A method and system for evaluating the aging state of a nuclear reactor plant

By determining the assessment scope, identifying potential aging effect items and obtaining monitoring parameters, and combining multiple analysis methods to conduct aging status assessment, the problem of inaccurate aging status assessment of nuclear reactor buildings in existing technologies has been solved, achieving higher assessment accuracy.

CN119670361BActive Publication Date: 2025-10-21NUCLEAR POWER INSTITUTE OF CHINA
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Patent Information

Application Number
CN202411657210.8
Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
Filing Date
2024-11-19
Publication Date
2025-10-21
Estimated Expiration
2044-11-19

AI Technical Summary

Technical Problem

Existing technologies are unable to accurately and comprehensively assess the aging status of nuclear reactor building structures or constructions, resulting in low accuracy of assessment results and the presence of interference factors.

Method used

By determining the assessment scope, identifying potential aging effect items, and obtaining monitoring parameters for visual and electrical detection signals, combined with the 'material-environment-influence factor' analysis method and the predetermined function loss analysis method, an aging status assessment is conducted to generate overall status assessment data and durability time assessment data.

Benefits of technology

The accuracy of the aging status assessment of nuclear reactor buildings has been improved, a systematic and comprehensive analysis of nuclear reactor building structures or construction structures has been achieved, and the errors in the assessment results have been reduced.

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Abstract

The application discloses a nuclear reactor plant aging state evaluation method and system. The method can determine an evaluation range according to a predetermined function performed by an object to be evaluated. Potential aging effect items of the object to be evaluated in the evaluation range are identified. Monitoring parameters are obtained according to the aging effect items, and aging state evaluation of the object to be evaluated is performed according to the monitoring parameters to obtain evaluation result data. The method can streamline the screening of aging management objects, aging effect identification and aging effect monitoring, comprehensively analyze the object to be evaluated in combination with multiple aging effect items, systematically evaluate the aging state of nuclear reactor plant structures or structural structures, and improve the accuracy of state evaluation results.
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Description

Technical Field

[0001] The present application relates to the field of nuclear industry technology, and in particular to a method and system for evaluating the aging status of a nuclear reactor building. Background Art

[0002] Nuclear reactor buildings consist of structures constructed of steel and concrete. These structures degrade over time. When these structures degrade to a certain degree, they can affect the safety of the nuclear reactor building. Therefore, to improve safety, it's important to assess the aging status of nuclear reactor building structures and predict their impact on production processes.

[0003] Aging assessment involves systematic analysis and evaluation of the performance degradation of nuclear reactor building structures due to environmental factors, material degradation, and other factors. Through comprehensive evaluation methods such as structural inspection, structural analysis, load testing, and durability testing, it is determined whether the structures will meet expected performance requirements within their service life and whether they require repair, reinforcement, or replacement.

[0004] However, the assessment of the aging status of nuclear reactor building structures is limited to the individual performance evaluation of a single structure or structure, and cannot obtain an accurate overall condition assessment result. In addition, the aging condition assessment process is subject to numerous interfering factors, further reducing the accuracy of the condition assessment results. Summary of the Invention

[0005] In view of this, embodiments of the present application provide a method and system for evaluating the aging status of a nuclear reactor building, so as to improve the accuracy of the evaluation results of the aging status of a nuclear reactor building.

[0006] According to one aspect of the present application, a method for assessing the aging status of a nuclear reactor building is provided, the method comprising:

[0007] Determining the scope of assessment according to a predetermined function performed by the object to be assessed, wherein the object to be assessed is a structure and / or construction structure in a nuclear reactor building structure; the predetermined function is a safety-related function performed by the object to be assessed in the building structure;

[0008] Identify potential aging effects of the subjects to be evaluated within the scope of the evaluation;

[0009] Acquiring monitoring parameters based on the aging effect item, the monitoring parameters including first-category parameters and second-category parameters, the first-category parameters being obtained by performing aging effect item feature recognition on visual signals of the object to be evaluated; and the second-category parameters being obtained by performing aging effect item feature recognition on electrical detection signals of the object to be evaluated;

[0010] An aging status assessment is performed on the object to be assessed according to the monitoring parameters to obtain assessment result data, wherein the assessment result data includes overall status assessment data and durability time assessment data.

[0011] Optionally, the scope of the assessment may be determined based on the intended functions performed by the subject to be assessed, including:

[0012] Obtain information on the structural characteristics of the plant;

[0013] Based on the structural characteristics of the plant, determine the object type and item list of the object to be assessed;

[0014] The evaluation scope is determined according to whether the object to be evaluated performs a predetermined function.

[0015] Optionally, the predetermined function includes a combination of one or more of a support function, a heat sink function, an equipment protection function, a shielding function, a pressure boundary function, a container function, a space isolation function, and an anti-intrusion barrier function.

[0016] Optionally, identifying potential aging effect items of the subject to be evaluated within the evaluation scope includes:

[0017] Acquire aging influencing parameters of the plant structure, wherein the aging influencing parameters include material parameters, environmental parameters, and influencing factor parameters of the plant structure;

[0018] determining a set of aging effect items according to the aging impact parameters;

[0019] According to the aging effect item set, potential aging effect items of the object to be evaluated within the evaluation scope are identified.

[0020] Optionally, obtaining monitoring parameters according to the aging effect item includes:

[0021] Acquiring a visual signal of the object to be evaluated;

[0022] extracting a target feature from the visual signal, wherein the target feature is a visual feature associated with the aging effect term;

[0023] The visual performance data of the target feature in the visual signal is recorded to generate the first type of parameters, wherein the visual performance data includes the feature type, feature morphological parameters, and feature position associated with the aging effect item.

