strategies are formulated according to different fault operating conditions. Figure 4 Step S104 may include but is not limited to steps S401 to S402:

[0121] Step S401, in response to the unit fault type being a first fault type, determining an emergency fault operating procedure corresponding to the first fault type from preset accident operating procedures.

[0122] Step S402, determining a target control strategy according to the emergency fault operation procedure and a preset nuclear reaction power threshold.

[0123] In step S401 of some embodiments, the fault operating condition of the first fault type needs to be introduced into the accident operating procedure for processing, and the emergency fault operating procedure corresponding to the fault type needs to be quickly retrieved and confirmed from the preset accident operating procedure.

[0124] In step S402 of some embodiments, the emergency fault operation procedure reflects that the unit needs to perform a retreat operation, and the target control strategy is: when the current power of the reactor is greater than the nuclear reaction power threshold, perform an automatic load reduction operation. When the current power of the reactor reaches the nuclear reaction power threshold, perform a manual shutdown operation, and then perform boronization, cooling or pressure reduction operations until the unit enters the retreat mode required by the operation procedure. Among them, the nuclear reaction power threshold can be 10% of the full power of the reactor, or other values, but is not limited to this.

[0125] In other embodiments, the emergency fault operating procedures reflect that the unit does not need to be evacuated, and the target control strategy is to maintain the stability of the unit within the accident operation range while the operating personnel handle the fault.

[0126] Steps S401 to S402 shown in the embodiment of the present application improve the efficiency of responding to serious faults, enhance the systematic nature of fault handling, and ensure the safe operation of the nuclear power plant.

[0127] See also Figure 5In some embodiments, a nuclear power plant unit includes a primary cooling system, a residual heat removal system, a reactor and a control rod. The control rod is used to be inserted into the reactor. The control rod is usually made of some materials that can absorb neutrons. By changing the position of the control rod in the reactor, the power and temperature of the reactor can be adjusted. When the type of the fault operating condition is the second fault type, it is necessary to introduce an abnormal operation procedure, and the unit needs to perform a retreat operation to exit power operation. Specifically, step S104 may also include but is not limited to steps S501 to S503:

[0128] Step S501, in response to the unit fault type being the second fault type, determining a control rod movement control strategy based on a preset target power and a preset power threshold of the reactor.

[0129] Step S502, determining the heat removal start-up conditions of the waste heat removal system according to the preset boric acid concentration, preset temperature data and preset pressure data of the primary cooling system.

[0130] Step S503: determining a target control strategy according to the movement control strategy and the heat removal start condition.

[0131] In step S501 of some embodiments, the preset target power is a power value that can reflect the power value of the reactor exiting power operation, and the preset power threshold is an intermediate power value that needs to be reached to perform the automatic load reduction operation, which can be set to 10% of the full power of the reactor. The mobile control strategy can be: when the current power of the reactor is greater than the preset power threshold, the unit performs an automatic load reduction operation, including automatically adjusting the position of the control rod. When the current power of the reactor is equal to the preset power threshold, the manual rod insertion operation begins.

[0132] In step S502 of some embodiments, the heat removal start-up condition is a judgment basis for determining whether to start the waste heat removal system, the preset boric acid concentration may be a preset concentration range, and the preset temperature data may be a preset temperature range. Exemplarily, the heat removal start-up condition may include: the boric acid concentration in the primary cooling system is within the preset boric acid concentration range, the average temperature value of the primary cooling system is within the preset temperature data, and the pressure of the primary cooling system is below the preset pressure data.

[0133] In step S503 of some embodiments, the target control strategy is set as follows: first execute the mobile control strategy, then execute the operations of boronization, temperature adjustment and pressure adjustment, so that the relevant parameters of the unit meet the heat removal start-up conditions, thereby starting the waste heat removal system. If during the period of automatically reducing the load and executing the operations of boronization, temperature adjustment and pressure adjustment, the equipment or functional failure is repaired and put into operation, or the waste heat removal system is successfully put into operation, then return to the normal operation procedure.

[0134] In the steps S501 to S503 shown in the embodiment of the present application, a comprehensive safety control strategy is formulated by comprehensively considering the control rod movement strategy and the startup conditions of the residual heat removal system. This method helps to improve the response capability of the nuclear power plant to faults and ensure safe operation under various fault conditions.

