Method and system for evaluating aging state of nuclear reactor plant

Abstract

The invention discloses a nuclear reactor plant aging state assessment method and system, and the method can determine an assessment range according to a predetermined function executed by a to-be-assessed object. And identifying a potential aging effect item of the to-be-evaluated object in the evaluation range. And obtaining monitoring parameters according to the aging effect item, and performing aging state evaluation on the to-be-evaluated object according to the monitoring parameters to obtain evaluation result data. According to the method, screening, aging effect identification and aging effect monitoring of aging management objects can be processed, comprehensive analysis is performed on the to-be-evaluated object in combination with a plurality of aging effect items, the aging state of the nuclear reactor plant building or the building structure is systematically evaluated, and the accuracy of a state evaluation result is improved.

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 include structures or constructions made of steel and concrete. These structures and constructions will age as they are deployed. When the structure ages to a certain extent, it will affect the safety performance of the nuclear reactor building. Therefore, in order to improve safety performance, the aging status of the nuclear reactor building structure can be evaluated to predict the impact of the aging status on the production process.

[0003] Aging status assessment refers to the systematic analysis and evaluation of the performance degradation process of nuclear reactor building structures or structures caused by environmental factors, materials, etc. Through comprehensive evaluation methods such as structural testing, structural analysis, load testing, and durability testing, it is determined whether the structure or structure can meet the expected performance requirements within its service life and whether it needs to be repaired, reinforced, or replaced.

[0004] However, the assessment of the aging status of nuclear reactor building structures or structures is limited to the single performance assessment of a single structure or a single structure, and it is impossible to obtain accurate overall status assessment results. In addition, there are many interference factors in the process of aging status assessment, which further reduces the accuracy of the status assessment results. Summary of the invention

[0005] In view of this, an embodiment of the present application provides 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] Determine the scope of assessment according to the predetermined function performed by the object to be assessed, wherein the object to be assessed is a structure and / or a construction structure in the 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 subject to be evaluated within the scope of the evaluation;

[0009] According to the aging effect item, monitoring parameters are obtained, the monitoring parameters including 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;

[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 is determined according to 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, the object type and item list of the object to be evaluated are delineated;

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

[0015] Optionally, the predetermined function includes one or more combinations 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 influence 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] Acquire the sensor type and sensor calibration parameters, wherein the detection calibration parameters are used to characterize the corresponding relationship between the electrical value of the electrical detection signal and the parameter information value;

[0026] Receiving 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 the sensor calibration parameters, the characteristic signal segment is converted into parameter information to generate the second type of parameters.

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

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

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

[0037] Based on the status assessment weights, a weighted sum 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] Determine the scope of assessment according to the predetermined function performed by the object to be assessed, wherein the object to be assessed is a structure and / or a construction structure in the 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 subject to be evaluated within the scope of the evaluation;

[0043] According to the aging effect item, monitoring parameters are obtained, the monitoring parameters including 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;

[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 scheme, the 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, 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 of an aging status assessment method 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 a process for determining an evaluation scope provided in an embodiment of the present application is shown;

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

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

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

[0055] Figure 8 A schematic diagram of the structure of a computer device 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 the embodiments and features in the embodiments of the present application can be combined with each other without conflict.

[0057] In the embodiments of the present application, a nuclear reactor is a group of nuclear power plant equipment used to control and maintain nuclear transformation reactions to generate energy. The nuclear reactor has a broad meaning and can include reactors used for formal production of nuclear power plants and research reactors used for research experiments. Depending on the purpose of the nuclear reactor, the reactor and the research reactor have some differences in scale, but both have high requirements for safety.

[0058] Some embodiments of the present application describe the method for assessing the aging status of a nuclear reactor building by taking a research reactor as an example, while other embodiments of the present application describe the method for assessing the aging status of a nuclear reactor building by taking a nuclear reactor that has been formally put into production 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 associated with those skilled in the art based on the embodiments of the present application also fall within the scope of protection of the present application.