[0024] Optionally, obtaining monitoring parameters according to the aging effect item includes:

[0025] Obtaining a sensor type and sensor calibration parameters, wherein the detection calibration parameters are used to characterize a correspondence between an electrical value of an electrical detection signal and a parameter information value;

[0026] Receive electrical detection signals collected by sensors;

[0027] extracting a characteristic signal segment from the electrical detection signal according to the type of the sensor;

[0028] According to sensor calibration parameters, the characteristic signal segment is converted into parameter information to generate the second type of parameters.

[0029] Optionally, performing an aging status assessment on the object to be assessed according to the monitoring parameters to obtain assessment result data includes:

[0030] Setting the limit state of the object to be evaluated;

[0031] Obtaining structural parameters of the object to be evaluated;

[0032] Determine the local environmental coefficient according to the preset environmental action level;

[0033] The durability time for the object to be evaluated to reach the limit state is calculated according to the monitoring parameters, the structural parameters and the local environmental coefficient to generate the durability time evaluation data.

[0034] Optionally, performing an aging status assessment on the object to be assessed according to the monitoring parameters to obtain assessment result data includes:

[0035] Obtaining the status evaluation interval to which the monitoring parameter belongs;

[0036] Setting a status evaluation weight according to the status evaluation interval to which the monitoring parameter belongs;

[0037] Based on the status assessment weights, a weighted summation is performed on the monitoring parameters to generate the overall status assessment data.

[0038] Optionally, the object to be evaluated is one or more combinations of: concrete structure, steel structure, structural expansion joint, masonry structure, equipment foundation, roof, pool and component support structure.

[0039] According to another aspect of the present application, a nuclear reactor building aging status assessment system is provided, the system comprising: a sensor and a controller, the sensor being configured to collect monitoring parameters;

[0040] The controller is configured to:

[0041] Determining the scope of assessment according to a predetermined function performed by the object to be assessed, wherein the object to be assessed is a structure and / or construction structure in a nuclear reactor building structure; the predetermined function is a safety-related function performed by the object to be assessed in the building structure;

[0042] Identify potential aging effects of the subjects to be evaluated within the scope of the evaluation;

[0043] Acquiring monitoring parameters based on the aging effect item, the monitoring parameters including first-category parameters and second-category parameters, the first-category parameters being obtained by performing aging effect item feature recognition on visual signals of the object to be evaluated; and the second-category parameters being obtained by performing aging effect item feature recognition on electrical detection signals of the object to be evaluated;

[0044] An aging status assessment is performed on the object to be assessed according to the monitoring parameters to obtain assessment result data, wherein the assessment result data includes overall status assessment data and durability time assessment data.

[0045] By means of the above technical solution, an embodiment of the present application provides a method and system for evaluating the aging status of a nuclear reactor building, wherein the method can determine the evaluation scope according to the predetermined functions performed by the object to be evaluated. Then identify the potential aging effect items of the object to be evaluated within the evaluation scope. And according to the aging effect items, obtain monitoring parameters, and perform aging status evaluation on the object to be evaluated according to the monitoring parameters to obtain evaluation result data. The method can streamline the screening of aging management objects, aging effect identification and aging effect monitoring and inspection processes, combine multiple aging effect items to conduct a comprehensive analysis of the object to be evaluated, and systematically evaluate the aging status of nuclear reactor building structures or construction structures, thereby improving the accuracy of status evaluation results.

[0046] The above description is only an overview of the technical solution of the present application. In order to more clearly understand the technical means of the present application, it can be implemented in accordance with the contents of the specification. In order to make the above and other purposes, features and advantages of the present application more obvious and easy to understand, the specific implementation methods of the present application are listed below. BRIEF DESCRIPTION OF THE DRAWINGS

[0047] The drawings described herein are used to provide a further understanding of the present application and constitute a part of the present application. The illustrative embodiments of the present application and their descriptions are used to explain the present application and do not constitute an improper limitation on the present application. In the drawings:

[0048] Figure 1 An application scenario diagram of an aging status assessment method provided by an embodiment of the present application is shown;

[0049] Figure 2 A schematic diagram of a process for evaluating an aging state provided in an embodiment of the present application is shown;

[0050] Figure 3 The overall flow chart of aging status assessment provided by the embodiment of the present application is shown;

[0051] Figure 4 A schematic diagram of the process for determining the evaluation scope provided in an embodiment of the present application is shown;

[0052] Figure 5 A schematic diagram of the process of generating overall status assessment data provided by an embodiment of the present application is shown;

[0053] Figure 6 A schematic diagram of the process of calculating the durability time provided in an embodiment of the present application is shown;

[0054] Figure 7 A schematic structural diagram of an aging status assessment system provided in an embodiment of the present application is shown;

[0055] Figure 8 A schematic diagram of the computer device structure provided in an embodiment of the present application is shown. DETAILED DESCRIPTION

[0056] The present application will be described in detail below with reference to the accompanying drawings and in combination with embodiments. It should be noted that, unless there is a conflict, the embodiments and features in the embodiments of the present application can be combined with each other.

[0057] In the embodiments of this application, a nuclear reactor is a group of nuclear power plant equipment used to control and maintain nuclear reactions to generate energy. The term "nuclear reactor" is broad and can include both reactors used for formal nuclear power plant production and research reactors used for research and experimentation. While reactors and research reactors may differ in scale depending on their intended use, both types share high safety requirements.

[0058] Some embodiments of this application describe methods for assessing the aging status of nuclear reactor buildings using research reactors as an example, while other embodiments of this application describe methods for assessing the aging status of buildings using a fully operational nuclear reactor as an example. It should be understood that the described embodiments can also be applied to other types of nuclear reactors. Other application scenarios that can be imagined by those skilled in the art based on the embodiments of this application also fall within the scope of protection of this application.

