A method and device for obtaining and comparing structural parameters of a nuclear power plant containment

Abstract

The embodiment of the application provides a method and device for obtaining and comparing structural parameters of a nuclear power plant containment, comprising: obtaining a concrete elastic modulus, a concrete aging coefficient and a concrete creep coefficient of the nuclear power plant containment; obtaining an age-adjusted effective modulus according to the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient according to a preset rule; and obtaining a strain and displacement theoretical value when a sealing test is performed on a containment with different service lives, so that the structural deformation of the containment with different service lives during the sealing test can be predicted, the pressure test can be guided, and the safety of the test process can be ensured.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear power technology, and in particular to a method for obtaining structural parameters of a containment of a nuclear power plant, a method for comparing structural parameters of a containment of a nuclear power plant, an apparatus for obtaining structural parameters of a containment of a nuclear power plant, an apparatus for comparing structural parameters of a containment of a nuclear power plant, a computer device, and a storage medium. BACKGROUND

[0002] Energy is the basis of social operation and economic development, and is a basic element of human life and production. With the development of society and the continuous improvement of people's living standards, people's demand for energy is also expanding year by year. Globally, at present, nuclear power, together with hydropower and thermal power, jointly constitutes the three major industry pillars of the world's electricity. Nuclear energy has large unit energy and abundant resources, and is the only economic, safe and clean energy that can replace conventional energy on a large scale. At present, there are 62 nuclear power units in China, of which 47 units have been loaded and put into operation, with a total installed capacity of 44645.16 MWe, distributed in 18 nuclear power plants. With the construction of nuclear power plants in China entering a period of rapid development, and the trend of nuclear power plants developing from the coast to the inland, the safety requirements of nuclear power plants have reached an unprecedented height, and ensuring the safety of nuclear power plants is the primary political responsibility.

[0003] The containment, as the third barrier of nuclear safety and the last barrier to prevent the leakage of radioactive substances, must be able to withstand high energy loads caused by severe accidents, so it needs to be regularly tested as a whole after its construction is completed and during its operation period to evaluate the sealing performance of the containment body and the safety of the structure. However, at present in the industry, when the containment is tested as a whole, the elastic modulus and other characteristic parameters of the concrete are not easy to measure, so the strain and displacement information monitored cannot be accurately estimated (time-varying effects cannot be considered), which makes it impossible to accurately grasp the structure state during the test, and the measured data lacks comparison and verification, so it is difficult to accurately evaluate the performance of the containment. SUMMARY

[0004] In view of the above problems, the present application embodiments are proposed to provide a method for obtaining structural parameters of a containment of a nuclear power plant, a method for comparing structural parameters of a containment of a nuclear power plant, an apparatus for obtaining structural parameters of a containment of a nuclear power plant, an apparatus for comparing structural parameters of a containment of a nuclear power plant, a computer device, and a storage medium, which overcome the above problems or at least partially solve the above problems.

[0005] To solve the above problems, the present application embodiments disclose a method for obtaining structural parameters of a containment of a nuclear power plant, comprising:

[0006] The concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient of the nuclear power plant containment are obtained.

[0007] The age-adjusted effective modulus is obtained according to the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient according to a preset rule.

[0008] Preferably, the step of obtaining the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient of the nuclear power plant containment comprises:

[0009] The concrete basic creep coefficient and the concrete dry creep coefficient of the nuclear power plant containment are obtained.

[0010] The concrete creep coefficient is obtained according to the basic creep coefficient and the concrete dry creep coefficient.

[0011] Preferably, the step of obtaining the concrete basic creep coefficient and the concrete dry creep coefficient of the nuclear power plant containment comprises:

[0012] The ultimate creep coefficient of the basic creep of the silica fume concrete or the non-silica fume concrete and the first concrete adjustment coefficient are obtained.

[0013] And, the time parameter for the concrete is obtained.

[0014] The concrete basic creep coefficient is obtained according to the ultimate creep coefficient of the basic creep, the first concrete adjustment coefficient, and the time parameter.

