Nuclear power plant abnormal response management system and method in heap mode

Abstract

The invention discloses a nuclear power plant abnormal response management system and method in a heap mode, and relates to the technical field of nuclear power plant daily maintenance, and the system comprises a resource optimization configuration module which comprises a data collection unit and a scheduling unit. The data acquisition unit is used for acquiring operation data and historical maintenance records of each reactor, and the scheduling unit is used for predicting a next maintenance time period according to information of the data acquisition unit and automatically allocating resources according to a prediction result; the maintenance module is used for managing resource scheduling of each reactor unit and implementing a maintenance strategy of the cross-reactor management module according to a result of the scheduling unit; according to the method, the problem of cross-reactor type and cross-unit resource coordination in daily management of the nuclear power plant in a group reactor mode can be solved, and through the integrated management mode, the nuclear power plant can manage resources more effectively, improve the operation efficiency, reduce potential risks and ensure safe and stable operation of the nuclear power plant.

Description

Technical Field

[0001] The present invention relates to the technical field of routine maintenance of nuclear power plants, and more specifically to an abnormal response management system and method for nuclear power plants in a cluster mode. Background Art

[0002] The abnormal response management system of a nuclear power plant in the cluster mode is a management system designed for multi-reactor nuclear power plants. It improves efficiency, safety and economy by centrally managing and coordinating the operation of multiple reactors. In the cluster mode, a nuclear power plant may contain reactors of different models and generations, which leads to complexity in resource allocation, technical support and personnel scheduling. For example, different reactors may require different maintenance strategies and spare parts, and resource sharing and optimal configuration may be difficult to achieve in actual operations. In addition, since each reactor unit may be in a different operating stage, it affects the daily maintenance of managers. Summary of the invention

[0003] In order to solve the above problems, the present invention provides an abnormal response management system and method for a nuclear power plant in a cluster mode.

[0004] The present invention provides an abnormal response management system for a nuclear power plant in a group reactor mode, which is characterized by comprising: A resource optimization configuration module, wherein the resource optimization configuration module includes a data acquisition unit and a scheduling unit, The data acquisition unit is used to collect the operating data and historical maintenance records of each reactor, and the scheduling unit is used to predict the next maintenance time period according to the information of the data acquisition unit, and automatically allocate resources according to the prediction results to meet the needs of each reactor; A cross-reactor management module and a maintenance module, wherein the cross-reactor management module is used to formulate a maintenance strategy for each reactor according to the data of the data acquisition unit and the prediction result of the scheduling unit, and transmit the maintenance strategy to the maintenance module in the next maintenance time period predicted by the scheduling unit; The maintenance module is used to manage the resource scheduling of each reactor unit and implement the maintenance strategy of the cross-reactor type management module according to the results of the scheduling unit.

[0005] Preferably, the specific working mode of the scheduling unit includes: Obtaining the operating data and historical maintenance records of each reactor according to the data acquisition unit; Obtain the most recent maintenance time and historical maintenance intervals of each reactor; Obtain the cumulative operating time of each reactor; According to the formula , calculate and obtain the average value of the historical maintenance intervals of each reactor , where n is the historical maintenance times of each reactor, is the time of the ith maintenance, It is Maintenance time of times; Obtain the difference D between the current operating time and the last maintenance time of each reactor; According to the formula , get the next maintenance time of each reactor , the next maintenance time of each reactor Transmitting to the cross-stack management module; in is the degradation rate of each reactor, is the initial performance of each reactor, is the performance threshold of each reactor.

[0006] Preferably, the resource optimization configuration module further includes an optimization unit, which is used to optimize the prediction result of the scheduling unit according to the historical records and feedback evaluation of the scheduling unit, specifically: Obtain the last actual maintenance time and historical predicted maintenance time of each reactor; The feedback error coefficient H is obtained by subtracting the historical predicted maintenance time from the last actual maintenance time of each reactor and dividing the result by the last actual maintenance time; According to the formula , obtain the optimized predicted maintenance time of each reactor ; The optimized predicted maintenance time for each reactor Transmitted to the cross-stack management module.