[0059] A research reactor refers to a nuclear facility or device other than a nuclear power plant, including research reactors, experimental reactors, critical assemblies, and subcritical systems driven by external power sources. Research reactors can be used for scientific research, education, and training. To maintain a research reactor, a building and facilities are constructed around the nuclear reactor. A research reactor building is a specialized facility that provides a safe and efficient operating environment for the research reactor. The research reactor building can be located inside or around the reactor, utilizing the reactor's neutron flux and ionizing radiation beams for research, development, isotope production, and other activities. Research reactors are important platforms for scientific research and experimental applications, used for basic research in neutron physics, research on the irradiation properties of reactor fuel and materials, and research and development using radioisotope irradiation.

[0060] The design of a research reactor building must adhere to strict safety regulations to ensure a controlled chain reaction can be maintained under all circumstances and to provide conditions for the layout and composition of the research core. These regulations include preventative measures for accident conditions and the design of multiple safety systems. A research reactor building can consist of a main building and auxiliary buildings. The main building is closer to the nuclear reactor and has higher safety requirements. The selection of construction materials for the main research reactor building must take into account factors such as radiation protection, heat resistance, and structural strength. Therefore, the main research reactor building is constructed using special materials such as reinforced concrete to ensure adequate protection and safety.

[0061] Because the main research reactor building primarily utilizes reinforced concrete, which ages over time after construction, the building can experience varying degrees of aging. This aging can include environmental factors such as freeze-thaw, cracks, melting, and carbonization; chemical changes in the concrete that cause bond breakdown; corrosion of steel bars that lead to loss of tensile strength and component failure; and the possibility that tiny cracks on the concrete surface can extend inward due to rain, ice, and salt weather, leading to further corrosion and leakage.

[0062] To minimize the impact of aging on research reactor building safety, regular aging testing and assessment is necessary. Aging assessment involves systematic analysis and evaluation of the performance degradation of nuclear reactor building structures due to environmental factors, material degradation, and other factors. Comprehensive evaluation methods, including structural testing, structural analysis, load testing, and durability testing, determine whether the structures will meet expected performance requirements within their service life and whether they require repair, reinforcement, or replacement.

[0063] To this end, this embodiment provides a method for assessing the aging status of a nuclear reactor building. The method can be applied to a nuclear reactor building aging status assessment system. The nuclear reactor building aging status assessment system is a software and hardware platform that performs aging status assessments based on user input or sensor detection data and displays the aging status assessment results. The nuclear reactor building aging status assessment system can rely on computers, mobile terminals, servers, industrial hosts, smart wearable devices, and the like to provide users with a human-computer interaction interface. In response to user input, the system collects, processes, transmits, and stores relevant data based on the provided human-computer interaction interface to meet specific user needs.

[0064] In one feasible embodiment, the nuclear reactor building aging status assessment system can be operated on a single device, that is, the user can realize all the functions of the aging status assessment system through a single client device. For example, the aging status assessment system is an application installed on a personal computer. The aging status assessment system application has an application program with a built-in aging status assessment algorithm. When performing the aging status assessment, the computer can obtain user input and / or monitoring data collected by sensors, and call the assessment model to perform an assessment on the monitoring data to obtain corresponding assessment result data. The assessment result data is then displayed based on the display program provided by the application.

[0065] In another feasible implementation, the aging status assessment system can be operated by multiple devices, that is, the coordination between multiple devices is required to realize the full functions of the aging status assessment system. Figure 1 As shown, the aging status assessment system includes a server, multiple clients connected to the server, and multiple sensors. These sensors can be used to collect monitoring data from different regions or types. The clients can be operated by different users, and the interaction data generated by these operations can be sent to the server via the network, requesting the server to collect, process, evaluate, distribute, and store the monitoring data. After receiving the evaluation results from the server, the clients display the results using a display program provided by the application.

[0066] It should be noted that in the embodiments of the present application, a client such as a computer is used as the execution subject of the aging state assessment method. Unless otherwise specified, the aging state assessment method can be implemented by running a related application on a client such as a computer, or by running a related application on a server, or by cooperating with a client to run a related application. Therefore, from the description process of the execution subject, the steps corresponding to the aging state assessment prediction method can be executed by the client, or by the server, or some steps can be executed by the client and some steps can be executed by the server.

[0067] like Figure 2 、 Figure 3 As shown, the nuclear reactor building aging status assessment method includes:

[0068] S101. Determine the scope of evaluation according to the predetermined functions performed by the object to be evaluated.

[0069] The objects to be assessed are structures and / or structures within the nuclear reactor building. Structures refer to independent buildings or components within the nuclear reactor building, constructed from steel or concrete. Structures refer to parts of independent buildings that impact the overall safety of the building structure.

[0070] In one feasible implementation, since concrete structures, steel structures, structural expansion joints, masonry structures, equipment foundations, roofs, water tanks, and component support structures significantly impact the overall safety of a nuclear reactor building, safety-critical structures or structures can be identified based on their design functions. Specifically, the objects to be assessed are one or a combination of concrete structures, steel structures, structural expansion joints, masonry structures, equipment foundations, roofs, water tanks, and component support structures.

[0071] For the object to be assessed, the assessment scope can be determined based on the predetermined functions being performed. The predetermined functions are safety-related functions performed by the object to be assessed within the plant structure. In some embodiments, the predetermined functions include one or more of the following: support function, heat sink function, equipment protection function, shielding function, pressure boundary function, container function, spatial isolation function, and anti-intrusion barrier function.

[0072] Among them, the support function is to provide structural or functional support functions to safety-related equipment. The heat sink function is to provide a heat sink function in the design basis accident conditions. The equipment protection function is to provide shielding or protection for safety-related equipment. The shielding function is to provide a radioactive shielding function. The pressure boundary function of the structure is to provide a leak-proof function as a pressure boundary in the design basis accident conditions to protect public health and safety. The container function is to provide a collection or storage function for liquid media (such as deionized water, radioactive wastewater, etc.). The spatial isolation function is to maintain the structural integrity of non-safety-related equipment and prevent the failure of safety equipment due to the failure of non-safety equipment.

