Nuclear power plant equipment aging management method, device, equipment, medium and product

Abstract

The invention discloses a nuclear power plant equipment aging management method and device, equipment, a medium and a product, and relates to the technical field of nuclear power, and the method comprises the steps: discriminating items in a nuclear power plant through employing a discrimination strategy, and determining the items meeting the requirements of the discrimination strategy as key items; for each component object of the key item, determining the component object at the pressure boundary as an important component, and evaluating whether the utilization coefficient of the important component is lower than a utilization coefficient threshold; if the utilization coefficient is lower than a preset utilization coefficient threshold value, it is determined that the important component meets the safety requirement; if all important parts forming the key item meet the safety requirements, the key item meets the safety requirements; determining the proportion of the target key item meeting the safety requirement in all the key items; and if the proportion is higher than the proportion threshold value, determining that the safety evaluation result meets the requirement of running license continuation. The method can accurately evaluate the safety state of the nuclear power plant operation license during the duration, and improves the operation safety of the nuclear power plant.

Description

Technical Field

[0001] The present application relates to the field of nuclear power technology, and in particular to methods, devices, equipment, media and products for managing aging of equipment in nuclear power plants. Background Art

[0002] The renewal of the operating license of a nuclear power plant is to evaluate the safe service status of the key systems, structures and components of the nuclear power plant, combined with relevant technical transformation, maintenance inspection and aging management methods, so that the current license of the nuclear power plant can be continued to operate. The renewal of the operating license of a nuclear power plant is an effective measure to maintain and increase the supply of nuclear power electricity, and an important means to alleviate the contradiction between energy supply and demand. Safety evaluation is one of the key contents of the renewal of the operating license of a nuclear power plant, including the key item identification strategy for safety evaluation, the key item safety evaluation model and method, etc. At present, there are tens of thousands of items used for the safety evaluation of a million-kilowatt nuclear power unit. The large number, complex types, and lack of identification principles and methods for key items have caused the safety evaluation objects of nuclear power plants to be not highlighted during the renewal of the operating license, resulting in the failure to concentrate limited resources on important items, which poses a hidden danger to the safe operation of nuclear power plants, and cannot accurately evaluate the safe service status of key equipment and components during the renewal of the operating license validity period, and cannot better ensure the safe operation of nuclear power plants. Summary of the invention

[0003] The main purpose of this application is to provide a method, device, equipment, medium and product for the management of aging of nuclear power plant equipment, which is intended to be used for the identification of key items in the safety assessment of the renewal of the validity period of the nuclear power plant operating license and the safety assessment of key and important equipment, so as to improve the safety of nuclear power plant operation.

[0004] To achieve the above objectives, the present application proposes a method for managing aging of nuclear power plant equipment, comprising:

[0005] Use the preset screening strategy to screen the items used for safety assessment in nuclear power plants, and identify the items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license;

[0006] For each component object of the key item, if the component object is within a preset pressure boundary, the component object is determined to be an important component, and the utilization coefficient of the important component is evaluated to see whether it is lower than a preset utilization coefficient threshold;

[0007] If the utilization factor is lower than a preset utilization factor threshold, it is determined that the important component meets the preset safety requirements;

[0008] If all important components of the first key item meet the safety requirements, it is determined that the first key item meets the safety requirements;

[0009] Determine the proportion of key items that meet safety requirements among all key items. If the proportion is higher than the preset proportion threshold, the safety evaluation result of the nuclear power plant is determined to meet the requirements for renewal of the operating license.

[0010] In one embodiment, the screening strategy includes a time-limited aging analysis strategy, and the items used for safety assessment in the nuclear power plant are screened using a preset screening strategy, and the step of determining the items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license includes at least one of the following:

[0011] According to the time-limited aging analysis strategy, items within the scope of neutron irradiation embrittlement assessment are identified as key items, where the identification strategy requires that items be within the scope of neutron irradiation embrittlement assessment;

[0012] According to the time-limited aging analysis strategy, items within the scope of metal fatigue life evaluation are identified as key items, where the identification strategy requires that items be included within the scope of metal fatigue life evaluation;

[0013] According to the time-limited aging analysis strategy, the items within the concrete containment prestress loss assessment scope are determined as key items, where the identification strategy requires that the items be included within the concrete containment prestress loss assessment scope;

[0014] According to the time-limited aging analysis strategy, items within the scope of the environmental qualification evaluation of electrical equipment are determined as key items, where the identification strategy requires that items be included within the scope of the environmental qualification evaluation of electrical equipment;

[0015] According to the time-limited aging analysis strategy, items within the specific aging analysis scope under the specific operating conditions of the nuclear power plant are determined as key items, where the screening strategy requires that items be within the specific aging analysis scope under the specific operating conditions of the nuclear power plant;

[0016] According to the time-limited aging analysis strategy, items within the applicable scope of operating experience and feedback data of other similar nuclear power plants are determined as key items, among which the screening strategy requires items within the applicable scope of operating experience and feedback data of other similar nuclear power plants.

[0017] In one embodiment, the identification strategy includes a trend analysis strategy, and the items used for safety assessment in the nuclear power plant are identified using a preset identification strategy, and the step of determining the items that meet the requirements of the identification strategy as key items for the safety assessment of the renewal of the operating license also includes:

[0018] If the items are applicable to the trend analysis strategy, the items included in the power plant aging management activities carried out based on the trend analysis strategy are identified as key items.

[0019] In one embodiment, the identification strategy includes a failure result impact analysis strategy, and the items used for safety assessment in the nuclear power plant are identified using a preset identification strategy, and the items that meet the requirements of the identification strategy are determined as key items for the safety assessment of the renewal of the operating license, and the steps also include:

[0020] If the item is applicable to the failure result impact analysis strategy, the item is graded according to the preset failure result to obtain the impact classification result;

[0021] Items with first-level impact are identified as key items, where the impact classification results include first-level impact, second-level impact, and third-level impact. First-level impact is the impact caused by unacceptable failure of the power plant, which requires immediate corrective measures. Second-level impact is the major impact of failure on the power plant, which requires temporary corrective measures. Third-level impact is the minor impact of failure on the power plant, and the power plant continues to operate without any temporary measures.