[0135] In some embodiments, step S104 may further include: in response to the unit fault type being the third fault type, maintaining the current operating procedure of the unit without changing the operating state of the unit.

[0136] It is understandable that by specifically classifying the fault operating conditions, the accident operation procedure is introduced for the first fault type, the abnormal operation procedure is introduced for the second fault type, and the normal operation procedure is introduced for the third fault type. The operational complexity and human risk caused by the frequent call of other procedures (such as overall operation procedures and system operation procedures) in the abnormal operation procedure (AOP) in the first existing solution are avoided. At the same time, a faster fault location and adjustment strategy is also provided, which effectively reduces the problem of excessive retreat caused by improper handling of the accident operation procedure.

[0137] It should be noted that in the embodiment of the present application, different interface types are set for different fault operating conditions, so that different warning information is displayed on the interactive interface used for early warning. The operator is required to confirm the fault based on the displayed warning information to determine the execution of the corresponding target control strategy.

[0138] Specifically, see Figure 6 In some embodiments, before step S105, the steps include but are not limited to steps S601 to S602:

[0139] Step S601, generating a warning display interface according to the unit fault type, equipment fault information and target control strategy.

[0140] Step S602: In response to a confirmation operation performed by the target object on the warning display interface, determining to execute the target control strategy.

[0141] In step S601 of some embodiments, the unit fault type, equipment fault information and target control strategy are displayed on the warning display interface, and relevant description text matching the unit fault type is added to the warning display interface. Figure 7 As shown, Figure 7It is a schematic diagram of an early warning display interface provided by an embodiment of the present application. When the unit has a low concentration of the primary coolant 18B, it belongs to the first fault type. The text information "After confirming that the primary coolant is mistakenly diluted, execute the accident operation procedure (EOP)" is added to the operation bar of the early warning display interface. In the field related to nuclear power plants, some faulty operating conditions of the first fault type need to be monitored and discovered through test procedures such as regular tests. An adaptive description of "executing the accident operation procedure" after monitoring a functional fault is added to the test procedure, such as Figure 8 As shown, Figure 8 This is another schematic diagram of an early warning display interface provided in an embodiment of the present application.

[0142] In other embodiments, when the unit has a faulty operating condition of the second fault type, a description is added to the operation bar of the warning display interface: after confirming the faulty operating condition and other conditions for entering the abnormal operating procedure, execute the abnormal operating procedure. Fig. 9 As shown, Fig. 9 It is another schematic diagram of the early warning display interface provided by the embodiment of the present application. When the unit has a low flow rate fault in the downstream main pipe, it belongs to the second fault type, and the following text information is added to the operation bar of the early warning display interface: "After checking that the RCV high-pressure downstream is unavailable, if the unit cannot stabilize in the current state or there is a demand for the primary circuit, call the abnormal operation procedure I04 (use RBS to retreat), which is applicable to modes 1, 2, 3 and mode 4 where the residual heat removal system (RIS-RHR) is not connected". Among them, mode 1 means that the reactor is in power operation and the nuclear power is greater than or equal to 2% of the full power. Mode 2 means that the reactor is in power operation and the nuclear power is less than 2% of the full power. Mode 3 means that the reactor is in a subcritical state, and a steam generator is used to achieve heat exchange of the primary coolant. Mode 4 means that the reactor is in a subcritical state, and the primary system is cooled by the residual heat removal system.

[0143] In step S602 of some embodiments, the target object is the operator of the nuclear power plant unit. After the operator performs a confirmation operation, the corresponding target control strategy is determined to be executed on the unit. If the operator does not perform a confirmation operation, the cause of triggering the warning is found according to the information on the warning display interface.

[0144] Steps S601 to S602 shown in the embodiment of the present application, combined with the operator's confirmation operation, improve the nuclear power plant's response capability and processing efficiency to fault conditions, not only improve the safety and reliability of accident handling, but also enhance the safety assurance system of the entire nuclear power plant.