[0007] Preferably, the specific working mode of the cross-reacter type management module is as follows: First, the collected data of each reactor is analyzed to determine the risk importance of each reactor, and each reactor is divided into low-risk reactor equipment, medium-risk reactor equipment and high-risk reactor equipment; According to the risk importance of each reactor, a maintenance strategy is selected for each reactor. The specific maintenance strategies include: For reactor equipment with low risk, maintenance is carried out at fixed time intervals or operating cycles; For medium-risk reactor equipment, real-time monitoring of equipment status can be used to predict potential failures and perform maintenance in advance. For high-risk reactor equipment, maintenance time is determined based on the actual operating status and performance data of the equipment; For reactor equipment with low risk, the predicted next forecast time of the reactor is used as a fixed maintenance time interval for regular maintenance, and no forecast is performed at the next forecast; For medium risk reactor equipment, use As the next maintenance time; For high-risk reactor equipment, the formula Obtain maintenance time based on the actual operating status and performance data of the equipment ,Will As the next maintenance time.

[0008] Preferably, the specific working method of determining the risk importance of each reactor is as follows: Obtain the equipment unavailability U, failure consequence severity C and failure frequency F of each reactor; The product of the equipment unavailability U, failure consequence severity C and failure frequency F of each reactor is taken as the risk value L of the reactor; According to the calculated risk value L, the risk can be divided into low-risk reactor equipment, medium-risk reactor equipment and high-risk reactor equipment.

[0009] Preferably, the specific working mode of the maintenance module is as follows: Adjust the spare parts inventory resource quantity of each reaction degree to be greater than or equal to the predicted spare parts resource consumption; The maintenance module further includes a personnel allocation unit, which is used to recommend the most suitable technician according to the risk importance analyzed by the cross-reactor management module.

[0010] Preferably, the specific working mode of the personnel allocation unit is: Obtain the skill level Z of each technician; The risk matching coefficient is obtained by dividing the skill level Z of each technician by the risk value L of each reactor, and the technician with the highest risk matching coefficient is assigned to the corresponding reactor maintenance.

[0011] Preferably, the specific method of obtaining the skill level Z of each technician is: Establish detailed personal files for each technician; The skills of the technicians are evaluated to obtain the skill level Z of each technician.

[0012] Preferably, the specific working method of the maintenance module also includes: After each maintenance of each reactor, the technicians will record the maintenance content; Categorize historical problems at each reactor based on record content; Create detailed personal profiles for each technician to match them with the type of problem.

[0013] A method for managing abnormal response of a nuclear power plant in a cluster mode is also proposed, comprising the following steps: Step 1: Data collection: Use the data collection unit to collect the operating data and historical maintenance records of each reactor, and analyze the collected data, including the operating status, failure rate, maintenance history, etc. of the equipment to determine the risk level and maintenance requirements of each reactor; Step 2: Determine the time period for the next maintenance of each reactor. The cross-reactor management module formulates a maintenance strategy for each reactor based on the prediction results, taking into account the risk level and maintenance requirements of different reactors; Step 3: Automatically allocate resources based on predicted resource consumption and maintenance strategies to ensure that the needs of each reactor are met within the scheduled maintenance period. The maintenance module manages the resource scheduling of each reactor unit and performs maintenance activities according to the maintenance strategy formulated by the cross-reactor management module within the maintenance period predicted by the scheduling unit. Beneficial effects: It can solve the cross-reactor and cross-unit resource coordination problems encountered in the daily management of nuclear power plants under the cluster mode. Through this integrated management method, nuclear power plants can manage resources more effectively, improve operational efficiency, reduce potential risks, and ensure the safe and stable operation of nuclear power plants. BRIEF DESCRIPTION OF THE DRAWINGS

[0014] Figure 1 is a flow chart of the management system of the present invention; Figure 2 It is a method diagram of the present invention. DETAILED DESCRIPTION

[0015] Application scenarios: In the cluster mode, a nuclear power plant may contain reactors of different models and generations, which leads to complexity in resource allocation, technical support and personnel scheduling. For example, different reactors may require different maintenance strategies and spare parts, and resource sharing and optimal configuration may be difficult to achieve in actual operations; in addition, since each reactor unit may be in a different operating stage, it affects the daily maintenance of managers.