[0073] Anti-intrusion barrier functions can include fire barriers, flood barriers, and missile barriers. Fire barriers control fires or prevent them from spreading to adjacent areas of the power plant. Flood barriers provide protection against internal or external flooding incidents. Missile barriers provide protection against internal or external missiles.

[0074] The assessment scope refers to the collection of various data items related to the aging state assessment. The assessment scope may include, but is not limited to, the scope of durability influencing factors, components or structural parts, time range, environmental conditions, structural usage functions, and structural layout.

[0075] Among them, the evaluation scope of durability influencing factors includes durability influencing factors that need to be considered, including physical factors such as freeze-thaw cycles, temperature changes, dry-wet cycles, chemical factors such as acids, alkalis, salts, and biological factors such as microorganisms. The evaluation scope of components or structural parts involves specific components or structural parts, that is, whether the object of the evaluation is the entire structure or a specific part of the structure. The time range means whether the evaluation considers the current state or includes performance changes within a certain period in the future. The evaluation scope of environmental conditions includes the environmental conditions in which the structure is located. The evaluation scope of structural use functions includes the specific use functions of the specific structure during the evaluation process. Since different use functions may have different requirements and influences on the aging state of concrete, the evaluation scope of structural use functions is also different in different evaluation processes. The evaluation scope of structural layout involves the layout of the structure, which is used to determine the degree of influence of the specific structure layout on durability and aging state.

[0076] like Figure 4 As shown, in order to determine the scope of the assessment, in one feasible implementation, the structural characteristics of the plant building can be first obtained. Then, based on the structural characteristics of the plant building, the object type and item list of the object to be assessed can be determined. The assessment scope can also be determined based on whether the object to be assessed performs the predetermined function.

[0077] For example, when performing an aging condition assessment, the intended functions of the safety-critical structures or structures (hereinafter referred to as the assessed objects) can be determined based on their design functions. The types and item lists of assessed objects can be divided based on the structural characteristics of the research reactor main building. The functions performed by each assessed object can then be screened based on the object type and item list. If the assessed object performs the intended function, it will be included in the assessment scope; if it does not perform the intended function, it will not be included in the assessment scope.

[0078] S102: Identify potential aging effect items of the subject to be evaluated within the evaluation scope.

[0079] After determining the assessment scope, the aging status assessment system can identify potential aging effects on the subject within the assessment scope based on a specific assessment algorithm. Specific assessment algorithms can include a "material-environment-influencing factor" analysis method and a predetermined loss of function analysis method. Within the detailed assessment scope, the "material-environment-influencing factor" and predetermined loss of function analysis methods can be used to determine the aging effects that require assessment for the subject.

[0080] In some embodiments, the potential aging effect items are also referred to as potential aging effect mechanisms, and may include one or more combinations of the following specific potential aging effect items. That is, the strength and modulus reduction effects caused by high temperatures, and the reduction in strength and modulus when normal temperatures are >150°F and local temperatures are >200°F. Cracking caused by aggregate expansion reactions. Increased porosity and permeability and strength loss caused by calcium hydroxide leaching and carbonization. Cracking, bond loss, and material loss caused by corrosion of embedded steel bars. Material loss and cracking caused by freeze-thaw. Material loss and cracking caused by severe chemical corrosion. Material loss refers to aging phenomena such as peeling and flaking. Cracking and deformation caused by increased stress levels due to settlement. Reduced foundation strength and cracking due to uneven settlement and erosion of porous concrete substrates. Weathering caused by increased material hardness, shrinkage, and reduced strength. Cracking caused by constrained shrinkage, creep, and corrosive environments. Cracking caused by suppressed shrinkage, creep, and harsh environments. Material loss caused by corrosion. Loss of coating integrity due to blistering, cracking, flaking, peeling or physical damage. Material loss due to uniform corrosion, pitting and crevice corrosion. Loss of preload due to self-loosening.

[0081] To identify potential aging effects on the object to be assessed, the aging condition assessment system can first obtain aging impact parameters for the plant structure. Based on these aging impact parameters, a set of aging impact items is then determined. Based on this set of aging impact items, potential aging effects on the object to be assessed within the assessment scope are identified. Aging impact parameters include material parameters, environmental parameters, and influencing factor parameters of the plant structure.

[0082] For example, when conducting an aging status assessment, the potential aging effects of eight types of structures in the research reactor main building can be identified: concrete structures, steel structures, structural expansion joints, masonry structures, equipment foundations, roofs, pools, and component supports. Based on the actual materials, environments, and influencing factors of these eight types of structures, the potential aging effect items for each structure can be determined, forming a set of aging effect items. In the subsequent analysis process, the "material-environment-influencing factor" analysis method is used to identify potential aging effect items one by one in the aging effect item set, thereby determining the detection parameters and specific analysis methods used in the aging status assessment process.

[0083] S103: Acquire monitoring parameters according to the aging effect item.

[0084] The monitoring parameters include first-category parameters and second-category parameters. The first-category parameters are monitoring parameters obtained using a visual signal detection method, i.e., the first-category parameters are obtained by performing aging effect feature recognition on the visual signal of the object to be evaluated. The second-category parameters are monitoring parameters obtained using a laboratory-specific detection method, i.e., the second-category parameters are obtained by performing aging effect feature recognition on the electrical detection signal of the object to be evaluated.

[0085] When performing aging status assessment, the main building structures of the research reactor can be screened, grouped, and the aging effects can be understood. Specific and feasible on-site visual signal detection methods and laboratory special detection methods can be selected according to industry experience and standards.