[0015] Preferably, the step of obtaining the concrete basic creep coefficient and the concrete dry creep coefficient of the nuclear power plant containment comprises:

[0016] The initial creep coefficient of the silica fume concrete or the non-silica fume concrete is obtained.

[0017] And, the concrete dry shrinkage strain at different times is obtained.

[0018] The concrete dry creep coefficient is obtained according to the initial creep coefficient and the concrete dry shrinkage strain.

[0019] Preferably, the step of obtaining the ultimate creep coefficient of the basic creep of the silica fume concrete or the non-silica fume concrete and the first concrete adjustment coefficient comprises:

[0020] The average value of the compressive strength of the concrete cylinder at a certain time and the characteristic value of the compressive strength of the concrete cylinder are obtained.

[0021] The first concrete adjustment coefficient is calculated according to the average value of the compressive strength of the concrete cylinder and the characteristic value of the compressive strength of the concrete cylinder.

[0022] The embodiment of the application discloses a comparison method of structural parameters of a nuclear power plant containment, comprising:

[0023] Request data is obtained from a three-dimensional model system of the nuclear power plant containment; wherein the request data comprises coordinate data;

[0024] A measuring point image is generated by associating the coordinate data with measuring points of the containment;

[0025] An age-adjusted effective modulus of the structure is calculated;

[0026] Theoretical values of strain and displacement are obtained according to the age-adjusted effective modulus;

[0027] The theoretical values of strain and displacement are compared with actual values of strain and displacement to obtain a comparison result.

[0028] Preferably, the method further comprises:

[0029] Data uniqueness checking is performed on the request data to obtain a checking result.

[0030] Preferably, the step of associating the coordinate data with the measuring points of the containment to generate the measuring point image comprises:

[0031] Structured data is generated by associating the device data;

[0032] An index relationship is established between graphics obtained from the three-dimensional model system and the coordinate data to generate the measuring point image.

[0033] The embodiment of the application discloses a structural parameter acquisition device for a nuclear power plant containment, comprising:

[0034] A first acquisition module is configured to acquire a concrete elastic modulus, a concrete aging coefficient and a concrete creep coefficient of the nuclear power plant containment;

[0035] An age-adjusted effective modulus obtaining module is configured to obtain an age-adjusted effective modulus according to the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient according to a preset rule.

[0036] The embodiment of the application discloses a comparison device for structural parameters of a nuclear power plant containment, comprising:

[0037] A request data acquisition module is configured to obtain request data from a three-dimensional model system of the nuclear power plant containment; wherein the request data comprises coordinate data;

[0038] A measuring point image generation module is configured to associate the coordinate data with measuring points of the containment to generate a measuring point image;

[0039] A calculation module is configured to calculate an age-adjusted effective modulus of the structure;

[0040] A strain and displacement theoretical value acquisition module is configured to obtain strain and displacement theoretical values according to the age-adjusted effective modulus.

[0041] A comparison module is configured to compare the strain and displacement theoretical values with strain and displacement actual values to obtain a comparison result.

[0042] The embodiment of the present application discloses a computer device, comprising a memory and a processor, the memory stores a computer program, and the processor implements the steps of the structure parameter acquisition and comparison method of the nuclear power plant containment when executing the computer program.

[0043] The embodiment of the present application discloses a computer readable storage medium, which stores a computer program, and the computer program implements the steps of the structure parameter acquisition and comparison method of the nuclear power plant containment when executed by a processor.

[0044] The embodiment of the present application has the following advantages:

[0045] In the embodiment of the present application, the structure parameter acquisition method of the nuclear power plant containment comprises: acquiring a concrete elastic modulus, a concrete aging coefficient and a concrete creep coefficient of the nuclear power plant containment; and obtaining an age-adjusted effective modulus according to the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient according to a preset rule.