[0059] A research reactor refers to a nuclear facility or device such as a research reactor, experimental reactor, critical assembly, and a subcritical system driven by an external source and operating with power, outside a nuclear power plant. Research reactors can be used for scientific research, education, and training. In order to maintain a research reactor, it is necessary to build plant facilities with the nuclear reactor as the core. A research reactor plant is a special facility that provides a safe and efficient operating environment for the research reactor. The research reactor plant can be deployed inside or around the reactor, using the reactor neutron flux and ionizing radiation beam for research, development, isotope production, and other work. The research reactor is an important scientific research and experimental application platform that can be used for basic research in neutron physics, research on the irradiation performance of reactor fuel and materials, and research and development of radioactive isotope irradiation.

[0060] The design of the research reactor building must follow strict safety regulations to ensure that a controlled chain reaction can be maintained under any circumstances and to provide conditions for the layout and composition of the research core. These regulations include preventive measures for accident conditions and the design of multiple safety systems. The research reactor building can include a main building and a secondary building. 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 needs to take into account factors such as radiation protection, heat resistance and structural strength. Therefore, the main research reactor building is constructed with special reinforced concrete and other materials to ensure adequate protection and safety.

[0061] Since the main plant of the research reactor adopts a large number of reinforced concrete structures, the reinforced concrete structures will age after being built as the service time increases, that is, the main plant of the research reactor will show different degrees of aging under different service time. The aging state can include freeze-thaw, cracks, melting, carbonization, etc. caused by environmental factors; the destruction of bonding components caused by chemical changes in concrete; the loss of tensile strength and component failure caused by steel corrosion; and the tiny cracks on the surface of the concrete may extend inward due to the influence of rain, ice and salt weather, further corroding cracks and leakage.

[0062] In order to reduce the impact of aging on the safety of research reactor buildings, it is necessary to regularly inspect and evaluate the aging status. Aging status assessment refers to the systematic analysis and evaluation of the performance degradation process of nuclear reactor building structures or structures caused by environmental factors, materials and other factors. Through comprehensive evaluation methods such as structural inspection, structural analysis, load testing, and durability testing, it is determined whether the structure or structure can meet the expected performance requirements within its service life, and whether it needs to be repaired, reinforced or replaced.

[0063] To this end, a method for assessing the aging state of a nuclear reactor building is provided in this embodiment, and the method can be applied to an aging state assessment system for a nuclear reactor building. The aging state assessment system for a nuclear reactor building is a software and hardware platform that performs aging state assessment according to user input or sensor detection data, and displays the aging state assessment results. The aging state assessment system for a nuclear reactor building can rely on computers, mobile terminals, servers, industrial hosts, smart wearable devices, etc. to provide users with a human-computer interaction interface, and perform operations such as collection, processing, transmission, and storage on relevant data based on the provided human-computer interaction interface in response to user input to meet specific user needs.

[0064] In a feasible implementation, the nuclear reactor building aging status assessment system can be operated by 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 with a built-in aging status assessment algorithm. When performing the aging status assessment, the computer can obtain the monitoring data input by the user and / or collected by the sensor, and call the assessment model to perform an assessment on the monitoring data to obtain the 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 and multiple clients and multiple sensors connected to the server. The multiple sensors can be used to collect monitoring data of different regions or different types. Multiple clients can be operated by different users respectively, and the interactive data generated by the operation can be sent to the server through the network to request the server to collect, process, evaluate, distribute and store the evaluation results of the monitoring data. After receiving the evaluation result data distributed by the server, the client displays the evaluation result data based on the 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 status evaluation method. Unless otherwise specified, the aging status evaluation method can be implemented by running relevant applications on a client such as a computer, or by running relevant applications on a server, or by cooperating with a client to run relevant applications. Therefore, from the description process of the execution subject, the steps corresponding to the aging status evaluation 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 object to be evaluated is the structure and / or construction structure in the nuclear reactor building structure. The structure refers to an independent building or independent component built of steel structure or concrete structure in the nuclear reactor building. The construction structure refers to a part of an independent building that has an impact on the overall safety of the building structure.