[0086] In some embodiments, the on-site visual signal detection method can first acquire a visual signal of the object to be evaluated. A target feature can then be extracted from the visual signal. The target feature is a visual feature associated with the aging effect term. Visual representation data of the target feature in the visual signal is then recorded to generate the first type of parameter. The recorded visual representation data of the target feature includes the feature type, feature morphological parameters, and feature location associated with the aging effect term.

[0087] For example, according to the aging effect detection method specified in the Outline for Aging Management of Nuclear Reactor Plant Equipment, it is possible to collect on-site visual signals and conduct multi-dimensional visual inspections on the object to be evaluated. The specific content of visual inspection may include one or more combinations of the following inspection items:

[0088] The beams, slabs, columns and walls of concrete structures are inspected for problems including concrete surface cracking, spalling, expansion cracking, hollowing, wear and chemical erosion, corrosion of concrete anchors and surrounding local concrete cracking, steel bar corrosion and reinforcement leakage.

[0089] For factory building foundations with concrete structures, when excavation is possible, visual signal detection is performed on the exposed concrete entities, including the inspection of the moisture-proof layer of the foundation and the exterior wall below the ground.

[0090] For steel structures, inspections are carried out, including surface corrosion of steel structures, bending and deformation of steel structures, corrosion, loosening and missing of structural bolts, cracking and peeling of surface coatings of steel structures, etc.

[0091] Masonry structures are inspected for problems such as chemical erosion, wear, corrosion, fracture, spalling, cracks and leakage, rust of anchors and aging of surrounding concrete, and deformation of masonry structures.

[0092] Structural expansion joints are inspected for hardening, tearing, cracking, and defects in the sealing materials at the expansion joints, debonding and peeling between the sealing materials and the concrete on both sides of the expansion joints, deformation and damage of the steel plates at the expansion joints, debonding and cracking of the expansion joint membranes, and leakage and water accumulation at the expansion joint nodes.

[0093] Inspections are conducted on equipment foundations, including cracks in the concrete equipment foundation, separation of the concrete equipment foundation from the floor slab, corrosion and deformation of the slide rail foundation components, missing and corroded anchor bolts, spalling of concrete around the anchors, and aging of the surface coating of the concrete equipment foundation.

[0094] The roof is inspected for surface cracks and fissures, detachment and aging of silicone weatherproof sealant, water accumulation on the roof, bulging of the roof, aging and missing of waterproof washers on the fastening screws at the roof joints, and water seepage on the roof.

[0095] The pool structure is inspected for cracks and spalling of concrete, corrosion of concrete reinforcement, and signs of pool leakage.

[0096] For component supports, inspections are carried out on conditions including aging of support surface coating, corrosion of support surface, corrosion and cracking of support connecting bolts, looseness and missing of support connecting bolts, local concrete spalling of support anchors, deformation and dislocation of supports, etc.

[0097] Based on the identified object to be evaluated and the potential aging effects, devices such as image sensors, infrared cameras, ultrasonic detection sensors, and lidar (lidar) can be used to capture images of the object to be evaluated. The captured image data is then fed into an image analysis model, which then extracts visual features associated with aging effects from the image data.

[0098] For example, if the object to be assessed is a concrete structure and the potential aging effect identified is concrete surface cracking, a conventional camera can be used to photograph the concrete surface to obtain an image. Then, based on the crack detection model, crack features are extracted from the concrete surface image based on the image pixel values. The degree of cracking on the concrete surface is then determined based on the visual representation data of the crack features. The visual representation data of the crack features may include the number of cracks in the concrete surface image, crack location, crack length, and crack width. This visual representation data can be calculated using parameters such as the number of pixels in the crack features and the camera focal length.

[0099] In some embodiments, for laboratory-specific detection methods, the sensor type and sensor calibration parameters can be obtained first. Wherein, the detection calibration parameters are used to characterize the correspondence between the electrical values ​​of the electrical detection signal and the parameter information values. Before the sensor detects specific parameters, the sensor needs to be calibrated first. Sensor calibration is to input a known measured quantity (standard quantity) into the sensor to be calibrated and obtain the output of the sensor at the same time. By processing and comparing the input and output, a series of calibration curves (i.e., sensor calibration parameters) that characterize the correspondence between the two are obtained, and then the measured results of the sensor performance indicators are obtained.

[0100] After obtaining the sensor type and sensor calibration parameters, an electrical detection signal collected by the sensor can be received. Based on the sensor type, characteristic signal segments can be extracted from the electrical detection signal. Furthermore, the characteristic signal segments can be converted into parameter information according to the sensor calibration parameters to generate the second type of parameters.

[0101] Among them, the specific equipment type of the sensor can be determined according to the specific detection items, that is, the sensor can include but is not limited to: crack detector, infrared thermal imager, infrared measuring instrument, rebound tester, strength tester, penetration measuring instrument, scanner, potential detection electrode, ion content detector, carbonization tester, petrographic analysis detector, metallographic and electron microscope, etc.

[0102] For example, according to the aging effect detection methods specified in the Nuclear Reactor Plant Equipment Aging Management Outline, laboratory-specific testing methods can be used to conduct multi-dimensional testing of the object to be assessed. Similarly, when conducting laboratory-specific testing, the specific content of the test can include one or more combinations of the following test items:

[0103] For concrete beams, slabs, columns, and walls, crack detection instruments can be used to measure the width, length, and direction of concrete cracks. Infrared thermal imagers can be used to detect concrete temperature distribution and internal defects. Infrared measuring instruments and infrared thermal imaging can also be used to measure the temperature field of the factory building and identify abnormal temperature points.

[0104] Concrete strength will be tested using a concrete rebound test hammer, and the compressive strength of bricks in the powerhouse masonry will be tested on-site using a brick rebound test hammer. Mortar rebound test hammers can also be used to test the compressive strength of mortar in the powerhouse masonry. During the compressive strength test, the core drilling method can be used to sample and test the concrete structure of the research reactor main powerhouse. Specifically, the core drilling method will be used to test the concrete strength, while the rebound method will be used to estimate the strength.