[0022] In one embodiment, the identification strategy includes an equipment replacement difficulty analysis strategy, and the items used for safety assessment in the nuclear power plant are identified using a preset identification strategy, and the step of determining the items that meet the requirements of the identification strategy as key items for the safety assessment of the renewal of the operating license also includes:

[0023] If the item is applicable to the equipment replacement difficulty analysis strategy, the item is graded according to the preset equipment replacement difficulty to obtain the equipment classification result;

[0024] Items belonging to level one equipment are identified as key items, among which the equipment classification results include level one equipment, level two equipment, and level three equipment. Level one equipment is equipment that cannot be repaired or replaced, level two equipment is equipment that is inaccessible or difficult to repair and replace, and level three equipment is equipment that is easy to repair and replace.

[0025] In one embodiment, before the step of evaluating whether the utilization coefficient of the important component is lower than a preset utilization coefficient threshold, the step includes:

[0026] Determine the life calculation value of the important components during the extension period of the operating license according to the preset calculation model, and obtain the life threshold value corresponding to the important components from the preset evaluation threshold matrix table;

[0027] The ratio of the calculated life value to the life threshold is taken as the utilization coefficient.

[0028] In addition, to achieve the above-mentioned purpose, the present application also proposes a nuclear power plant equipment aging management device, the nuclear power plant equipment aging management device comprising:

[0029] The item screening module uses the preset screening strategy to screen the items used for safety assessment in the nuclear power plant, and identifies the items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license;

[0030] The component identification module determines that each component object of the key item is an important component if the component object is within the preset pressure boundary, and evaluates whether the utilization coefficient of the important component is lower than the preset utilization coefficient threshold;

[0031] A component safety evaluation module determines that an important component meets preset safety requirements if the utilization factor is lower than a preset utilization factor threshold;

[0032] The item safety evaluation module determines that the first key item meets the safety requirements if all important components of the first key item meet the safety requirements;

[0033] The overall safety evaluation module determines the proportion of key items that meet safety requirements among all key items. If the proportion is higher than the preset proportion threshold, the safety evaluation result of the nuclear power plant is determined to meet the requirements for the renewal of the operating license.

[0034] In addition, to achieve the above-mentioned purpose, the present application also proposes a nuclear power plant equipment aging management device, the device comprising: a memory, a processor, and a computer program stored in the memory and executable on the processor, the computer program being configured to implement the steps of the nuclear power plant equipment aging management method as described above.

[0035] In addition, to achieve the above-mentioned purpose, the present application also proposes a medium, which is a computer-readable storage medium, on which a computer program is stored, and when the computer program is executed by a processor, the steps of the nuclear power plant equipment aging management method as described above are implemented.

[0036] In addition, to achieve the above-mentioned purpose, the present application also provides a product, which is a computer program product. The computer program product includes a computer program, and when the computer program is executed by a processor, it implements the steps of the nuclear power plant equipment aging management method as described above.

[0037] One or more technical solutions proposed in this application have at least the following technical effects:

[0038] This application uses a screening strategy to screen items within the scope of safety assessment, and determines items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license, focusing on the key objects of the safety assessment of the renewal of the operating license, and improving the efficiency of the safety assessment; for each component object of the key item, if the component object is at a preset pressure boundary, the component object is determined to be an important component. This method can ensure that only key components are retained in the renewal of the operating license, reducing unnecessary maintenance costs, while improving the safety and efficiency of the nuclear power plant. Evaluate whether the utilization coefficient of the important component is lower than the preset utilization coefficient threshold. If the utilization coefficient is lower than the preset utilization coefficient threshold, it is determined that the important component meets the preset safety requirements; all important components constituting the key item meet the preset safety requirements, and the key item meets the safety requirements; determine the target proportion of the target key items that meet the safety requirements among all key items. If the target proportion is higher than the preset proportion threshold, it is determined that the safety assessment result of the nuclear power plant meets the requirements for the renewal of the operating license. This method provides a systematic evaluation mechanism that can objectively measure the safety status of the nuclear power plant, accurately evaluate the safe service status of key equipment and components during the renewal of the validity period of the operating license, and ensure the long-term safe operation of the nuclear power plant. BRIEF DESCRIPTION OF THE DRAWINGS

[0039] The accompanying drawings, which are incorporated in and constitute a part of this specification, illustrate embodiments consistent with the present application and, together with the description, serve to explain the principles of the present application.

[0040] In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the drawings required for use in the embodiments or the description of the prior art will be briefly introduced below. Obviously, for ordinary technicians in this field, other drawings can be obtained based on these drawings without paying any creative work.

[0041] Figure 1 This is a flow chart of Embodiment 1 of the method for managing aging of nuclear power plant equipment in this application;

[0042] Figure 2 This is a flow chart of Embodiment 3 of the method for managing aging of nuclear power plant equipment in this application;

[0043] Figure 3 A schematic diagram of the method for managing the aging of nuclear power plant equipment for this application;

[0044] Figure 4 This is a schematic diagram of the module structure of the nuclear power plant equipment aging management device according to an embodiment of the present application;

[0045] Figure 5 Schematic diagram of the equipment structure of the hardware operating environment involved in the nuclear power plant equipment aging management method in the embodiment of the present application.

[0046] The purpose, features and advantages of this application will be further described in conjunction with the embodiments and with reference to the accompanying drawings. DETAILED DESCRIPTION

[0047] It should be understood that the specific embodiments described herein are only used to explain the technical solutions of the present application and are not used to limit the present application.

[0048] In order to better understand the technical solution of the present application, a detailed description will be given below in conjunction with the accompanying drawings and specific implementation methods.

[0049] It should be noted that the execution subject of this embodiment can be a computing service device with data processing, network communication and program running functions, such as a tablet computer, a personal computer, a mobile phone, etc., or an electronic device capable of realizing the above functions, a terminal system, etc. The following takes the system as an example to illustrate this embodiment and the following embodiments.