[0070] In a feasible implementation, since in the design of nuclear reactor buildings, concrete structures, steel structures, structural expansion joints, masonry structures, equipment foundations, roofs, pools, and component support structures have a great impact on the overall safety of nuclear reactors, safety-important structures or constructions can be determined based on the design functions of safety-important structures or constructions of nuclear reactor buildings. That is, 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.

[0071] For the object to be evaluated, the evaluation scope can be determined according to the predetermined function performed. The predetermined function is a safety-related function performed by the object to be evaluated in the plant structure. In some embodiments, 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.

[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 leakage prevention 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 may include fire barrier functions, flood barrier functions, and missile barrier functions. The fire barrier function is a function to control the fire or prevent the fire from spreading to adjacent areas of the power plant. The flood barrier is a barrier that provides protection against flooding in the event of internal or external flooding. The missile barrier is a function that provides protection against internal or external missiles.

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

[0075] Among them, the evaluation scope of durability influencing factors includes the 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 in 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 the structural use function includes the specific use function 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 the structural use function is also different in different evaluation processes. The evaluation scope of the structural layout involves the layout of the structure, which is used to determine the degree of influence on the durability and aging state based on the layout of the specific structure.

[0076] like Figure 4 As shown, in order to determine the evaluation scope, in a feasible implementation, the plant structure characteristic information can be first obtained, and then the object type and item list of the object to be evaluated can be delineated according to the plant structure characteristic information. And the evaluation scope can be determined according to whether the object to be evaluated performs a predetermined function.

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

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

[0079] After determining the evaluation scope, the aging status evaluation system can identify the potential aging effect items of the object to be evaluated within the evaluation scope based on a specific evaluation algorithm. Among them, the specific evaluation algorithm can be the "material-environment-influence factor" analysis method and the predetermined function loss analysis method. After determining the evaluation scope, the aging effect that needs to be evaluated for the object to be evaluated can be determined within the detailed evaluation scope based on the "material-environment-influence factor" analysis method and the predetermined function loss analysis method.

[0080] In some embodiments, the potential aging effect item is also referred to as a potential aging effect mechanism, and may include one or more combinations of the following specific potential aging effect items. That is: strength and modulus reduction effect caused by high temperature, strength and modulus reduction when normal temperature is >150°F and local temperature is >200°F. Cracking caused by aggregate expansion reaction. Increased porosity and permeability and strength loss caused by calcium hydroxide leaching and carbonization. Cracking, bond loss and material loss caused by erosion of embedded steel bars. Material loss and cracking caused by freezing and thawing. Material loss and cracking caused by severe chemical erosion. Among them, material loss refers to aging phenomena such as peeling and spalling. Cracking and deformation caused by increased stress levels of settlement. Decreased foundation strength and cracking caused by 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 environment. Cracking caused by suppressed shrinkage, creep and harsh environment. 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] In order to identify the potential aging effect items of the object to be evaluated, the aging status assessment system can first obtain the aging influence parameters of the plant structure. Then determine the aging effect item set according to the aging influence parameters, and identify the potential aging effect items of the object to be evaluated within the assessment scope according to the aging effect item set. Among them, the aging influence 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 main building of the research reactor, including concrete structures, steel structures, structural expansion joints, masonry structures, equipment foundations, roofs, pools, and component supports, can be identified. Based on the actual materials and environment of these eight types of structures combined with the analysis of influencing factors, the potential aging effect items of each structure can be determined to form an aging effect item set. In the subsequent analysis process, the "material-environment-influencing factor" analysis method is used to determine the potential aging effect items one by one in the aging effect item set, and then determine the 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 according to the visual signal detection method, that is, 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 monitoring parameters obtained according to the laboratory special detection method, that is, the second-category parameters are obtained by performing aging effect item 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 recognized, and specific and achievable on-site visual signal detection methods and laboratory special detection methods can be selected according to industry experience and standards.

[0086] In some embodiments, for the on-site visual signal detection method, the visual signal of the object to be evaluated can be first obtained. Then, the target feature is extracted from the visual signal. Among them, the target feature is the visual feature associated with the aging effect item. Then, the visual performance data of the target feature in the visual signal is recorded to generate the first type of parameters. In the recorded target feature, the visual performance data includes the feature type, feature morphological parameters and feature position associated with the aging effect item.