[0046] The nuclear power plant containment time-varying effect analysis system of the embodiment of the present application encapsulates the structure calculation results of different years, different pressures and different instruments, can realize convenient and fast query function and comparison analysis function, can discover data abnormalities and structure damage in time, and can evaluate structure safety. BRIEF DESCRIPTION OF DRAWINGS

[0047] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings needed to be used in the embodiments will be briefly introduced. Obviously, the drawings in the following description only constitute some embodiments of the present application, and for those skilled in the art, other drawings can be obtained based on these drawings without creative effort

[0048] Figure 1 is a step flow chart of a structure parameter acquisition method of a nuclear power plant containment of an embodiment of the present application;

[0049] Figure 2 is a flowchart of an acquisition step of an embodiment of the present application;

[0050] Figure 3 is a flowchart of an acquisition step of an embodiment of the present application;

[0051] Figure 4 is a flowchart of an acquisition step of an embodiment of the present application;

[0052] Figure 5 is a flowchart of an acquisition step of an embodiment of the present application;

[0053] Figure 6 is a step flow chart of a structure parameter comparison method of a nuclear power plant containment of an embodiment of the present application;

[0054] Figure 7 is a structure block diagram of a structure parameter acquisition device of a nuclear power plant containment of an embodiment of the present application;

[0055] Figure 8 is a structure block diagram of a structure parameter comparison device of a nuclear power plant containment of an embodiment of the present application;

[0056] Figure 9 is an internal structure diagram of a computer device of an embodiment. DETAILED DESCRIPTION

[0057] In order to make the technical problems, technical solutions and beneficial effects solved by the embodiments of the present application more clearly understood, the embodiments of the present application will be further described in detail below with reference to the drawings and embodiments. It should be understood that the specific embodiments described herein are only used to explain the present application, and are not used to limit the present application.

[0058] Referring to Figure 1 , a step flow chart of a structure parameter acquisition method of a nuclear power plant containment of an embodiment of the present application is shown, which can specifically include the following steps:

[0059] In step 101, the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient of the nuclear power plant containment are obtained.

[0060] In the embodiment of the present application, the time-varying effect analysis system of the nuclear power plant containment can first obtain the relevant parameters of the concrete of the nuclear power plant containment, such as the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient, and the present application does not make too many limitations on this.

[0061] In step 102, the age-adjusted effective modulus is obtained according to the preset rule based on the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient.

[0062] Further, after obtaining the above parameters, the time-varying effect analysis system of the nuclear power plant containment can calculate the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient according to the preset rule, obtain the age-adjusted effective modulus of the nuclear power plant containment, and then take the age-adjusted effective modulus as an input value, adjust the environmental parameters, and perform finite element analysis to obtain the theoretical value of strain and displacement.

[0063] The preset rule can be any preset rule set by the technician, such as the product of the concrete elastic modulus divided by 1 plus the concrete aging coefficient and the concrete creep coefficient, as shown in formula 1.

[0064]

[0065] In formula 1, E c (t,t0) is called the age-adjusted effective modulus; E c (t0) is the elastic modulus of the concrete loaded at t0, which can be a fixed value; χ(t,t0) is called the concrete aging coefficient, which can generally take a value of 0.8; is the concrete creep coefficient.

[0066] The above formula (1) is only an example of the embodiment of the present application, and the age-adjusted effective modulus can also be calculated by other preset rules. The age-adjusted effective modulus is input into the time-varying effect analysis system of the nuclear power plant containment to obtain the comparison result, realize the effect of considering the time-varying loss of the equivalent elastic modulus of the concrete, and improve the accuracy of the overall test value of the containment. The present application does not make too many limitations on the specific composition and mutual relationship of the preset rule.

[0067] The method for obtaining the structural parameters of the nuclear power plant containment in the embodiment comprises: obtaining a concrete elastic modulus, a concrete aging coefficient and a concrete creep coefficient of the nuclear power plant containment; and obtaining an effective modulus adjusted according to the age according to the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient according to a preset rule. In the embodiment, the strain and displacement information considering the time-varying effect are considered in the calculation, the structural state of the containment is accurately mastered, the containment structure calculation and analysis method considering the time-varying effect of the structure is proposed, the aging of the concrete and the time-varying loss of the prestressed reinforcement are considered in the model calculation, the theoretical values of the strain and displacement of the containment with different service lives during the sealing test are obtained, and thus the structural deformation of the containment with different service lives during the sealing test can be predicted, the pressure test is guided, and the safety of the test process is ensured.