[0105] Concrete permeameters are used to test concrete permeability, and Permea air permeability meters can be used to measure the change in air pressure per unit time to evaluate concrete's impermeability. When testing the concrete permeability of the research reactor's main building, batches can be divided according to different concrete design strength grades. Six components from each batch are sampled for concrete permeability testing to determine the concrete permeability coefficient and grade.

[0106] A rebar scanner is used to non-destructively detect the thickness of the concrete cover, and the non-destructive testing results can be verified by partial chiseling verification method.

[0107] A steel bar corrosion meter is used to detect steel bar corrosion. When testing the corrosion of concrete steel bars in the main powerhouse of a research reactor, a single-electrode method can be used to sample and test the concrete corrosion to obtain the steel bar potential.

[0108] Laboratory analysis was used to test the chloride ion content of concrete. A concrete carbonation tester was used to test the carbonation depth of concrete. Laboratory analysis was used to test the alkali content of concrete. Concrete petrographic analysis was used to test the alkali-aggregate activity of concrete. A total station was used to test structural deformation.

[0109] For the plant foundation of concrete structure, monitor the groundwater or soil environment, including: pH value of groundwater or soil, Cl - Ion concentration or SO4 2- Concentration; use high-precision level to observe settlement. For masonry structures, use crack observation instrument to detect masonry cracks.

[0110] For equipment foundations, a concrete rebound tester can be used to test the strength of the concrete equipment foundation, and metallographic and electron microscopy techniques can be used to analyze the causes.

[0111] The carbonation depth of concrete can be tested using a 1% to 2% phenolphthalein alcohol solution. The concrete can also be divided into batches based on the plant's segmentation, with wall panels classified as one category and beams and columns as another.

[0112] Water drills were used to sample the concrete components of the factory building and analyze the chloride ion content. Water drills and special grinding tools were used to drill samples for aggregate petrographic analysis and alkali content testing.

[0113] Distance sensors can also be used to inspect concrete deformations such as tilt and deflection, as well as masonry wall deformations such as outward flash and tilt. A total station is used to inspect the tilt of the main building, with tilt detection points located at the exterior corners of the building.

[0114] In addition, underground soil around the main building of the research reactor can also be tested, including pH value, chloride ion content, and sulfate ion content.

[0115] In addition to acquiring the aforementioned monitoring parameters, in some embodiments, environmental and data collection can also be performed on the research reactor main building. This data includes: building location, construction date, main building materials, building elevation, floor area, overall structure, climate of the area where the building is located, annual average temperature, annual average relative humidity, annual average rainfall, and major aging mechanisms. This data can be used to assist in aging status assessment, resulting in more accurate assessment results.

[0116] S104: Perform aging status assessment on the object to be assessed according to the monitoring parameters to obtain assessment result data.

[0117] After obtaining the monitoring parameters, an aging condition assessment can be performed on the object to be assessed based on the monitoring parameters using the "material-environment-influencing factors" analysis method and the predetermined function loss analysis method to obtain assessment result data. Based on the "material-environment-influencing factors" analysis method, overall condition assessment data can be obtained. Based on the predetermined function loss analysis method, durability time assessment data can be obtained. Therefore, the assessment result data includes overall condition assessment data and durability time assessment data.

[0118] Among them, for the "material-environment-influencing factor" analysis method, after obtaining the monitoring parameters, you can first determine the durability influencing factors, that is, identify the durability influencing factors, including physical factors, chemical factors, and biological factors. Then, according to the purpose and scope of the assessment, select the appropriate durability assessment method. The assessment methods include traditional empirical methods, practical identification methods, fuzzy hierarchical analysis methods, etc. And according to the needs of the assessment, carry out relevant durability tests, such as impermeability, frost resistance, and erosion resistance. The detection methods include water seepage method, antifreeze label method, electrical flux method, chloride ion migration coefficient method, etc. Then, based on the test data and analysis results, evaluate the durability level of concrete. Considering factors such as the performance degradation of concrete, the degree of damage, and the remaining service life, comprehensively judge the safety and reliability of concrete.

[0119] In some embodiments, the overall status assessment data obtained based on the "material-environment-influencing factors" analysis method can reflect the aging status of the research reactor building by calculating the evaluation score. The evaluation score can be a weighted summation result calculated based on the monitoring data. Figure 5 As shown, when performing an aging status assessment on the object to be assessed based on the monitoring parameters to obtain assessment result data, the status assessment interval to which the monitoring parameters belong can be first obtained. Status assessment weights can then be set based on the status assessment interval to which the monitoring parameters belong. Furthermore, based on the status assessment weights, a weighted summation of the monitoring parameters is performed to generate the overall status assessment data.

[0120] The method of loss of intended function analysis is to prove through calculation, analysis, experiment, etc. that a certain aging effect will not lead to loss of intended function of the object to be evaluated under the design working conditions, so as to prove whether it is necessary to consider the relevant aging effect. Figure 6 As shown, in some embodiments, performing an aging state assessment on the object to be assessed based on the monitoring parameters to obtain assessment result data further includes: setting a limit state for the object to be assessed, obtaining structural parameters of the object to be assessed, and determining a local environmental coefficient according to a preset environmental action level. The durability time required for the object to be assessed to reach the limit state is then calculated based on the monitoring parameters, the structural parameters, and the local environmental coefficient to generate the durability time assessment data.