[0087] For example, according to the aging effect detection method specified in the nuclear reactor plant equipment aging management outline, the object to be evaluated can be visually inspected in multiple dimensions by collecting on-site visual signals. The specific content of visual inspection can include one or more combinations of the following inspection items:

[0088] For the beams, slabs, columns and walls of concrete structures, inspections are carried out on problems including concrete surface cracking, peeling, expansion cracking, hollowing, wear and chemical erosion, concrete anchor rusting and surrounding local concrete cracking, steel bar rusting and reinforcement leakage.

[0089] For the factory building foundation with concrete structure, when there is an opportunity to excavate, perform visual signal detection on the exposed concrete entity, including detection of the moisture-proof layer of the foundation and the exterior wall below the floor.

[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 coating of steel structures, etc.

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

[0092] For structural expansion joints, inspections are carried out on phenomena such as hardening, tearing, cracking and defects of sealing materials at expansion joints, debonding and peeling between sealing materials and concrete on both sides of expansion joints, deformation and damage of steel plates at expansion joints, debonding and cracking of expansion joint membranes, leakage and water accumulation at expansion joint nodes, etc.

[0093] Inspections are carried out on the equipment foundation, 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 tested for surface cracks and fissures, shedding and aging of silicone weather-resistant sealant, water accumulation on the roof, bulging of the roof, aging and missing of the waterproof gaskets that come with the fastening screws at the roof joints, and water seepage on the roof.

[0095] The pool structure is inspected for cracks and peeling 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 misalignment of supports, etc.

[0097] According to the determined object to be evaluated and the identified potential aging effect items, image sensors, infrared cameras, ultrasonic detection sensors, laser radars and other devices used to detect visual signals can be used to collect images of the object to be evaluated. The collected image data is then input into the image analysis model, and the image analysis model is used to extract visual features associated with aging effect items from the image data.

[0098] For example, when the object to be evaluated is a concrete structure and the potential aging effect item identified is the concrete surface cracking item, the concrete surface can be photographed with a conventional camera to obtain a concrete surface image. Then, based on the crack detection model, the crack features are extracted from the concrete surface image according to the image pixel values, and then the degree of cracking on the concrete surface is determined according to the visual performance data of the crack features. Among them, the visual performance data of the crack features may include the number of cracks contained in the concrete surface image, the crack position, the crack length, the crack width, etc. These visual performance data can be calculated through parameters such as the number of pixels contained in the crack features and the focal length of the camera.

[0099] In some embodiments, for laboratory special detection methods, the sensor type and sensor calibration parameters can be obtained first. Among them, 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 the 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 may be received, and then a characteristic signal segment may be extracted from the electrical detection signal according to the type of the sensor, and the characteristic signal segment may 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 method specified in the nuclear reactor plant equipment aging management outline, the object to be evaluated can be tested in multiple dimensions through laboratory special testing methods. Similarly, when conducting laboratory special testing, the specific content of the test can include one or more combinations of the following test items:

[0103] For beams, slabs, columns and walls of concrete structures, crack detection instruments can be used to detect 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 plant to obtain abnormal temperature points in the plant.

[0104] The concrete rebound tester is used to test the concrete strength, and the brick rebound tester is used to conduct on-site testing of the compressive strength of the masonry bricks in the powerhouse masonry. The mortar rebound tester can also be used to conduct on-site testing of the compressive strength of the masonry mortar in the powerhouse masonry. When conducting the compressive strength test, the core drilling verification method can be used to conduct sampling testing on the concrete structure of the main powerhouse of the research reactor, that is, the core drilling verification method is used to test the concrete strength, and the rebound method is used to estimate the strength.

[0105] The concrete permeability is tested by using a concrete permeameter, and the Permea air permeability meter can be used to measure the change in air pressure per unit time to evaluate the concrete's anti-permeability performance. When testing the concrete permeability of the main building of the research reactor, batches can be divided according to different concrete design strength grades, and 6 components are selected from each batch for concrete permeability testing to obtain the concrete permeability coefficient and grade.