[0145] See also Fig.10 In some embodiments, step S105 may include but is not limited to steps S1001 to S1004:

[0146] Step S1001, obtaining the initial power of the reactor.

[0147] Step S1002, moving the control rod according to the preset power threshold, initial power and movement control strategy until the initial power reaches the preset target power.

[0148] Step S1003, performing boronization operation, temperature reduction operation and pressure reduction operation on the primary cooling system, and updating the equipment fault information.

[0149] Step S1004, when the current boric acid concentration, current temperature data and current pressure data of the primary cooling system meet the heat removal start condition, it is determined to start the waste heat removal system.

[0150] In step S1001 of some embodiments, the acquisition of initial power may be achieved through a monitoring and control system of a nuclear power plant, which can monitor the power level of the reactor in real time.

[0151] In step S1002 of some embodiments, if the initial power is greater than the preset power threshold, the automatic load reduction operation is performed until the initial power reaches the preset power threshold, and the equipment fault information is updated. If during this period, the equipment or functional fault has been repaired and put into operation, it directly returns to the normal operating condition and operates the unit according to the normal operating procedures.

[0152] If the initial power is less than or equal to the preset power threshold, the control rod is moved according to the movement control strategy, that is, the operation of manually inserting the control rod is performed until the initial power reaches the preset target power.

[0153] In step S1003 of some embodiments, if the equipment or functional failure has been repaired and put into operation during the boronization operation, temperature reduction operation and pressure reduction operation of the primary cooling system, the normal operating condition is directly returned to and the unit is operated according to the normal operating procedures.

[0154] In step S1004 of some embodiments, the specific content of the heat removal start-up condition has been described in detail in the relevant embodiments of step S502, and will not be repeated here. When the current boric acid concentration, current temperature data and current pressure data of the primary cooling system meet the heat removal start-up condition, the waste heat removal system is started. If the waste heat removal system is successfully put into operation, it returns to the normal operating condition and operates the unit according to the normal operating procedures.

[0155] Steps S1001 to S1004 shown in the embodiment of the present application improve the adaptability and responsiveness of the nuclear power plant to various operating conditions by accurately controlling the reactor power and the state of the primary loop system, and enhance accident prevention and response measures, thereby ensuring the safe and stable operation of the nuclear power plant.

[0156] In step S106 of some embodiments, as the fault is repaired, the updating of the equipment fault information is a key process, which ensures that the operators of the nuclear power plant can obtain the latest and most accurate equipment status information. The relationship between the equipment fault information and the fault being repaired is dynamic and complementary, and the reduction of the equipment fault information directly reflects the progress and effect of the fault repair. When the equipment fault information is reduced to zero, it means that all equipment or functional faults have been repaired and put back into use, and the unit can be safely restored to a normal operating state. The preset condition for resuming normal operation can be that the equipment fault information is cleared.

[0157] According to the above embodiment, the conditions for resuming normal operation may also be: during the automatic load reduction period of the unit, when the equipment or functional failure has been repaired and put into use; during the temperature and pressure reduction period of the unit, when the equipment or functional failure has been repaired and put into use; the waste heat removal system is successfully put into operation.

[0158] See also Fig.11 The embodiment of the present application further provides a nuclear power plant unit operation control device, which can implement the above-mentioned nuclear power plant unit operation control method, and the device includes:

[0159] The first acquisition module is used to obtain the operating condition information of the nuclear power plant unit;

[0160] A second acquisition module, configured to acquire equipment fault information in response to the operating condition information being a faulty operating condition;

[0161] A fault type determination module is used to determine the unit fault type according to the equipment fault information and preset fault association reference information;

[0162] A control strategy formulation module is used to determine the target control strategy according to the type of unit failure;

[0163] A control strategy execution module is used to execute the target control strategy and update the equipment fault information;

[0164] The normal operation recovery module is used to determine the control of the nuclear power plant units according to the preset normal operation procedures based on the updated equipment fault information and the preset normal operation recovery conditions.

[0165] The specific implementation of the nuclear power plant unit operation control device is basically the same as the specific implementation of the above-mentioned nuclear power plant unit operation control method, and will not be repeated here.