[0121] For example, the durability assessment is conducted with the beginning of steel bar corrosion in concrete components as the limit state. The durability of steel bar corrosion can be calculated using the following formula:

[0122]

[0123] Where: t is the durability of steel bar corrosion; f1 is the influence coefficient of carbonation coefficient on the durability of steel bar corrosion; x is the measured carbonation depth of concrete (mm). When the carbonation measurement area is not at the corner of the component, the carbonation depth of the component corner can be taken as 1.4 times the measured carbonation depth; t0 is the time from the construction of the structure to the time of testing (a). The calculation formula of f1 is as follows:

[0124]

[0125] f2 is the coefficient of influence of the protective layer thickness on the durability of steel bar corrosion. c is the thickness of the concrete protective layer (mm). The calculation formula of f2 is as follows:

[0126]

[0127] f3 is the influence coefficient of the local environment on the durability of steel bar corrosion. m is the local environment coefficient. The qualitative evaluation method is shown in the following table:

[0128]

[0129] The formula for calculating f3 is as follows:

[0130]

[0131] Based on the above formula, the durability period before steel bars begin to rust can be calculated, thereby obtaining the evaluation result data. Similarly, for other types of objects to be evaluated and other potential aging effect items, they can also be calculated using the corresponding durability time evaluation method, which will not be shown one by one in the examples of this application.

[0132] The nuclear reactor building aging status assessment method described in the above embodiment can determine the assessment scope according to the predetermined function performed by the object to be assessed by applying the technical solution of this embodiment. Then identify the potential aging effect items of the object to be assessed within the assessment scope. And according to the aging effect items, obtain monitoring parameters, and perform aging status assessment on the object to be assessed according to the monitoring parameters to obtain assessment result data. The method can streamline the screening of aging management objects, aging effect identification and aging effect monitoring and inspection processes, combine multiple aging effect items to conduct a comprehensive analysis of the object to be assessed, and systematically assess the aging status of nuclear reactor building structures or construction structures, thereby improving the accuracy of status assessment results.

[0133] Furthermore, as a specific implementation of the nuclear reactor building aging status assessment method, the present application embodiment provides a nuclear reactor building aging status assessment system, such as Figure 7 As shown, the system includes: a sensor and a controller. The controller can establish a communication connection with multiple sensors. The sensors are configured to collect monitoring parameters. The controller is configured to perform the following steps:

[0134] Determining the scope of assessment according to a predetermined function performed by the object to be assessed, wherein the object to be assessed is a structure and / or construction structure in a nuclear reactor building structure; the predetermined function is a safety-related function performed by the object to be assessed in the building structure;

[0135] Identify potential aging effects of the subjects to be evaluated within the scope of the evaluation;

[0136] Acquiring monitoring parameters based on the aging effect item, the monitoring parameters including first-category parameters and second-category parameters, the first-category parameters being obtained by performing aging effect item feature recognition on visual signals of the object to be evaluated; and the second-category parameters being obtained by performing aging effect item feature recognition on electrical detection signals of the object to be evaluated;

[0137] An aging status assessment is performed on the object to be assessed according to the monitoring parameters to obtain assessment result data, wherein the assessment result data includes overall status assessment data and durability time assessment data.

[0138] It should be noted that, for the description of the specific steps executed by the controller involved in the nuclear reactor building aging status assessment system provided in the embodiment of the present application, reference can be made to the corresponding description in the nuclear reactor building aging status assessment method described in the above embodiment, and no further details will be given here.

[0139] like Figure 8As shown, an embodiment of the present application further provides a computer device, which may be a personal computer, a server, a network device, etc. The computer device includes a bus, a processor, a memory, and a communication interface, and may also include an input / output interface and a display device. The processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, a computer program, and a database. The internal memory provides an environment for the operation of the operating system and the computer program in the non-volatile storage medium. The database of the computer device is used to store location information. The network interface of the computer device is used to communicate with an external terminal via a network connection. When the computer program is executed by the processor, the steps in each method embodiment are implemented.

[0140] Those skilled in the art will understand that the structure of the above-mentioned computer device is only a partial structure related to the solution of the present application and does not constitute a limitation on the computer device to which the solution of the present application is applied. The specific computer device may include more or fewer components, or combine certain components, or have a different component arrangement.

[0141] In one embodiment, a computer-readable storage medium is provided. The computer-readable storage medium may be non-volatile or volatile, and stores a computer program thereon. When the computer program is executed by a processor, the steps in the above-mentioned method embodiments are implemented.

[0142] In one embodiment, a computer program product is provided, including a computer program, which implements the steps in the above method embodiments when executed by a processor.

[0143] It should be noted that the user information (including but not limited to user device information, user personal information, etc.) and data (including but not limited to data used for analysis, stored data, displayed data, etc.) involved in this application are all information and data authorized by the user or fully authorized by all parties.

[0144] Those skilled in the art will appreciate that all or part of the processes in the above-mentioned embodiment methods can be implemented by instructing the relevant hardware through a computer program, and the computer program can be stored in a non-volatile computer-readable storage medium. When the computer program is executed, it can include the processes of the embodiments of the above-mentioned methods. Among them, any reference to memory, database or other media used in the embodiments provided in this application may include at least one of non-volatile and volatile memory. Non-volatile memory may include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetic random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory may include random access memory (RAM) or external cache memory, etc. By way of illustration and not limitation, RAM can be in various forms, such as static random access memory (SRAM) or dynamic random access memory (DRAM). The database involved in the various embodiments provided herein may include at least one of a relational database and a non-relational database. Non-relational databases may include, but are not limited to, distributed databases based on blockchains. The processor involved in the various embodiments provided herein may be, but are not limited to, a general-purpose processor, a graphics processor, a digital signal processor, a programmable logic device, a data processing logic device based on quantum computing, and the like.

[0145] The technical features of the above embodiments can be combined arbitrarily. To make the description concise, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0146] The above-described embodiments merely represent several implementation methods of the present application. While the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the present application. It should be noted that a person of ordinary skill in the art may make various modifications and improvements without departing from the spirit of the present application, and these modifications and improvements fall within the scope of protection of the present application. Therefore, the scope of protection of the present application shall be determined by the appended claims.