[0016] like Figure 1 As shown: A nuclear power plant abnormal response management system in a group reactor mode, comprising: A resource optimization configuration module, wherein the resource optimization configuration module includes a data acquisition unit and a scheduling unit, The data acquisition unit is used to collect the operating data and historical maintenance records of each reactor, and the scheduling unit is used to predict the next maintenance time period according to the information of the data acquisition unit, and automatically allocate resources according to the prediction results to meet the needs of each reactor; A cross-reactor management module and a maintenance module, wherein the cross-reactor management module is used to formulate a maintenance strategy for each reactor according to the data of the data acquisition unit and the prediction result of the scheduling unit, and transmit the maintenance strategy to the maintenance module in the next maintenance time period predicted by the scheduling unit; The maintenance module is used to manage the resource scheduling of each reactor unit and implement the maintenance strategy of the cross-reactor management module according to the results of the scheduling unit. It can solve the cross-reactor and cross-unit resource coordination problems encountered in the daily management of nuclear power plants in the cluster mode. Through this integrated management method, nuclear power plants can manage resources more effectively, improve operational efficiency, reduce potential risks, and ensure the safe and stable operation of nuclear power plants.

[0017] As an optional embodiment: the specific working mode of the scheduling unit includes: The operating data and historical maintenance records of each reactor are obtained according to the data acquisition unit; it should be noted that the operating data include key parameters such as temperature, pressure, flow rate, etc., and the historical maintenance records include information such as maintenance activities, fault records, maintenance time, and replacement parts; Obtain the most recent maintenance time and historical maintenance intervals of each reactor; Obtain the cumulative operating time of each reactor; the cumulative operating time refers to the total time from the start of the equipment operation to the current moment. This indicator reflects the actual working time of the equipment since it was put into use, including all operating cycles, regardless of whether the equipment is operating under normal load or under different working conditions; According to the formula , calculate and obtain the average value of the historical maintenance intervals of each reactor , where n is the historical maintenance times of each reactor, is the time of the ith maintenance, It is Maintenance time of times; The difference D between the current operating time and the last maintenance time of each reactor is obtained; it should be noted that the difference D is obtained by subtracting the time of the most recent maintenance from the accumulated operating time of the equipment; According to the formula , get the next maintenance time of each reactor , the next maintenance time of each reactor Transmitting to the cross-stack management module; in is the degradation rate of each reactor, is the initial performance of each reactor, It is the performance threshold of each reactor. It should be noted that the initial performance usually refers to the performance indicators of the reactor in a brand new state, such as power output, efficiency, neutron flux density, etc. These data can be obtained through the test and debugging process when the reactor is started. The initial performance can also be determined by the design parameters and data provided by the manufacturer. These data are usually based on the design and expected performance of the reactor. The performance threshold is the expected performance; The degradation rate refers to the rate at which reactor performance decreases over time, which is usually related to factors such as material aging, fuel consumption and radiation damage. Through regular monitoring and analysis of operating data, the trend of performance parameters over time can be observed, thereby estimating the degradation rate. For example, the degradation rate can be estimated by monitoring the decrease in reactor power output over time; It should also be noted that, in this embodiment, The calculation is based on the historical maintenance interval and the current operation difference to adjust the forecast time. The predicted maintenance time based on the performance degradation model combines these two factors to select the shortest time period as the next predicted maintenance time; This approach allows for a more accurate prediction of the next maintenance time, taking into account the cumulative operating time and performance degradation of the equipment. This approach is applicable when equipment performance degrades significantly over time and can better guide maintenance decisions.