[0050] Based on this, this embodiment provides a method for managing aging of nuclear power plant equipment. Figure 1 , Figure 1 This is a flow chart of Embodiment 1 of the method for managing aging of nuclear power plant equipment in this application. The method for managing aging of nuclear power plant equipment includes steps S10 to S50:

[0051] Step S10, using a preset identification strategy to identify items used for safety assessment in the nuclear power plant, and determining items that meet the requirements of the identification strategy as key items for safety assessment of renewal of the operating license;

[0052] It should be noted that the renewal of an operating license refers to the process in which a nuclear power plant applies for and is approved to continue operating after the existing operating license expires. During this process, the safety status of the power plant needs to be evaluated to ensure that it can operate safely. In this embodiment, the scope of safety evaluation refers to the collection of important structures, systems and components that need to be safety evaluated in order to determine the renewal of the operating license of a nuclear power plant. Important structures, systems and components are structures, systems and components that directly affect the basic safety functions of a nuclear power plant, such as reactor pressure vessels, steam generators, etc. The screening strategy is a method for identifying and selecting key items, including time-based aging analysis, trend analysis, and failure result impact analysis. Key items are items that are critical to safe operation within the scope of the safety evaluation and are determined according to the screening strategy.

[0053] First, the scope of the operating license renewal safety assessment needs to be clarified in accordance with regulatory requirements. After the scope of the safety assessment is determined, the items within the scope are screened using screening strategies. These screening strategies may include time-limited aging analysis, trend analysis, and failure result impact analysis. Screening can be performed by executing the screening strategy through a preset processor. Through these methods, key items are identified from the items within the scope, which are critical to the safe operation of the nuclear power plant.

[0054] Step S20, for each component object of the key item, if the component object is within a preset pressure boundary, the component object is determined to be an important component, and the utilization coefficient of the important component is evaluated to be lower than a preset utilization coefficient threshold;

[0055] Step S30, if the utilization coefficient is lower than a preset utilization coefficient threshold, it is determined that the important component meets the preset safety requirements;

[0056] It should be noted that the component object is a component of the key item and can be a single component or a collection of multiple components. The pressure boundary refers to the boundary between the pressure-bearing part of the system or equipment and the external environment. The preset safety conditions are the safety requirements or standards that the components must meet in advance according to the system design or industry standards. Important components are components that have a significant impact on safety functions that are screened out from key items. The utilization factor is the ratio of the calculated life value of the important component to its life threshold, which is used to evaluate whether the component meets safety requirements. The calculated life value is the estimated remaining life based on the actual operating data and aging analysis of the important components. The life threshold is the set life limit value, which is used to evaluate whether the life of the component meets safety requirements.

[0057] Identify all component objects located at the pressure boundary of the nuclear power plant. These component objects have a decisive impact on the safe operation of the nuclear power plant because they are in direct contact with the reactor coolant. The component objects located at the pressure boundary of the nuclear power plant can be identified by a processor with an identification program. A detailed safety evaluation is performed on these component objects to determine which components meet the preset safety conditions. The safety conditions include three aspects: Quantitative analysis requirements for nuclear power plant design: This involves rigorous mathematical and physical analysis of component design to ensure that they can theoretically withstand the designed working pressure and temperature. These analyses are usually performed during the component design phase to verify the integrity and functionality of the components under extreme conditions. Good performance in actual operation of the nuclear power plant refers to the performance of the components during the actual operation of the nuclear power plant. Through monitoring and maintenance records, evaluate whether there are abnormal conditions such as leakage, corrosion or unexpected failures. The actual operation history of the component is an important basis for evaluating its safety. Good practice feedback from similar nuclear power plants, which involves collecting and analyzing operating data and feedback from the same or similar components in other similar nuclear power plants. If these components operate well in other power plants without frequent faults or early failures, then it can be assumed that they may also operate safely in the current nuclear power plant. Component objects that meet any of the above safety conditions are identified as important components. This means that these components have performed well in design, operating history, or feedback from similar power plants, and are therefore considered to be key factors in the safe operation of nuclear power plants.

[0058] Calculate the utilization coefficient of these important components using the formula: Utilization coefficient = calculated component life value / component life threshold. The calculated component life value is based on the actual use and / or wear of the component, and the component life threshold is the expected life determined when the component is designed. Compare the calculated utilization coefficient with the preset safety standard. If the utilization coefficient is less than or equal to 100%, it means that the actual service life of the component does not exceed the design life and meets the safety requirements; if the utilization coefficient is greater than 100%, it means that the component has exceeded the design life and may not meet the safety requirements.

[0059] Step S40, if all important components of the first key item meet the safety requirements, then determining that the first key item meets the safety requirements;

[0060] Step S50, determining the proportion of key items that meet safety requirements among all key items. If the proportion is higher than a preset proportion threshold, determining that the safety evaluation result of the nuclear power plant meets the requirements for renewal of the operating license.

[0061] For each key item, if all its important components meet the safety requirements, it is determined that the key item meets the safety requirements. Finally, the proportion of key items that meet the safety requirements among all key items is calculated to obtain the overall safety evaluation result. The proportion can be calculated by a processor with a calculation program. There can be a proportion threshold here, and the threshold data source can come from the standard threshold of world standards or historical data summary. When the proportion of key items that meet the safety requirements among all key items is higher than the proportion threshold, the overall evaluation result is good; otherwise, further review or remedial measures may be required. This result will determine whether the nuclear power plant can obtain the renewal of the operating license.

[0062] This embodiment uses a screening strategy to screen items within the scope of safety evaluation, and determines items that meet the requirements of the screening strategy as key items for the safety evaluation of the renewal of the operating license, focusing on the key objects of the safety evaluation of the renewal of the operating license, and improving the efficiency of the safety evaluation; for each component object of the key item, if the component object is within the preset pressure boundary, the component object is determined to be an important component. This method can ensure that only key components are retained in the renewal of the operating license, reducing unnecessary maintenance costs, and improving the safety and efficiency of the nuclear power plant. Evaluate whether the utilization coefficient of the important component is lower than the preset utilization coefficient threshold. If the utilization coefficient is lower than the preset utilization coefficient threshold, it is determined that the important component meets the preset safety requirements; if all important components constituting the key item meet the preset safety requirements, the key item meets the safety requirements; determine the target proportion of the target key items that meet the safety requirements among all key items. If the target proportion is higher than the preset proportion threshold, it is determined that the safety evaluation result of the nuclear power plant meets the requirements for the renewal of the operating license. This method provides a systematic evaluation mechanism that can objectively measure the safety status of the nuclear power plant, accurately evaluate the safe service status of key equipment and components during the renewal of the validity period of the operating license, and ensure the long-term safe operation of the nuclear power plant.