[0166] The embodiment of the present application also provides an electronic device, the electronic device includes a memory and a processor, the memory stores a computer program, and the processor implements the above-mentioned nuclear power plant unit operation control method when executing the computer program. The electronic device can be any intelligent terminal including a tablet computer, a car computer, etc.

[0167] See also Fig.12 , Fig.12 The hardware structure of an electronic device of another embodiment is illustrated, and the electronic device includes:

[0168] The processor 1201 may be implemented by a general-purpose CPU (Central Processing Unit), a microprocessor, an 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 the present application;

[0169] The memory 1202 can be implemented in the form of a read-only memory (ROM), a static storage device, a dynamic storage device, or a random access memory (RAM). The memory 1202 can store an operating system and other application programs. When the technical solution provided in the embodiment of this specification is implemented by software or firmware, the relevant program code is stored in the memory 1202, and the processor 1201 calls and executes the nuclear power plant unit operation control method of the embodiment of this application;

[0170] Input / output interface 1203, used to implement information input and output;

[0171] The communication interface 1204 is used to realize the communication interaction between the device and other devices. The communication can be realized through a wired manner (such as USB, network cable, etc.) or a wireless manner (such as mobile network, WIFI, Bluetooth, etc.);

[0172] A bus 1205 that transmits information between various components of the device (e.g., the processor 1201, the memory 1202, the input / output interface 1203, and the communication interface 1204);

[0173] The processor 1201 , the memory 1202 , the input / output interface 1203 and the communication interface 1204 are connected to each other in communication within the device via the bus 1205 .

[0174] An embodiment of the present application also provides a computer-readable storage medium, which stores a computer program. When the computer program is executed by a processor, the above-mentioned nuclear power plant unit operation control method is implemented.

[0175] The memory, as a non-transient computer-readable storage medium, can be used to store non-transient software programs and non-transient computer executable programs. In addition, the memory may include a high-speed random access memory, and may also include a non-transient memory, such as at least one disk storage device, a flash memory device, or other non-transient solid-state storage device. In some embodiments, the memory may optionally include a memory remotely disposed relative to the processor, and these remote memories may be connected to the processor via a network. Examples of the above-mentioned network include, but are not limited to, the Internet, an intranet, a local area network, a mobile communication network, and combinations thereof.

[0176] The nuclear power plant unit operation control method, nuclear power plant unit operation control device, electronic device and storage medium provided in the embodiment of the present application implement targeted control strategies by accurately acquiring the operating conditions and equipment fault information of the nuclear power plant unit, so as to help the unit quickly return to normal operating state. First, by acquiring the operating condition information of the unit, when it is confirmed that it has entered the fault operating condition, the specific fault type is further analyzed through the equipment fault information and the preset fault association reference information. Then, the corresponding target control strategy is formulated according to different fault types. Then, the control strategy is executed, and the equipment fault information is dynamically responded and continuously updated, so that the strategy can be adjusted according to the progress of fault recovery to avoid unnecessary operation delays. Finally, according to the change of fault information, when it is determined that the unit reaches the preset recovery condition, the unit can be returned to the normal operating condition and operated according to the normal operating procedure. The scheme effectively reduces the problem of excessive retreat caused by improper handling of accident operation procedures through faster fault location and adjustment strategies, reduces the frequency of unit shutdown transients, and thus reduces the difficulty of the unit returning to normal operation, thereby reducing the fault operation time of the unit.

[0177] The embodiments described in the embodiments of the present application are intended to more clearly illustrate the technical solutions of the embodiments of the present application and do not constitute a limitation on the technical solutions provided in the embodiments of the present application. Those skilled in the art will appreciate that with the evolution of technology and the emergence of new application scenarios, the technical solutions provided in the embodiments of the present application are also applicable to similar technical problems.

[0178] Those skilled in the art will appreciate that the technical solutions shown in the figures do not constitute a limitation on the embodiments of the present application, and may include more or fewer steps than shown in the figures, or a combination of certain steps, or different steps.

[0179] The device embodiments described above are merely illustrative, and the units described as separate components may or may not be physically separated, that is, they may be located in one place or distributed on multiple network units. Some or all of the modules may be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0180] Those skilled in the art will appreciate that all or some of the steps in the methods disclosed above, and the functional modules / units in the systems and devices may be implemented as software, firmware, hardware, or a suitable combination thereof.