[0068] In one embodiment, referring to Figure 2 , a flowchart of an obtaining step of an embodiment of the present application is shown, comprising:

[0069] Step S11, obtaining a basic creep coefficient of concrete and a dry creep coefficient of concrete of the nuclear power plant containment.

[0070] Step S12, obtaining the concrete creep coefficient according to the basic creep coefficient and the dry creep coefficient of concrete.

[0071] In one practical application, the nuclear power plant containment time-varying effect analysis system can obtain the basic creep coefficient of concrete and the dry creep coefficient of concrete, and then obtain the concrete creep coefficient according to the basic creep coefficient and the dry creep coefficient of concrete. For example, the sum of the basic creep coefficient and the dry creep coefficient of concrete can be taken as the concrete creep coefficient.

[0072] For example, as shown in formula (2), is the basic creep coefficient; is the dry creep coefficient;

[0073]

[0074] In one embodiment, referring to Figure 3 , a flowchart of an obtaining step of an embodiment of the present application is shown, comprising:

[0075] Step S21, obtaining a basic creep ultimate creep coefficient and a first concrete adjustment coefficient of the basic creep of silica ash concrete or non-silica ash concrete.

[0076] Specifically applied to the embodiment of the present application, the time-varying effect analysis system of the nuclear power plant containment can also obtain the ultimate creep coefficient of the basic creep of silica ash concrete or non-silica ash concrete; and obtain the first concrete adjustment coefficient; wherein the first concrete adjustment system can be the first concrete adjustment coefficient under the silica ash concrete or non-silica ash concrete.

[0077] Step S22, obtaining the time parameter for the concrete;

[0078] Further applied to the embodiment of the present application, the time parameter for the containment concrete can be obtained, such as t o Or t1, etc.

[0079] Step S23, obtaining the basic creep coefficient of the concrete according to the ultimate creep coefficient of the basic creep, the first concrete adjustment coefficient and the time parameter.

[0080] In the embodiment of the present application, the basic creep coefficient of the concrete can be calculated according to the ultimate creep coefficient of the basic creep, the first concrete adjustment coefficient and the time parameter.

[0081] For example, the basic creep coefficient of the concrete is As shown in formula (3),

[0082]

[0083] Wherein, the difference between the to moment and the t moment can be the time passed by the concrete, ψ bo Refers to the ultimate creep coefficient of the basic creep, and β bc Is the first concrete adjustment coefficient, and the basic creep coefficient of the concrete can be calculated by formula (3).

[0084] Wherein, ψ bo Can be shown as formula (4),

[0085]

[0086] f cm (t0) is the average value of the compressive strength of the concrete cylinder at t0 moment;

[0087] In another embodiment, the basic creep coefficient of the concrete can also be obtained by other preset rules (i.e. calculation formula), and the embodiment of the present application does not make too many limitations.

[0088] In one embodiment, referring to Figure 4 , a flowchart of an obtaining step of an embodiment of the present application is shown, which includes:

[0089] Step S31, obtaining the average value of the compressive strength of the concrete cylinder at a certain time, and the characteristic value of the compressive strength of the concrete cylinder;

[0090] Step S32, calculating the first concrete adjustment coefficient according to the average value of the compressive strength of the concrete cylinder and the characteristic value of the compressive strength of the concrete cylinder.

[0091] On the other hand, the first concrete adjustment coefficient β bc may be calculated by f cm (t0) and f ck according to formula (5).

[0092]

[0093] f ck is the characteristic value of the compressive strength of the concrete cylinder;

[0094] f cm (t0) is the average value of the compressive strength of the concrete cylinder at t0;

[0095] In one embodiment, referring to Figure 5 , a flowchart of an acquisition step of an embodiment of the present application is shown, which includes:

[0096] Step S41, obtaining the initial creep coefficient of silica fume concrete or non-silica fume concrete;

[0097] Specifically, the containment time-varying effect analysis system of the nuclear power plant can obtain the initial creep coefficient of silica fume concrete or non-silica fume concrete, and obtain different coefficients according to different types of concrete, thereby ensuring the accuracy of the data; as shown in formula (6), ψ do is the initial creep coefficient.