[0063] Based on the first embodiment of the present application, in the second embodiment of the present application, the same or similar contents as those in the first embodiment can be referred to the above description, and will not be repeated hereafter. On this basis, the step S10 further includes at least one of steps A10 to A60:

[0064] Step A10, according to the time-limited aging analysis strategy, determining items within the neutron irradiation embrittlement evaluation range as key items, wherein the identification strategy requires that the items be within the neutron irradiation embrittlement evaluation range;

[0065] It should be noted that time-limited aging analysis refers to the analysis of the gradual aging of items due to long-term use, which may affect their performance and safety. Radiation embrittlement is the effect of neutron irradiation on the performance of reactor pressure vessel materials. The degradation of its macroscopic performance can be evaluated by analyzing the changes in the microstructure inside the material.

[0066] Using the preset embrittlement model, the initial performance parameters and neutron irradiation data of the reactor pressure vessel material are input. The model calculates the degree of influence of neutron irradiation on the material performance by analyzing the microstructural changes inside the material. This value reflects the degree of embrittlement and performance degradation of the material under irradiation.

[0067] Step A20, determining items within the metal fatigue life evaluation range as key items according to the time-limited aging analysis strategy, wherein the identification strategy requires that the items be within the metal fatigue life evaluation range;

[0068] It should be noted that metal fatigue life is based on material mechanics and fatigue theory, and is the life of metal parts under cyclic loads until fatigue failure.

[0069] Apply the preset fatigue algorithm and input the geometric dimensions, material properties, loads and cyclic characteristics of the metal component. The algorithm calculates the fatigue life prediction value of the component based on fatigue theory, that is, the estimated time until the component fails under cyclic load.

[0070] Step A30, according to the time-limited aging analysis strategy, determining items within the concrete containment prestress loss evaluation range as key items, wherein the identification strategy requires that the items be within the concrete containment prestress loss evaluation range;

[0071] It should be noted that prestress loss is the phenomenon of reduction of prestress in the steel tendons in the concrete containment due to time, environment and other factors, which affects the overall stability and bearing capacity of the structure.

[0072] The prestress loss of the steel tendons in the concrete containment is analyzed, taking into account the effects of environmental factors such as time, temperature, and humidity on the prestress. The prestress loss value is obtained by calculation, and the impact of the reduction of the prestress of the steel tendons on the structural stability is evaluated.

[0073] Step A40, determining items within the scope of the electrical equipment environmental identification and evaluation as key items according to the time-limited aging analysis strategy, wherein the identification strategy requires that the items be within the scope of the electrical equipment environmental identification and evaluation;

[0074] In the specific environment of nuclear power plants, the performance of electrical equipment is tested and analyzed. Performance indicators such as equipment efficiency, stability and reliability are evaluated to obtain the performance value of electrical equipment.

[0075] Step A50, according to the time-limited aging analysis strategy, determining items within the specific aging analysis range under specific operating conditions of the nuclear power plant as key items, wherein the identification strategy requires that the items be within the specific aging analysis range under specific operating conditions of the nuclear power plant;

[0076] It should be noted that items will produce special aging phenomena under the unique operating conditions of nuclear power plants (such as high temperature, radiation, etc.).

[0077] Aging analysis is performed on items under the unique operating conditions of nuclear power plants (such as high temperature, radiation, etc.). The impact of these special conditions on the performance of items is evaluated to obtain unique aging values.

[0078] Step A60, according to the time-limited aging analysis strategy, determine that the items within the applicable scope of the operating experience and feedback data of other similar nuclear power plants are key items, wherein the identification strategy requires that the items be within the applicable scope of the operating experience and feedback data of other similar nuclear power plants.

[0079] Collect and analyze data on item performance, aging, etc. from other similar nuclear power plants. Through comparison and analysis, obtain empirical data values ​​to evaluate the performance and aging of current items.

[0080] According to the above analysis, if an item meets any of the screening principles, it will be identified as a critical item, which means that the item plays a key role in the operation of the nuclear power plant and its performance or aging requires special attention and monitoring.

[0081] This embodiment comprehensively applies preset analysis tools such as embrittlement models and fatigue algorithms to conduct in-depth analysis of reactor pressure vessel materials, fatigue life of metal components, prestress loss of steel tendons in concrete containment, and performance of electrical equipment in specific environments, focusing on components that may experience performance degradation due to long-term use, so as to take measures in advance to avoid potential safety risks.

[0082] In a feasible implementation manner, step S10 further includes step B10:

[0083] Step B10: If the items are applicable to the trend analysis strategy, the items included in the power plant aging management activities carried out according to the trend analysis strategy are determined as key items.

[0084] It should be noted that in power plant aging management activities, trend analysis strategies can be applied to analyze the changing trends of key indicators such as item performance and aging degree, so as to identify items with significant changing trends that may have a significant impact on power plant operations.

[0085] From the preset power plant aging management activity record table, collect record data involving inspection, monitoring and operation, including key information such as item name, performance parameters, aging degree, etc. Based on the collected data, draw a trend chart of key indicators such as item performance parameters and aging degree over time. Observe the trend chart and identify the trend type in the data (such as rising trend, falling trend, stable trend, etc.), as well as the inflection point, abnormal point or significant change point in the trend. Combined with the actual situation and business background of the power plant, analyze whether the items corresponding to the inflection point, abnormal trend or significant change point identified in the trend chart have a significant impact on the operation of the power plant. Furthermore, the collected data can be directly analyzed through the preset trend analysis model, and according to the analysis results, those items with significant change trends that may have a significant impact on the safety and reliability of the power plant are determined as key items.

[0086] The identification of this embodiment strengthens the aging management activities. Through regular data recording and analysis, the aging status of power plant equipment can be continuously tracked and managed, thereby improving the maintenance efficiency and predictability of the equipment.

[0087] In a feasible implementation manner, step S10 further includes steps C10 to C20:

[0088] Step C10: if the item is suitable for the failure result impact analysis strategy, the item is graded according to the preset failure result to obtain an impact grading result;

[0089] Step C20, determine the items belonging to the first-level impact as key items, where the impact classification results include first-level impact, second-level impact, and third-level impact. The first-level impact is the impact caused by unacceptable failure of the power plant, which requires immediate corrective measures. The second-level impact is the failure that has a significant impact on the power plant, which requires temporary corrective measures. The third-level impact is the minor impact of the failure on the power plant, and the power plant continues to operate without any temporary measures.

[0090] It should be noted that the failure result is the impact that may be caused to the safety and operation of the power plant when an item fails.