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

[0107] The steel bar corrosion tester is used to detect the steel bar corrosion condition. When testing the concrete steel bar corrosion condition of the main powerhouse of the research reactor, the single electrode method can be used to sample the concrete corrosion condition and obtain the steel bar potential condition.

[0108] Laboratory analysis is used to detect the chloride ion content of concrete. A concrete carbonation tester is used to detect the carbonation depth of concrete. Laboratory analysis is used to detect the alkali content of concrete. Concrete petrographic analysis is used to detect the alkali aggregate activity of concrete. A total station is used to detect 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 by using 1% to 2% phenolphthalein alcohol solution. It can also be divided into batches according to the segmentation of the plant, with wall panels as one category and beams and columns as another category.

[0112] The concrete components of the plant were sampled and analyzed for chloride ion content using a water drill. The samples were drilled using a water drill and special grinding tools for aggregate petrographic analysis and alkali content testing.

[0113] Distance sensors can also be used to check on-site deformations such as concrete tilt and deflection, and on-site deformations such as wall flash and tilt. A total station is used to detect the tilt of the main body of the plant, and the tilt detection point is arranged at the outer corner of the plant.

[0114] In addition, the 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 obtaining the above monitoring parameters, in some embodiments, the environment and data of the main plant of the research reactor can also be obtained, and the acquired data include: plant location, construction period, main material, plant elevation, building area, overall structure, climate of the area where the plant is located, annual average temperature, annual average relative humidity, annual average rainfall, main aging mechanism, etc. The acquired data can be used to assist in aging status assessment to obtain 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, the aging state evaluation can be performed on the object to be evaluated according to the monitoring parameters according to the "material-environment-influencing factor" analysis method and the predetermined function loss analysis method to obtain the evaluation result data. The overall state evaluation data can be obtained based on the "material-environment-influencing factor" analysis method. And the durability time evaluation data can be obtained based on the predetermined function loss analysis law. Therefore, the evaluation result data includes the overall state evaluation data and the durability time evaluation data.

[0118] Among them, for the "material-environment-influencing factor" analysis method, after obtaining the monitoring parameters, the durability influencing factors can be determined first, that is, the durability influencing factors can be identified, 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, electric 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, damage degree, and remaining service life of concrete, comprehensively judge the safety and reliability of concrete.

[0119] In some embodiments, the overall status assessment data obtained based on the "material-environment-influencing factor" 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 aging status evaluation on the object to be evaluated according to the monitoring parameters to obtain evaluation result data, the status evaluation interval to which the monitoring parameters belong can be first obtained. Then, the status evaluation weight is set according to the status evaluation interval to which the monitoring parameters belong. And based on the status evaluation weight, the monitoring parameters are weighted summed to generate the overall status evaluation 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 the 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 aging state evaluation on the object to be evaluated according to the monitoring parameters to obtain evaluation result data further includes: setting the limit state of the object to be evaluated, obtaining the structural parameters of the object to be evaluated, and determining the local environmental coefficient according to the preset environmental action level. Then, according to the monitoring parameters, the structural parameters and the local environmental coefficient, the durability time of the object to be evaluated to reach the limit state is calculated to generate the durability time evaluation data.

[0121] For example, the durability assessment is carried out with the beginning of corrosion of the steel bars of the concrete component as the limit state. The durability of the beginning of corrosion of the steel bars can be calculated using the following formula:

[0122]

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

[0124]

[0125] f2 is the coefficient of influence of protective layer thickness on the durability of steel bar corrosion. c is the thickness of 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 calculation formula of f3 is as follows:

[0130]

[0131] Based on the above formula, the durability years of steel bar corrosion can be calculated to obtain the evaluation result data. Similarly, for other types of objects to be evaluated and other potential aging effect items, they can also be calculated according to the corresponding durability time evaluation method, which will not be shown one by one in the embodiments 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 functions performed by the object to be assessed by applying the technical solution of this embodiment. Re-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, 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] Further, 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 sensor is configured to collect monitoring parameters. The controller is configured to perform the following steps:

[0134] Determine the scope of assessment according to the predetermined function performed by the object to be assessed, wherein the object to be assessed is a structure and / or a construction structure in the 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 subject to be evaluated within the scope of the evaluation;

[0136] According to the aging effect item, monitoring parameters are obtained, the monitoring parameters including 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;

[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 will not be repeated here.