[0181] The terms "first", "second", "third", "fourth", etc. (if any) in the specification of the present application and the above-mentioned drawings are used to distinguish similar objects, and are not necessarily used to describe a specific order or sequence. It should be understood that the data used in this way can be interchangeable where appropriate, so that the embodiments of the present application described herein can be implemented in an order other than those illustrated or described herein. In addition, the terms "including" and "having" and any of their variations are intended to cover non-exclusive inclusions, for example, a process, method, system, product or device comprising a series of steps or units is not necessarily limited to those steps or units clearly listed, but may include other steps or units that are not clearly listed or inherent to these processes, methods, products or devices.

[0182] It should be understood that in the present application, "at least one (item)" means one or more, and "plurality" means two or more. "And / or" is used to describe the association relationship of associated objects, indicating that three relationships may exist. For example, "A and / or B" can mean: only A exists, only B exists, and A and B exist at the same time, where A and B can be singular or plural. The character " / " generally indicates that the objects associated before and after are in an "or" relationship. "At least one of the following" or similar expressions refers to any combination of these items, including any combination of single or plural items. For example, at least one of a, b or c can mean: a, b, c, "a and b", "a and c", "b and c", or "a and b and c", where a, b, c can be single or multiple.

[0183] In the several embodiments provided in the present application, it should be understood that the disclosed devices and methods can be implemented in other ways. For example, the device embodiments described above are only schematic. For example, the division of the above 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.

[0184] The units described above 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.

[0185] In addition, each functional unit in each embodiment of the present application may be integrated into one processing unit, or each unit may exist physically separately, or two or more units may be integrated into one unit. The above-mentioned integrated unit may be implemented in the form of hardware or in the form of software functional units.

[0186] 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 technical solution of the present application, 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, and the computer software product is stored in a storage medium, including multiple instructions to enable a computer device (which can be a personal computer, server, or network device, etc.) to execute all or part of the steps of the methods of various embodiments of the present application. The aforementioned storage medium includes: U disk, mobile hard disk, read-only memory (Read-Only Memory, referred to as ROM), random access memory (Random Access Memory, referred to as RAM), disk or optical disk and other media that can store programs.

[0187] The preferred embodiments of the present invention are described above with reference to the accompanying drawings, but the scope of the rights of the present invention is not limited thereto. Any modification, equivalent substitution and improvement made by a person skilled in the art without departing from the scope and essence of the present invention should be within the scope of the rights of the present invention.

Claims

1. A method for controlling the operation of a nuclear power plant unit, characterized in that: The method comprises: Obtaining operating condition information of the nuclear power plant unit; In response to the operating condition information being a faulty operating condition, acquiring equipment fault information; Determining the unit fault type according to the equipment fault information and preset fault association reference information; Determining a target control strategy according to the type of unit failure; Executing the target control strategy and updating the device fault information; Based on the updated equipment fault information and the preset conditions for resuming normal operation, it is determined that the nuclear power plant unit is controlled according to the preset normal operation procedures.

2. The method according to claim 1, characterized in that The determining the unit fault type according to the equipment fault information and preset fault association reference information includes: Performing fault type analysis on the equipment fault information based on the fault association reference information to obtain a fault risk analysis result; In response to the fault risk analysis result indicating that the nuclear power plant unit has at least one of a radioactive leakage risk, a heat removal function failure risk, and a circulation function failure risk, the unit fault type is determined to be a first fault type.

3. The method according to claim 2, characterized in that Determining the target control strategy according to the unit fault type includes: In response to the unit fault type being the first fault type, determining an emergency fault operating procedure corresponding to the first fault type from preset accident operating procedures; The target control strategy is determined according to the emergency fault operation procedure and a preset nuclear reaction power threshold.