[0098]

[0099] Step S42, obtaining the concrete dry shrinkage strain at different times;

[0100] Further applied to the embodiment of the present application, the concrete dry shrinkage strain ε cd (t) at different times can also be obtained.

[0101] Specifically, referring to formula (7), the concrete dry shrinkage strain ε cd (t) can be obtained.

[0102]

[0103] The second concrete adjustment coefficient is shown in formula (8),

[0104] The third concrete adjustment coefficient is shown in formula (9)

[0105] f ck is the characteristic value of the compressive strength of the concrete cylinder;

[0106] The environmental relative humidity value is RH;

[0107] h0 is the nominal size of the member cross section;

[0108] The difference between the time ts and the time t can also be the elapsed time of the concrete;

[0109] In step S43, the initial creep coefficient and the concrete dry shrinkage strain are used to obtain the concrete dry creep coefficient.

[0110] Finally, the initial creep coefficient and the concrete dry shrinkage strain are obtained, and the concrete dry creep coefficient can be calculated;

[0111] Specifically, as shown in formula (10),

[0112]

[0113] The concrete dry creep coefficient can be obtained by multiplying the initial creep coefficient and the difference between the concrete dry shrinkage strains at different specific times.

[0114] Referring to Figure 6 , a step flow chart of an embodiment of a comparison method for structural parameters of a nuclear power plant containment is shown, and can specifically include the following steps:

[0115] In step 201, request data is obtained from a three-dimensional model system of the nuclear power plant containment; wherein the request data includes coordinate data;

[0116] In the embodiment, the three-dimensional model system refers to a virtual three-dimensional model of the nuclear power plant containment, and different data acquisition devices are arranged at different positions on the nuclear power plant containment. The data acquisition devices can include various devices such as sensors, and the embodiment does not make excessive limitations thereon. The position of the sensor on the nuclear power plant containment is a measurement point, and the data acquisition device can acquire various data such as node number, X coordinate, Y coordinate, Z coordinate, radial displacement, tangential displacement, vertical displacement, total displacement, radial strain, tangential strain, vertical strain, and total strain.

[0117] Specifically, the request data can include node number, X coordinate, Y coordinate, Z coordinate, radial displacement, tangential displacement, vertical displacement, total displacement, radial strain, tangential strain, vertical strain, total strain, node number corresponding to the data acquisition device of the measuring point, angle g, radius, height, model corresponding angle, and the like, and of course, other request data can also be included, and the embodiments of the present application do not make too many limitations thereon.

[0118] Wherein, the device data can include node number corresponding to the data acquisition device of the measuring point, angle g, radius, height, model corresponding angle, and the like, and the coordinate data refers to X coordinate, Y coordinate, Z coordinate.

[0119] The containment time-varying effect analysis system of the nuclear power plant is connected with the three-dimensional model system, which can include different devices such as computers or servers.

[0120] Further applied to the embodiments of the present application, the method further includes: performing data uniqueness check on the request data to obtain a check result.

[0121] The request data obtained from the three-dimensional model system is checked for uniqueness according to node number, and the obtained result is stored in a text according to rows, thereby effectively improving the data correctness and functional completeness of the nuclear power design software.

[0122] In another preferred embodiment, the containment time-varying effect analysis system of the nuclear power plant can determine whether the request data is updated according to a pre-set JSON string, discard the data obtained this time if there is no update, otherwise obtain the node number, X coordinate, Y coordinate, Z coordinate, radial displacement, tangential displacement, vertical displacement, total displacement, radial strain, tangential strain, vertical strain, total strain of the three-dimensional model system, and the node number corresponding to the data acquisition device, angle g, radius, height, model corresponding angle, obtain updated three-dimensional measuring point data in combination with the change of the Json format and specific identification.

[0123] Step 202, associating the coordinate data with the containment measuring point to generate a measuring point image;

[0124] Specifically, the containment time-varying effect analysis system of the nuclear power plant can associate the coordinate data with the containment measuring point to generate a measuring point image.