[0018] As an optional embodiment: the resource optimization configuration module further includes an optimization unit, and the optimization unit is used to optimize the prediction result of the scheduling unit according to the historical records and feedback evaluation of the scheduling unit, specifically: Obtain the last actual maintenance time and historical predicted maintenance time of each reactor; The feedback error coefficient H is obtained by subtracting the historical predicted maintenance time from the last actual maintenance time of each reactor and dividing the result by the last actual maintenance time; According to the formula , obtain the optimized predicted maintenance time of each reactor ; The optimized predicted maintenance time for each reactor Transmitted to the cross-stack management module.

[0019] For example, the nuclear power plant has different types of reactors, including VVER-1000, M310 and VVER-1200 In this group reactor mode, the above method can be used to optimize the maintenance time prediction. First, the operation data and historical maintenance records of each reactor are collected, and the feedback error coefficient H is calculated. Then, the predicted maintenance time is adjusted according to the feedback error coefficient H. Finally, the adjusted parameters are used to predict the next maintenance time, and the prediction results are updated and optimized according to the effects of actual maintenance activities. With this approach, nuclear power plants can more accurately predict when maintenance will be needed, reduce the risk of unplanned downtime, and improve operational efficiency and safety.

[0020] As an optional embodiment: the specific working mode of the cross-heap type management module is as follows: First, the collected data of each reactor is analyzed to determine the risk importance of each reactor, and each reactor is divided into a low-risk reactor equipment, a medium-risk reactor equipment and a high-risk reactor equipment; it should be noted that, in this embodiment, the collected data of each reactor is obtained by the data acquisition unit, which specifically includes historical maintenance records, operation data and predicted resource consumption; According to the risk importance of each reactor, a maintenance strategy is selected for each reactor. The specific maintenance strategies include: For reactor equipment with low risk, maintenance is performed at fixed time intervals or operating cycles; this approach is simple and easy to implement, but may lead to over-maintenance or under-maintenance; For medium-risk reactor equipment, real-time monitoring of equipment status can be used to predict potential failures and perform maintenance in advance; this approach can reduce unplanned downtime and optimize maintenance plans; For high-risk reactor equipment, maintenance time is determined based on the equipment's actual operating status and performance data; this approach can maximize equipment uptime and minimize unnecessary maintenance tasks; For reactor equipment with low risk, the predicted next prediction time of the reactor is used as a fixed maintenance time interval for regular maintenance, and no prediction is performed at the next prediction; the workload of the scheduling unit can be reduced; For medium risk reactor equipment, use As the next maintenance time; it should be noted that the optimized maintenance time of each reactor can also be used ; For high-risk reactor equipment, the formula Obtain maintenance time based on the actual operating status and performance data of the equipment ,Will As the next maintenance time.

[0021] For example, a nuclear power plant has three different types of reactors A, B, and C; by analyzing the data, we find that: Reactor A has a low failure rate and low maintenance costs, so it is classified as low risk; Reactor B has a moderate failure rate and maintenance costs and is classified as medium risk; Reactor C is classified as high risk due to its older design, high failure rate and high maintenance costs; For the low-risk reactor A, we choose to perform maintenance at fixed time intervals; For the medium-risk reactor B, we use real-time monitoring of equipment status, predict potential failures through predictive analysis tools, and perform maintenance before failures occur; For high-risk reactor C, we determine maintenance time based on the actual operating status and performance data of the equipment, which may require more frequent inspections and maintenance; In this way, different daily management strategies can be implemented for different types of reactors, which not only avoids waste of manpower but also ensures maintenance efficiency.

[0022] As an optional embodiment: the specific working method of determining the risk importance of each reactor is as follows: Obtain the equipment unavailability U, failure consequence severity C and failure frequency F of each reactor; The product of the equipment unavailability U, failure consequence severity C and failure frequency F of each reactor is taken as the risk value L of the reactor; According to the calculated risk value L, the risk can be divided into low-risk reactor equipment, medium-risk reactor equipment and high-risk reactor equipment.