Claims

1. A method for assessing the aging status of a nuclear reactor building, characterized in that: The method comprises: Determine the scope of assessment according to the predetermined functions performed by the object to be assessed, wherein the object to be assessed is a structure and / or construction structure in the nuclear reactor building structure; the predetermined functions are safety-related functions performed by the object to be assessed in the building structure; the predetermined functions include one or more of the following: support function, heat sink function, equipment protection function, shielding function, pressure boundary function, container function, spatial isolation function, and anti-intrusion barrier function; Identify potential aging effects of the subjects to be evaluated within the scope of the evaluation; According to the aging effect item, monitoring parameters are obtained, and the monitoring parameters include first-category parameters and second-category parameters, the first-category parameters are obtained by performing aging effect item feature recognition on the visual signal of the object to be evaluated; the second-category parameters are obtained by performing aging effect item feature recognition on the electrical detection signal of the object to be evaluated; according to the aging effect item, monitoring parameters are obtained, including: obtaining the visual signal of the object to be evaluated; extracting target features from the visual signal, the target features being the visual features associated with the aging effect item; recording visual performance data of the target features in the visual signal to generate the first-category parameters, the visual performance data including the feature type, feature morphological parameters and feature position associated with the aging effect item; obtaining the sensor type and sensor calibration parameters, the detection calibration parameters being used to characterize the correspondence between the electrical values ​​of the electrical detection signal and the parameter information values; receiving the electrical detection signal collected by the sensor; extracting characteristic signal segments from the electrical detection signal according to the type of the sensor; converting the characteristic signal segments into parameter information according to the sensor calibration parameters to generate the second-category parameters; An aging status assessment is performed on the object to be assessed according to the monitoring parameters to obtain assessment result data, wherein the assessment result data includes overall status assessment data and durability time assessment data; an aging status assessment is performed on the object to be assessed according to the monitoring parameters to obtain assessment result data, including: setting a limit state of the object to be assessed; obtaining structural parameters of the object to be assessed; determining a local environmental coefficient according to a preset environmental action level; and calculating the durability time for the object to be assessed to reach the limit state according to the monitoring parameters, the structural parameters and the local environmental coefficient to generate the durability time assessment data.

2. The method according to claim 1, characterized in that Determine the scope of the assessment based on the intended functions of the entity to be assessed, including: Obtain information on the structural characteristics of the plant; Based on the structural characteristics of the plant, determine the object type and item list of the object to be assessed; The evaluation scope is determined according to whether the object to be evaluated performs a predetermined function.

3. The method according to claim 1, characterized in that Identify potential aging effects on the subjects to be assessed within the scope of the assessment, including: Acquire aging influencing parameters of the plant structure, wherein the aging influencing parameters include material parameters, environmental parameters, and influencing factor parameters of the plant structure; determining a set of aging effect items according to the aging impact parameters; According to the aging effect item set, potential aging effect items of the object to be evaluated within the evaluation scope are identified.

4. The method according to claim 1, wherein Performing an aging status assessment on the object to be assessed according to the monitoring parameters to obtain assessment result data, including: Obtaining the status evaluation interval to which the monitoring parameter belongs; Setting a status evaluation weight according to the status evaluation interval to which the monitoring parameter belongs; Based on the status assessment weights, a weighted summation is performed on the monitoring parameters to generate the overall status assessment data.

5. The method according to any one of claims 1 to 4, characterized in that The objects to be evaluated are: one or more combinations of concrete structures, steel structures, structural expansion joints, masonry structures, equipment foundations, roofs, pools, and component support structures.

6. A nuclear reactor building aging status assessment system, characterized in that: The system includes: a sensor and a controller, wherein the sensor is configured to collect monitoring parameters; The controller is configured to: Determine the scope of assessment according to the predetermined functions performed by the object to be assessed, wherein the object to be assessed is a structure and / or construction structure in the nuclear reactor building structure; the predetermined functions are safety-related functions performed by the object to be assessed in the building structure; the predetermined functions include one or more of the following: support function, heat sink function, equipment protection function, shielding function, pressure boundary function, container function, spatial isolation function, and anti-intrusion barrier function; Identify potential aging effects of the subjects to be evaluated within the scope of the evaluation; According to the aging effect item, monitoring parameters are obtained, and the monitoring parameters include first-category parameters and second-category parameters, the first-category parameters are obtained by performing aging effect item feature recognition on the visual signal of the object to be evaluated; the second-category parameters are obtained by performing aging effect item feature recognition on the electrical detection signal of the object to be evaluated; according to the aging effect item, monitoring parameters are obtained, including: obtaining the visual signal of the object to be evaluated; extracting target features from the visual signal, the target features being the visual features associated with the aging effect item; recording visual performance data of the target features in the visual signal to generate the first-category parameters, the visual performance data including the feature type, feature morphological parameters and feature position associated with the aging effect item; obtaining the sensor type and sensor calibration parameters, the detection calibration parameters being used to characterize the correspondence between the electrical values ​​of the electrical detection signal and the parameter information values; receiving the electrical detection signal collected by the sensor; extracting characteristic signal segments from the electrical detection signal according to the type of the sensor; converting the characteristic signal segments into parameter information according to the sensor calibration parameters to generate the second-category parameters; An aging status assessment is performed on the object to be assessed according to the monitoring parameters to obtain assessment result data, wherein the assessment result data includes overall status assessment data and durability time assessment data; an aging status assessment is performed on the object to be assessed according to the monitoring parameters to obtain assessment result data, including: setting a limit state of the object to be assessed; obtaining structural parameters of the object to be assessed; determining a local environmental coefficient according to a preset environmental action level; and calculating the durability time for the object to be assessed to reach the limit state according to the monitoring parameters, the structural parameters and the local environmental coefficient to generate the durability time assessment data.

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