[0091] All items are analyzed for the impact of failure results. This analysis evaluates the possible consequences of item failures, including the impact on the safety, environment and economy of the power plant. According to the analysis results, the failure results are obtained. The failure results have three impact levels. The first level is the consequences of unacceptable failures in the power plant, and corrective measures must be taken immediately. The reactor must be shut down until permanent corrective measures are implemented. The second level is that the failure has a significant impact on the power plant, and temporary corrective measures must be taken. After the corrective measures are implemented, the power plant can continue to operate within a limited time. The third level is that the failure has a small impact on the power plant, and the power plant continues to operate without any temporary measures. Corrective measures can be implemented within the specified period.

[0092] This embodiment determines key items through failure results, so that the power plant can give priority to those components that may cause serious impacts once a failure occurs, ensuring a rapid response when a failure occurs and reducing downtime.

[0093] In a feasible implementation manner, step S10 further includes steps D10 to D20:

[0094] Step D10: if the item is applicable to the equipment replacement difficulty analysis strategy, the item is graded according to the preset equipment replacement difficulty to obtain an equipment grading result;

[0095] Step D20, determine the items belonging to the first-level equipment as key items, where the equipment classification results include first-level equipment, second-level equipment, and third-level equipment. First-level equipment is equipment that cannot be repaired or replaced, second-level equipment is equipment that is inaccessible or difficult to repair and replace, and third-level equipment is equipment that is easy to repair and replace.

[0096] It should be noted that the difficulty of equipment replacement refers to the ease of replacing a specific device or component.

[0097] Conduct an equipment replacement difficulty analysis, which takes into account the time, resources, and complexity required to replace equipment or components. According to the difficulty of equipment replacement, items are also divided into three levels: level 1 equipment is non-repairable and non-replaceable equipment, whose life determines the life of the power plant; level 2 equipment is inaccessible or difficult to repair and replace equipment, and inspection and maintenance occupy a long-term shutdown window; level 3 equipment is easy to repair and replace equipment, or inspection and maintenance activities are easy to implement. Further, any combination of level 2 equipment and equipment belonging to the first-pole impact or the second-pole impact in step C10 can be determined as a key item. Similarly, any combination of equipment belonging to the second-pole impact in step C10 and the first-pole equipment or the second-pole equipment in this step can also be determined as a key item.

[0098] This embodiment enables the power plant to identify parts that are difficult to replace through equipment replacement difficulty analysis, and formulate special maintenance and replacement strategies for these parts to ensure the continuous operation of the power plant.

[0099] Based on the first or second embodiment of the present application, in the third embodiment of the present application, the same or similar contents as those in the first or second embodiment can be referred to the above introduction, and will not be described in detail later. Figure 2 , Figure 2 This is a flow chart of the third implementation of the method for managing aging of nuclear power plant equipment in this application. Step S20 also includes steps E10 to E20:

[0100] Step E10, determining the life calculation value of the important component during the extension period of the operating license according to the preset calculation model, and obtaining the life threshold corresponding to the important component from the preset evaluation threshold matrix table;

[0101] It should be noted that the operating license extension period refers to the period of continuous operation of the system or equipment after obtaining the operating license, and regular evaluation is required to determine whether the operating license can be extended. The preset calculation model is a mathematical model or algorithm used to predict or calculate the life of a component. The preset evaluation threshold matrix table is a table containing different components and their corresponding life thresholds, which is used to evaluate whether the component life meets the requirements.

[0102] For each important component, a preset calculation model is used to calculate its life calculation value during the extension period of the operating license. At the same time, the life threshold corresponding to the component is found from the preset evaluation threshold matrix table. The preset calculation model can predict the life of the component based on factors such as the material, structure, and service environment of the component. The evaluation threshold matrix table is shown in Table 1 below. The threshold column in Table 1 is the life threshold set for different components based on system design or industry standards. By comparing the life calculation value and the life threshold, it can be evaluated whether the life of the component meets the requirements. Each important component (only two are listed in the table for explanation) corresponds to eight mechanisms, including radiation embrittlement, radiation-promoted stress corrosion, stress corrosion, uniform corrosion, pitting, wear, fatigue, and thermal aging. The material type is the component material, and the main types are low alloy steel, stainless steel, nickel-based alloy, carbon steel, etc. The operating environment mainly includes temperature, pressure, dissolved oxygen, chloride ions, Ph value, etc. The thresholds are the values ​​allowed by the eight mechanisms during the extension period of the operating license (such as 20 years). Except for the cumulative fatigue damage coefficient threshold corresponding to fatigue being 1.0, the thresholds of other mechanisms are different for different materials and operating environments.

[0103]

[0104] Table 1

[0105] Step E20, taking the ratio of the life calculation value to the life threshold as the utilization coefficient.

[0106] It should be noted that the preset utilization threshold is a safety upper limit of the utilization factor preset according to system design or industry standards.

[0107] The utilization coefficient of each important component is calculated using the life calculation value and the life threshold. Then, the utilization coefficient is compared with the preset utilization threshold to determine whether the component meets the safety requirements. The utilization coefficient reflects the relationship between the actual utilization degree of the component and its safe life. When the utilization coefficient is less than or equal to the preset utilization threshold (which can be 100%), it means that the utilization degree of the component is within the safety range and meets the safety requirements. Otherwise, measures need to be taken for maintenance or replacement.

[0108] This embodiment provides a systematic and scientific safety assessment method for nuclear power plant components. This method not only improves the efficiency and accuracy of component safety management, but also provides a solid guarantee for the operation safety of nuclear power plants through quantitative evaluation results, and also provides a reliable basis for component maintenance and replacement decisions. Through this method, nuclear power plants can more accurately identify and manage the safety risks of key components, thereby ensuring the long-term stable operation of power plants and the safety of personnel.