[0139] like Figure 8As shown, the embodiment of the present application also provides a computer device, which can be specifically a personal computer, a server, a network device, etc. The computer device includes a bus, a processor, a memory and a communication interface, and can also include an input and output interface and a display device. Among them, 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 through 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 appreciate 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 arrangement of components.

[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 can understand that all or part of the processes in the above-mentioned embodiment methods can be completed 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 the memory, database or other medium used in the embodiments provided in the present application can include at least one of non-volatile and volatile memory. Non-volatile memory can include read-only memory (ROM), magnetic tape, floppy disk, flash memory, optical memory, high-density embedded non-volatile memory, resistive random access memory (ReRAM), magnetoresistive random access memory (MRAM), ferroelectric random access memory (FRAM), phase change memory (PCM), graphene memory, etc. Volatile memory can include random access memory (RAM) or external cache memory, etc. As an 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 each embodiment provided in this application may include at least one of a relational database and a non-relational database. Non-relational databases may include distributed databases based on blockchains, etc., but are not limited to this. The processor involved in each embodiment provided in this application may be a general-purpose processor, a graphics processor, a digital signal processor, a programmable logic device, a data processing logic device based on quantum computing, etc., but are not limited to this.

[0145] The technical features of the above embodiments may 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 only express several implementation methods of the present application, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the scope of the present application. It should be pointed out that, for a person of ordinary skill in the art, several variations and improvements can be made without departing from the concept of the present application, and these all belong to the protection scope of the present application. Therefore, the protection scope of the present application shall be subject to the attached 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 function performed by the object to be assessed, wherein the object to be assessed is a structure and / or a construction structure in the nuclear reactor building structure; the predetermined function is a safety-related function performed by the object to be assessed in the building structure; Identify potential aging effects of the subject to be evaluated within the scope of the evaluation; According to the aging effect item, monitoring parameters are obtained, the monitoring parameters including 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; 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.

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

3. The method according to claim 2, characterized in that The predetermined functions include one or more combinations of support functions, heat sink functions, equipment protection functions, shielding functions, pressure boundary functions, container functions, space isolation functions, and anti-intrusion barrier functions.

4. The method according to claim 1, characterized in that: Identify potential aging effects of the subjects to be evaluated 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 influence parameters; According to the aging effect item set, potential aging effect items of the object to be evaluated within the evaluation scope are identified.

5. The method according to claim 1, characterized in that According to the aging effect item, monitoring parameters are obtained, including: Acquiring a visual signal of the object to be evaluated; extracting a target feature from the visual signal, wherein the target feature is a visual feature associated with the aging effect term; 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.

6. The method according to claim 1, characterized in that According to the aging effect item, monitoring parameters are obtained, including: Acquire the sensor type and sensor calibration parameters, wherein the detection calibration parameters are used to characterize the corresponding relationship between the electrical value of the electrical detection signal and the parameter information value; Receiving electrical detection signals collected by sensors; extracting a characteristic signal segment from the electrical detection signal according to the type of the sensor; According to the sensor calibration parameters, the characteristic signal segment is converted into parameter information to generate the second type of parameters.

7. The method according to claim 1, characterized in that Performing an aging status assessment on the object to be assessed according to the monitoring parameters to obtain assessment result data, including: Setting the limit state of the object to be evaluated; Obtaining structural parameters of the object to be evaluated; Determine the local environmental coefficient according to the preset environmental action level; 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.

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

9. The method according to any one of claims 1 to 8, 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.

10. 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 function performed by the object to be assessed, wherein the object to be assessed is a structure and / or a construction structure in the nuclear reactor building structure; the predetermined function is a safety-related function performed by the object to be assessed in the building structure; Identify potential aging effects of the subject to be evaluated within the scope of the evaluation; According to the aging effect item, monitoring parameters are obtained, the monitoring parameters including 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; 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.

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