[0023] It should be noted that a threshold range of the risk value L can be set. If the risk value L is less than this range, it is a low risk. If the risk value L is within this threshold range, it is a medium risk. If the risk value L is greater than this threshold range, it is a high risk. The specific threshold range is set by the staff and can refer to the historical average value. It should also be noted that the equipment unavailability U reflects the impact of equipment failure on the system. It can be estimated by the equipment failure rate and maintenance time; The severity of the consequences of failure C indicates the severity of the consequences that may be caused by equipment failure, and can be scored based on the impact of equipment failure on personnel safety, environment and production; The failure frequency F is the frequency of equipment failure, which can be estimated from historical failure data; In this embodiment, the specific scoring criteria are: Equipment unavailability U: 0.00-0.10: Very high availability 0.11-0.25: High Availability 0.26-0.50: Moderate availability 0.51-0.75: Low availability 0.76-1.00: Very low availability Severity of failure consequences C: 1: Minor consequences 2: Moderate consequences 3: Serious consequences 4: Very serious consequences 5: Catastrophic consequences Failure frequency F: 1: Very low (less than 0.1 times per year) 2: Low (0.1 to 1 times per year) 3: Moderate (1 to 10 times per year) 4: High (10 to 100 times per year) 5: Very high (more than 100 times per year).

[0024] As an optional embodiment: the specific working mode of the maintenance module is as follows: Adjust the spare parts inventory resource quantity of each reaction degree to be greater than or equal to the predicted spare parts resource consumption; The maintenance module further includes a personnel allocation unit, which is used to recommend the most suitable technician according to the risk importance analyzed by the cross-reactor management module.

[0025] As an optional embodiment: the specific working mode of the personnel allocation unit is: Obtain the skill level Z of each technician; The risk matching coefficient is obtained by dividing the skill level Z of each technician by the risk value L of each reactor, and the technician with the highest risk matching coefficient is assigned to the corresponding reactor for maintenance. It should be noted that each technician can only match one reactor.

[0026] As an optional embodiment: the specific method of obtaining the skill level Z of each technician is: Establish detailed personal files for each technician; including but not limited to: Qualification certification: record the professional qualifications and certifications of technicians, such as electrician certificates, welder certificates, etc. Work experience: record the work experience of technicians, including past projects, responsibilities and achievements. Training records: record the training courses, training dates and training results attended by technicians. Evaluate the skills of the technicians to obtain the skill level Z of each technician; including: Assess the professional skills of technicians through written tests, practical skills assessments, and on-site question-and-answer assessments; Project management capability assessment: assess the technical staff's capabilities in project planning, organization and coordination, and resource management; Obtain each technician's professional skill test score U and project management ability assessment score E, design weights for the two scores, and perform weighted summation to obtain each technician's skill level Z, where the sum of the two score weights is 1. In this embodiment, they can be 0.293 and 0.707, respectively.

[0027] As an optional embodiment: the specific working mode of the maintenance module also includes: After each maintenance of each reactor, the technicians will record the maintenance content; Categorize historical problems at each reactor based on record content; Create detailed personal profiles for each technician to match them with the type of problem.

[0028] In this embodiment, specifically: Create a skills matrix that lists the names of all technicians and the key skills they possess. These skills should include but are not limited to mechanical maintenance, electrical engineering, control systems, radiation protection, etc. Use a 1 to 5 rating system to rate each technician's ability in each skill; Establish a historical problem database to record the maintenance history of each reactor, including problem type, frequency of occurrence, solution and related technicians; Based on the information in the question bank, the skills required to solve a specific problem are assessed, for example, if a problem is related to electrical systems, technicians with high electrical engineering skill scores will be given priority.