[0109] For example, refer to Figure 3 , Figure 3The process of the nuclear power plant equipment aging management method is presented, which is divided into two main parts: the key item identification method (screening strategy) for the operating license renewal safety assessment and the key item safety assessment method. The items determined in the scope of the operating license renewal safety assessment are screened by the key item identification method for the operating license renewal safety assessment to obtain key items. The key item safety assessment method is used to obtain an overall safety assessment for the key items. These methods are finally summarized into the overall safety assessment method for the renewal of the nuclear power plant operating license. First, the identification of key items for the operating license renewal safety assessment involves the identification of key items based on different analyses. This includes key item identification strategies based on time-limited aging analysis, trend analysis, failure failure result impact analysis, and equipment replacement difficulty analysis. Each analysis aims to identify components that are critical to safe operation from different perspectives. Finally, the safety evaluation method for key items of operating license renewal safety evaluation includes classification of key components of key items (classification based on whether they are at the pressure boundary), determination of the evaluation threshold matrix of key components (determination of the evaluation threshold matrix table), and threshold-based safety evaluation of key items (determining the life calculation value of key components during the operation license renewal period according to the preset calculation model, and obtaining the corresponding life threshold of the key components from the preset evaluation threshold matrix table, and taking the ratio of the life calculation value to the life threshold as the utilization coefficient. If the utilization coefficient is lower than the preset utilization coefficient threshold, it is determined that the key component meets the preset safety requirements. If all the key components in a key item meet the preset safety requirements, the key item meets the requirements for the renewal of the operating license). This step calculates the life calculation value of the key component and the life threshold obtained from the evaluation threshold matrix table to obtain the utilization coefficient, and judges whether the component meets the safety requirements based on whether the utilization coefficient meets the preset utilization threshold. The overall compliance of the nuclear power plant with the renewal of the license is evaluated by the proportion of key items that meet the preset safety requirements in all key items. Combining these steps, the process provides a systematic safety evaluation method for the renewal of the nuclear power plant operating license, ensuring the long-term safe operation of the nuclear power plant.

[0110] It should be noted that the above examples are only used to understand the present application and do not constitute a limitation on the aging management method for nuclear power plant equipment of the present application. More simple transformations based on this technical concept are all within the scope of protection of the present application.

[0111] This application also provides a nuclear power plant equipment aging management device, please refer to Figure 4 , the aging management device for nuclear power plant equipment includes:

[0112] The item screening module 10 screens the items used for safety assessment in the nuclear power plant using a preset screening strategy, and determines the items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license;

[0113] The component identification module 20 determines, for each component object of the key item, if the component object is within a preset pressure boundary, that the component object is an important component, and evaluates whether the utilization coefficient of the important component is lower than a preset utilization coefficient threshold;

[0114] The component safety evaluation module 30 determines that the important component meets the preset safety requirements if the utilization coefficient is lower than the preset utilization coefficient threshold;

[0115] The item safety evaluation module 40 determines that the first key item meets the safety requirements if all important components of the first key item meet the safety requirements;

[0116] The overall safety evaluation module 50 determines the proportion of key items that meet safety requirements among all key items. If the proportion is higher than a preset proportion threshold, it is determined that the safety evaluation result of the nuclear power plant meets the requirements for renewal of the operating license.

[0117] The nuclear power plant equipment aging management device provided by the present application adopts the nuclear power plant equipment aging management method in the above-mentioned embodiment, which can solve the technical problem of being unable to accurately evaluate the safe service status of key equipment and components during the extension of the validity period of the operating license. Compared with the prior art, the beneficial effects of the nuclear power plant equipment aging management device provided by the present application are the same as the beneficial effects of the nuclear power plant equipment aging management method provided by the above-mentioned embodiment, and other technical features in the nuclear power plant equipment aging management device are the same as the features disclosed in the above-mentioned embodiment method, which will not be repeated here.

[0118] The present application provides a nuclear power plant equipment aging management device, which includes: at least one processor; and a memory communicatively connected to the at least one processor; wherein the memory stores instructions executable by the at least one processor, and the instructions are executed by the at least one processor so that the at least one processor can execute the nuclear power plant equipment aging management method in the above-mentioned embodiment one.

[0119] Reference below Figure 5 , which shows a schematic diagram of the structure of a nuclear power plant equipment aging management device suitable for implementing the embodiment of the present application. The nuclear power plant equipment aging management device in the embodiment of the present application may include but is not limited to mobile terminals such as mobile phones, laptop computers, digital broadcast receivers, PDAs (Personal Digital Assistants), PADs (Portable Application Descriptions), PMPs (Portable Media Players), vehicle-mounted terminals (such as vehicle-mounted navigation terminals), etc., and fixed terminals such as digital TVs, desktop computers, etc. Figure 5The nuclear power plant equipment aging management device shown is merely an example and should not bring any limitation to the functions and scope of use of the embodiments of the present application.

[0120] like Figure 5 As shown, the nuclear power plant equipment aging management device may include a processing device 1001 (such as a central processing unit, a graphics processing unit, etc.), which can perform various appropriate actions and processes according to a program stored in a read-only memory (ROM: Read Only Memory) 1002 or a program loaded from a storage device 1003 to a random access memory (RAM: Random Access Memory) 1004. In RAM1004, various programs and data required for the operation of the nuclear power plant equipment aging management device are also stored. The processing device 1001, ROM1002 and RAM1004 are connected to each other through a bus 1005. An input / output (I / O) interface 1006 is also connected to the bus. Typically, the following systems can be connected to the I / O interface 1006: input devices 1007 including, for example, a touch screen, a touchpad, a keyboard, a mouse, an image sensor, a microphone, an accelerometer, a gyroscope, etc.; output devices 1008 including, for example, a liquid crystal display (LCD), a speaker, a vibrator, etc.; storage devices 1003 including, for example, a magnetic tape, a hard disk, etc.; and communication devices 1009. The communication device 1009 can allow the nuclear power plant equipment aging management device to communicate wirelessly or wired with other devices to exchange data. Although the figure shows a nuclear power plant equipment aging management device with various systems, it should be understood that it is not required to implement or have all the systems shown. More or fewer systems may be implemented or have alternatively.

[0121] In particular, according to the embodiments disclosed in the present application, the process described above with reference to the flowchart can be implemented as a computer software program. For example, the embodiments disclosed in the present application include a computer program product, which includes a computer program carried on a computer-readable medium, and the computer program includes a program code for executing the method shown in the flowchart. In such an embodiment, the computer program can be downloaded and installed from a network through a communication device, or installed from a storage device 1003, or installed from a ROM 1002. When the computer program is executed by the processing device 1001, the above-mentioned functions defined in the method of the embodiment disclosed in the present application are executed.