4. The method according to claim 2, characterized in that: The determining the unit fault type according to the equipment fault information and preset fault association reference information includes: In response to the fault risk analysis result indicating that the nuclear power plant unit does not have the risk of radioactive leakage, the risk of heat removal function failure, and the risk of circulation function failure, a stability assessment is performed on the equipment fault information based on the fault-related reference information to obtain a stability assessment result; In response to the stability assessment result indicating that the nuclear power plant unit interrupts stable operation of the unit within a preset time period, or an abnormality occurs when the nuclear power plant unit enters a fallback mode, determining the unit fault type as a second fault type; or, In response to the stability assessment result indicating that the nuclear power plant unit maintains stable operation within a preset time period, or the nuclear power plant unit normally enters a fallback mode, it is determined that the unit fault type is a third fault type.

5. The method according to claim 4, characterized in that The nuclear power plant unit includes a primary cooling system, a residual heat removal system, a reactor and a control rod, wherein the control rod is used to be inserted into the reactor; and determining a target control strategy according to the fault type of the unit includes: In response to the unit fault type being the second fault type, determining a movement control strategy of the control rods according to a preset target power and a preset power threshold of the reactor; Determining the heat removal start-up condition of the waste heat removal system according to the preset boric acid concentration, preset temperature data and preset pressure data of the primary cooling system; The target control strategy is determined according to the movement control strategy and the heat removal starting condition.

6. The method according to claim 5, characterized in that The executing the target control strategy and updating the device fault information includes: obtaining an initial power of the reactor; moving the control rod according to the preset power threshold, the initial power and the movement control strategy until the initial power reaches the preset target power; Performing boronization, temperature reduction and pressure reduction operations on the primary cooling system, and updating the equipment fault information; When the current boric acid concentration, current temperature data and current pressure data of the primary cooling system meet the heat removal start condition, it is determined to start the waste heat removal system.

7. The method according to claim 6, characterized in that The moving the control rod according to the preset power threshold, the initial power and the movement control strategy until the initial power reaches the preset target power comprises: When the initial power is greater than the preset power threshold, an automatic load reduction operation is performed until the initial power reaches the preset power threshold, and the device fault information is updated; When the initial power is less than or equal to the preset power threshold, the control rod is moved according to the movement control strategy until the initial power reaches the preset target power.

8. The method according to any one of claims 1 to 7, characterized in that: Before executing the target control strategy and updating the device fault information, the method further includes: Generate an early warning display interface according to the unit fault type, the equipment fault information and the target control strategy; In response to a confirmation operation performed by a target object on the early warning display interface, it is determined to execute the target control strategy; wherein the target object is an operator of the nuclear power plant unit.

9. The method according to any one of claims 1 to 7, characterized in that: Before determining the unit fault type according to the equipment fault information and preset fault association reference information, the method includes: Obtaining equipment function failure information of the nuclear power plant unit; Performing system failure risk analysis on the equipment function failure information to obtain subsystem level risk information; Performing unit failure risk analysis according to the subsystem level risk information to obtain unit level risk information; The fault-related reference information is determined according to the equipment function fault information, the subsystem level risk information and the unit level risk information.

10. The method according to any one of claims 1 to 7, characterized in that: After obtaining the operating condition information of the nuclear power plant unit, the method further includes: In response to the operating condition information being a normal operating condition, controlling the nuclear power plant unit according to the normal operating procedure; or, In response to the operating condition information being an accident operating condition, the nuclear power plant unit is controlled according to a preset accident operating procedure.

11. A nuclear power plant unit operation control device, characterized in that: The device comprises: A first acquisition module, used to acquire the operating condition information of the nuclear power plant unit; A second acquisition module, configured to acquire equipment fault information in response to the operating condition information being a faulty operating condition; A fault type determination module, used to determine the unit fault type according to the equipment fault information and preset fault association reference information; A control strategy formulation module, used to determine a target control strategy according to the type of unit failure; A control strategy execution module, used to execute the target control strategy and update the device fault information; The normal operation recovery module is used to determine, based on the updated equipment fault information and the preset normal operation recovery conditions, to control the nuclear power plant unit according to the preset normal operation procedures.

12. An electronic device, characterized in that: The electronic device comprises a memory and a processor, the memory stores a computer program, and the processor implements the method according to any one of claims 1 to 10 when executing the computer program.

13. A computer-readable storage medium storing a computer program, characterized in that: When the computer program is executed by a processor, the method according to any one of claims 1 to 10 is implemented.

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