[0029] Match the technician's skill rating with the skills required for the problem and select the most suitable technician; For example, suppose a nuclear power plant has three reactors: Reactors A, B, and C. Through data analysis, it is found that Reactor A mainly has equipment failures, Reactor B has performance degradation problems, and Reactor C faces safety hazards. Based on these problems, the following steps are taken: Reactor A: Based on the type of equipment failure, select technicians with experience in mechanical failure repair to perform maintenance; Reactor B: In response to performance degradation, technicians with relevant performance evaluation and optimization experience were selected to conduct inspections and adjustments; Reactor C: For potential safety hazards, technical personnel with safety management and emergency response capabilities are deployed to conduct a comprehensive inspection.

[0030] The present invention also proposes a method for managing abnormal response of a nuclear power plant in a cluster mode, comprising the following steps: Step 1: Data collection: Use the data collection unit to collect the operating data and historical maintenance records of each reactor, and analyze the collected data, including the operating status, failure rate, maintenance history, etc. of the equipment to determine the risk level and maintenance requirements of each reactor; Step 2: Determine the time period for the next maintenance of each reactor. The cross-reactor management module formulates a maintenance strategy for each reactor based on the prediction results, taking into account the risk level and maintenance requirements of different reactors; Step 3: Automatically allocate resources based on predicted resource consumption and maintenance strategies to ensure that the needs of each reactor are met within the scheduled maintenance time period. During the maintenance time period predicted by the scheduling unit, the maintenance module manages the resource scheduling of each reactor unit and performs maintenance activities based on the maintenance strategy formulated by the cross-reactor management module.

[0031] How it works It can solve the cross-reactor and cross-unit resource coordination problems encountered in the daily management of nuclear power plants under the cluster mode. Through this integrated management method, nuclear power plants can manage resources more effectively, improve operational efficiency, reduce potential risks, and ensure the safe and stable operation of nuclear power plants.

[0032] The above are only preferred implementations of the present invention. The protection scope of the present invention is not limited to the above embodiments. All technical solutions under the concept of the present invention belong to the protection scope of the present invention. It should be pointed out that for ordinary technical staff in this technical field, some improvements and modifications without departing from the principle of the present invention should also be regarded as the protection scope of this template.

Claims

1. An abnormal response management system for a nuclear power plant in a cluster mode, characterized in that: include: A resource optimization configuration module, wherein the resource optimization configuration module includes a data acquisition unit and a scheduling unit, The data acquisition unit is used to collect the operating data and historical maintenance records of each reactor, and the scheduling unit is used to predict the next maintenance time period according to the information of the data acquisition unit, and automatically allocate resources according to the prediction results to meet the needs of each reactor; A cross-reactor management module and a maintenance module, wherein the cross-reactor management module is used to formulate a maintenance strategy for each reactor according to the data of the data acquisition unit and the prediction result of the scheduling unit, and transmit the maintenance strategy to the maintenance module in the next maintenance time period predicted by the scheduling unit; The maintenance module is used to manage the resource scheduling of each reactor unit and implement the maintenance strategy of the cross-reactor type management module according to the results of the scheduling unit.

2. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 1, characterized in that: The specific working mode of the scheduling unit includes: Obtaining the operating data and historical maintenance records of each reactor according to the data acquisition unit; Obtain the most recent maintenance time and historical maintenance intervals of each reactor; Obtain the cumulative operating time of each reactor; According to the formula , calculate and obtain the average value of the historical maintenance intervals of each reactor , where n is the historical maintenance times of each reactor, is the time of the ith maintenance, It is Maintenance time of times; Obtain the difference D between the current operating time and the last maintenance time of each reactor; According to the formula , get the next maintenance time of each reactor , the next maintenance time of each reactor Transmitting to the cross-stack management module; in is the degradation rate of each reactor, is the initial performance of each reactor, is the performance threshold of each reactor.

3. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 2, characterized in that: The resource optimization configuration module further includes an optimization unit, which is used to optimize the prediction result of the scheduling unit according to the historical records and feedback evaluation of the scheduling unit, specifically: Obtain the last actual maintenance time and historical predicted maintenance time of each reactor; The feedback error coefficient H is obtained by subtracting the historical predicted maintenance time from the last actual maintenance time of each reactor and dividing the result by the last actual maintenance time; According to the formula , obtain the optimized predicted maintenance time of each reactor ; The optimized predicted maintenance time of each reactor Transmitted to the cross-stack management module.

4. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 1, characterized in that: The specific working mode of the cross-reacter type management module is as follows: First, the collected data of each reactor is analyzed to determine the risk importance of each reactor, and each reactor is divided into low-risk reactor equipment, medium-risk reactor equipment and high-risk reactor equipment; According to the risk importance of each reactor, a maintenance strategy is selected for each reactor. The specific maintenance strategies include: For reactor equipment with low risk, maintenance is carried out at fixed time intervals or operating cycles; For medium-risk reactor equipment, real-time monitoring of equipment status can be used to predict potential failures and perform maintenance in advance. For high-risk reactor equipment, maintenance time is determined based on the actual operating status and performance data of the equipment; For reactor equipment with low risk, the predicted next forecast time of the reactor is used as a fixed maintenance time interval for regular maintenance, and no forecast is performed at the next forecast time. For medium risk reactor equipment, use As the next maintenance time; For high-risk reactor equipment, the formula Obtain maintenance time based on the actual operating status and performance data of the equipment ,Will As the next maintenance time.

5. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 4, characterized in that: The specific working method of determining the risk importance of each reactor is as follows: Obtain the equipment unavailability U, failure consequence severity C and failure frequency F of each reactor; The product of the equipment unavailability U, failure consequence severity C and failure frequency F of each reactor is taken as the risk value L of the reactor; According to the calculated risk value L, the risk can be divided into low-risk reactor equipment, medium-risk reactor equipment and high-risk reactor equipment.

6. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 4, characterized in that: The specific working mode of the maintenance module is as follows: Adjust the spare parts inventory resource quantity of each reaction degree to be greater than or equal to the predicted spare parts resource consumption; The maintenance module further includes a personnel allocation unit, which is used to recommend the most suitable technician according to the risk importance analyzed by the cross-reactor management module.

7. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 6, characterized in that: The specific working mode of the personnel allocation unit is as follows: Obtain the skill level Z of each technician; The risk matching coefficient is obtained by dividing the skill level Z of each technician by the risk value L of each reactor, and the technician with the highest risk matching coefficient is assigned to the corresponding reactor maintenance.

8. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 7, characterized in that: The specific method of obtaining the skill level Z of each technician is as follows: Establish detailed personal files for each technician; The skills of the technicians are evaluated to obtain the skill level Z of each technician.

9. The abnormal response management system of a nuclear power plant in a cluster mode according to claim 8, characterized in that: The specific working method of the maintenance module also includes: After each maintenance of each reactor, the technicians will record the maintenance content; Categorize historical problems at each reactor based on record content; Create detailed personal profiles for each technician to match them with the type of problem.

10. A method for managing abnormal response of a nuclear power plant in a cluster mode, applicable to a management system for abnormal response of a nuclear power plant in a cluster mode proposed in claims 1 to 9, characterized in that: The following steps are involved: Step 1: Data collection: Use the data collection unit to collect the operating data and historical maintenance records of each reactor, and analyze the collected data, including the operating status, failure rate, maintenance history, etc. of the equipment to determine the risk level and maintenance requirements of each reactor; Step 2: Determine the time period for the next maintenance of each reactor. The cross-reactor management module formulates a maintenance strategy for each reactor based on the prediction results, taking into account the risk level and maintenance requirements of different reactors; Step 3: Automatically allocate resources based on predicted resource consumption and maintenance strategies to ensure that the needs of each reactor are met within the scheduled maintenance time period. During the maintenance time period predicted by the scheduling unit, the maintenance module manages the resource scheduling of each reactor unit and performs maintenance activities based on the maintenance strategy formulated by the cross-reactor management module.

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