[0122] The nuclear power plant equipment aging management device provided by the present application adopts the nuclear power plant equipment aging management method in the above embodiment, which can solve the technical problem of being unable to accurately evaluate the safe service status of key equipment and components during the extension of the validity period of the operating license. Compared with the prior art, the beneficial effects of the nuclear power plant equipment aging management device provided by the present application are the same as the beneficial effects of the nuclear power plant equipment aging management method provided by the above embodiment, and the other technical features of the nuclear power plant equipment aging management device are the same as the features disclosed in the method of the previous embodiment, which will not be repeated here.

[0123] It should be understood that the various parts disclosed in this application can be implemented by hardware, software, firmware or a combination thereof. In the description of the above embodiments, specific features, structures, materials or characteristics can be combined in any one or more embodiments or examples in a suitable manner.

[0124] The above are only specific implementations of the present application, but the protection scope of the present application is not limited thereto. Any technician familiar with the technical field can easily think of changes or substitutions within the technical scope disclosed in the present application, which should be included in the protection scope of the present application. Therefore, the protection scope of the present application should be based on the protection scope of the claims.

[0125] The present application provides a medium, which is a computer-readable storage medium having computer-readable program instructions (ie, computer programs) stored thereon, and the computer-readable program instructions are used to execute the nuclear power plant equipment aging management method in the above-mentioned embodiment.

[0126] The computer-readable storage medium provided in the present application may be, for example, a USB flash drive, but is not limited to electrical, magnetic, optical, electromagnetic, infrared, or semiconductor systems or devices, or any combination of the above. More specific examples of computer-readable storage media may include, but are not limited to: an electrical connection with one or more wires, a portable computer disk, a hard disk, a random access memory (RAM: Random Access Memory), a read-only memory (ROM: Read Only Memory), an erasable programmable read-only memory (EPROM: Erasable Programmable Read Only Memory or flash memory), an optical fiber, a portable compact disk read-only memory (CD-ROM: CD-Read Only Memory), an optical storage device, a magnetic storage device, or any suitable combination of the above. In this embodiment, the computer-readable storage medium may be any tangible medium containing or storing a program that can be used by or in combination with an instruction execution system or device. The program code contained on the computer-readable storage medium may be transmitted using any appropriate medium, including but not limited to: wires, optical cables, RF (Radio Frequency: Radio Frequency), etc., or any suitable combination of the above.

[0127] The computer-readable storage medium may be included in the nuclear power plant equipment aging management device; or may exist independently without being assembled into the nuclear power plant equipment aging management device.

[0128] The computer-readable storage medium carries one or more programs. When the one or more programs are executed by the nuclear power plant equipment aging management device, the nuclear power plant equipment aging management device:

[0129] Use the preset screening strategy to screen the items used for safety assessment in nuclear power plants, and identify the items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license;

[0130] For each component object of the key item, if the component object is within a preset pressure boundary, the component object is determined to be an important component, and the utilization coefficient of the important component is evaluated to see whether it is lower than a preset utilization coefficient threshold;

[0131] If the utilization factor is lower than a preset utilization factor threshold, it is determined that the important component meets the preset safety requirements;

[0132] If all important components of the first key item meet the safety requirements, it is determined that the first key item meets the safety requirements;

[0133] Determine the proportion of key items that meet safety requirements among all key items. If the proportion is higher than the preset proportion threshold, the safety evaluation result of the nuclear power plant is determined to meet the requirements for renewal of the operating license.

[0134] Computer program code for performing the operations of the present application may be written in one or more programming languages ​​or a combination thereof, including object-oriented programming languages ​​such as Java, Smalltalk, C++, and conventional procedural programming languages ​​such as "C" or similar programming languages. The program code may be executed entirely on the user's computer, partially on the user's computer, as a separate software package, partially on the user's computer and partially on a remote computer, or entirely on a remote computer or server. In the case of a remote computer, the remote computer may be connected to the user's computer through any type of network, including a local area network (LAN) or a wide area network (WAN), or may be connected to an external computer (e.g., via the Internet using an Internet service provider).

[0135] The flow chart and block diagram in the accompanying drawings illustrate the possible architecture, function and operation of the system, method and computer program product according to various embodiments of the present application. In this regard, each square box in the flow chart or block diagram can represent a module, a program segment or a part of a code, and the module, the program segment or a part of the code contains one or more executable instructions for realizing the specified logical function. It should also be noted that in some alternative implementations, the functions marked in the square box can also occur in a sequence different from that marked in the accompanying drawings. For example, two square boxes represented in succession can actually be executed substantially in parallel, and they can sometimes be executed in the opposite order, depending on the functions involved. It should also be noted that each square box in the block diagram and / or flow chart, and the combination of the square boxes in the block diagram and / or flow chart can be implemented with a dedicated hardware-based system that performs a specified function or operation, or can be implemented with a combination of dedicated hardware and computer instructions.

[0136] The modules involved in the embodiments described in this application may be implemented by software or hardware, wherein the name of the module does not constitute a limitation on the unit itself in some cases.

[0137] The readable storage medium provided by the present application is a computer-readable storage medium, which stores computer-readable program instructions (i.e., computer programs) for executing the above-mentioned nuclear power plant equipment aging management method, and can solve the technical problem of being unable to accurately evaluate the safe service status of key equipment and components during the extension of the validity period of the operating license. Compared with the prior art, the beneficial effects of the computer-readable storage medium provided by the present application are the same as the beneficial effects of the nuclear power plant equipment aging management method provided by the above-mentioned embodiment, and will not be repeated here.

[0138] The present application also provides a product, which is a computer program product, including a computer program, which implements the steps of the above-mentioned nuclear power plant equipment aging management method when executed by a processor.

[0139] The computer program product provided by this application can solve the technical problem of being unable to accurately evaluate the safe service status of key equipment and components during the extension of the validity period of the operating license. Compared with the prior art, the beneficial effects of the computer program product provided by this application are the same as the beneficial effects of the nuclear power plant equipment aging management method provided by the above embodiment, and will not be repeated here.

[0140] The above are only some embodiments of the present application, and are not intended to limit the patent scope of the present application. All equivalent structural changes made using the contents of the present application specification and drawings under the technical concept of the present application, or direct / indirect application in other related technical fields are included in the patent protection scope of the present application.

Claims

1. A method for managing aging of nuclear power plant equipment, characterized in that: The nuclear power plant equipment aging management method comprises: Use the preset screening strategy to screen the items used for safety assessment in nuclear power plants, and identify the items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license; For each component object of the key item, if the component object is within a preset pressure boundary, the component object is determined to be an important component, and a utilization coefficient of the important component is evaluated to be lower than a preset utilization coefficient threshold; If the utilization coefficient is lower than a preset utilization coefficient threshold, it is determined that the important component meets the preset safety requirements; If all important components of the first key item meet the safety requirements, it is determined that the first key item meets the safety requirements; The proportion of key items that meet safety requirements among all key items is determined. If the proportion is higher than a preset proportion threshold, the safety evaluation result of the nuclear power plant is determined to meet the requirements for renewal of the operating license.

2. The method for managing aging of nuclear power plant equipment according to claim 1, characterized in that: The screening strategy includes a time-limited aging analysis strategy, and the steps of screening items used for safety assessment in the nuclear power plant using a preset screening strategy and determining the items that meet the requirements of the screening strategy as key items for the safety assessment of the renewal of the operating license include at least one of the following: According to the time-limited aging analysis strategy, items within the neutron irradiation embrittlement evaluation range are determined as key items, wherein the identification strategy requires that items be within the neutron irradiation embrittlement evaluation range; According to the time-limited aging analysis strategy, items within the metal fatigue life evaluation range are determined as key items, wherein the identification strategy requires that items be within the metal fatigue life evaluation range; According to the time-limited aging analysis strategy, items within the concrete containment prestress loss evaluation range are determined as key items, wherein the identification strategy requires that items be included within the concrete containment prestress loss evaluation range; According to the time-limited aging analysis strategy, items within the scope of the environmental identification and evaluation of electrical equipment are determined as key items, wherein the identification strategy requires that items be within the scope of the environmental identification and evaluation of electrical equipment; According to the time-limited aging analysis strategy, items within the specific aging analysis scope under specific operating conditions of the nuclear power plant are determined as key items, wherein the identification strategy requires that items be within the specific aging analysis scope under specific operating conditions of the nuclear power plant; According to the time-limited aging analysis strategy, items within the applicable scope of operating experience and feedback data of other similar nuclear power plants are determined as key items, wherein the identification strategy requires items within the applicable scope of operating experience and feedback data of other similar nuclear power plants.

3. The method for managing aging of nuclear power plant equipment according to claim 1, characterized in that: The identification strategy includes a trend analysis strategy, and the steps of using a preset identification strategy to identify items used for safety assessment in a nuclear power plant, and determining the items that meet the requirements of the identification strategy as key items for safety assessment for renewal of the operating license also include: If the items are applicable to the trend analysis strategy, the items included in the power plant aging management activities carried out based on the trend analysis strategy are determined to be key items.

4. The method for managing aging of nuclear power plant equipment according to claim 1, characterized in that: The identification strategy includes a failure result impact analysis strategy, and the step of using a preset identification strategy to identify items used for safety assessment in the nuclear power plant and determining the items that meet the requirements of the identification strategy as key items for the safety assessment of the renewal of the operating license also includes: If the item is applicable to the failure result impact analysis strategy, the item is graded according to the preset failure result to obtain an impact grading result; The items belonging to the first-level impact are determined as the key items, wherein the impact classification results include first-level impact, second-level impact, and third-level impact. The first-level impact is the impact caused by unacceptable failure of the power plant, which requires immediate corrective measures. The second-level impact is the significant impact of the failure on the power plant, which requires temporary corrective measures. The third-level impact is the minor impact of the failure on the power plant, and the power plant continues to operate without any temporary measures.

5. The method for managing aging of nuclear power plant equipment according to claim 1, characterized in that: The identification strategy includes an equipment replacement difficulty analysis strategy, and the steps of using a preset identification strategy to identify items used for safety assessment in a nuclear power plant, and determining the items that meet the requirements of the identification strategy as key items for safety assessment of the renewal of the operating license also include: If the item is applicable to the equipment replacement difficulty analysis strategy, the item is graded according to the preset equipment replacement difficulty to obtain an equipment grading result; The items belonging to the first-level equipment are determined as the key items, wherein the equipment classification results include first-level equipment, second-level equipment, and third-level equipment. First-level equipment is equipment that cannot be repaired or replaced, second-level equipment is equipment that is inaccessible or difficult to repair and replace, and third-level equipment is equipment that is easy to repair and replace.

6. The method for managing aging of nuclear power plant equipment according to claim 1, characterized in that: Before the step of evaluating whether the utilization coefficient of the important component is lower than a preset utilization coefficient threshold, the method includes: Determine the life calculation value of the important component during the extension period of the operating license according to a preset calculation model, and obtain the life threshold value corresponding to the important component from a preset evaluation threshold matrix table; The ratio of the life calculation value to the life threshold is used as a utilization coefficient.

7. A nuclear power plant equipment aging management device, characterized in that: The nuclear power plant equipment aging management device comprises: The item screening module uses a preset screening strategy to screen items used for safety assessment in nuclear power plants, and identifies items that meet the requirements of the screening strategy as key items for safety assessment of renewal of operating licenses; a component identification module, for each component object of the key item, if the component object is within a preset pressure boundary, determining the component object as an important component, and evaluating whether the utilization coefficient of the important component is lower than a preset utilization coefficient threshold; A component safety evaluation module, if the utilization coefficient is lower than a preset utilization coefficient threshold, determines that the important component meets the preset safety requirements; an item safety evaluation module, determining that the first key item meets the safety requirements if all important components of the first key item meet the safety requirements; The overall safety evaluation module determines the proportion of key items that meet safety requirements among all key items. If the proportion is higher than a preset proportion threshold, the safety evaluation result of the nuclear power plant is determined to meet the requirements for renewal of the operating license.

8. A nuclear power plant equipment aging management device, characterized in that: The nuclear power plant equipment aging management device comprises: a memory, a processor, and a computer program stored in the memory and executable on the processor, wherein the computer program is configured to implement the steps of the nuclear power plant equipment aging management method according to any one of claims 1 to 6.

9. A computer-readable storage medium having a computer program stored thereon, wherein the computer program, when executed by a processor, implements the steps of the method for managing aging of nuclear power plant equipment according to any one of claims 1 to 6.

10. A computer program product, comprising a computer program, wherein when the computer program is executed by a processor, the steps of the method for managing aging of nuclear power plant equipment according to any one of claims 1 to 6 are implemented.

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