[0125] Specifically, the device data is associated according to unit, coordinate data, age data, displacement, force, etc. to form structured data, and the graphics obtained from the three-dimensional model system and the coordinate data are indexed, so that after selecting unit number, age, pressure platform, instrument type, instrument grouping, and instrument number, coordinate positioning data and images can be quickly obtained.

[0126] In step 203, the age-adjusted effective modulus of the structure is calculated.

[0127] Further, the age-adjusted effective modulus of the structure can be calculated according to the above method for obtaining the structural parameters of the containment of the nuclear power plant.

[0128] In step 204, the strain and displacement theoretical values are obtained according to the age-adjusted effective modulus.

[0129] After obtaining the age-adjusted effective modulus, the age-adjusted effective modulus can be used as an input value to adjust the environmental parameters, perform finite element analysis, obtain the strain and displacement theoretical values, and store the strain and displacement theoretical values in the database for easy calling.

[0130] In step 205, the strain and displacement theoretical values are compared with the strain and displacement actual values to obtain a comparison result.

[0131] It should be noted that the strain and displacement actual values can be actual values collected by a sensor or other data collection equipment. The strain and displacement theoretical values are compared with the strain and displacement actual values to obtain a comparison result, and the performance of the containment is accurately evaluated according to the comparison result.

[0132] The time-varying effect analysis system for the containment of the nuclear power plant according to the embodiment encapsulates the calculation results of structures with different service lives, different pressures, and different instruments, can realize convenient and fast query function and comparison analysis function, can timely discover data anomalies and structural damage, and can evaluate the safety of the structure. A technical system for intelligent evaluation of the containment structure of the nuclear power plant based on data correlation is established, batch data processing, iterative comparison, data verification, etc. are performed, data value is fully mined, the problem of scattered calculation data and inconvenient use is solved, the theoretical values of corresponding monitoring instruments can be conveniently and quickly queried and displayed, and the comparison and analysis of the theoretical values and test values are performed, so that structural damage can be timely discovered and the safety of the structure can be evaluated.

[0133] It should be noted that, for the method embodiments, in order to simply describe, they are all described as a series of action combinations, but those skilled in the art should know that the embodiment of the present application is not limited to the action sequence described, because according to the embodiment of the present application, certain steps can be performed in other sequences or simultaneously. Secondly, those skilled in the art should know that the embodiments described in the specification all belong to preferred embodiments, and the actions involved are not necessarily necessary for the embodiment of the present application.

[0134] Referring to Figure 7 , a structural block diagram of an embodiment of a device for obtaining structural parameters of a containment of a nuclear power plant is shown, which can specifically include the following modules:

[0135] The first obtaining module 301 is configured to obtain the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient of the nuclear power plant containment.

[0136] The age-adjusted effective modulus obtaining module 302 is configured to obtain an age-adjusted effective modulus according to the concrete elastic modulus, the concrete aging coefficient, and the concrete creep coefficient according to a preset rule.

[0137] Preferably, the first obtaining module comprises:

[0138] The first obtaining sub-module is configured to obtain the basic concrete creep coefficient and the dry concrete creep coefficient of the nuclear power plant containment.

[0139] The concrete creep coefficient obtaining sub-module is configured to obtain the concrete creep coefficient according to the basic concrete creep coefficient and the dry concrete creep coefficient.

[0140] Preferably, the first obtaining sub-module comprises:

[0141] The first obtaining unit is configured to obtain the ultimate creep coefficient of the basic creep of silica ash concrete or non-silica ash concrete and a first concrete adjustment coefficient.

[0142] In addition, the time parameter obtaining unit is configured to obtain a time parameter for the concrete.

[0143] The second obtaining unit is configured to obtain the basic concrete creep coefficient according to the ultimate creep coefficient of the basic creep, the first concrete adjustment coefficient, and the time parameter.

[0144] Preferably, the first obtaining sub-module comprises:

[0145] The third obtaining unit is configured to obtain the initial creep coefficient of the silica ash concrete or the non-silica ash concrete.

[0146] In addition, the dry shrinkage strain obtaining unit is configured to obtain the dry shrinkage strain of the concrete at different times.

[0147] The fourth obtaining unit is configured to obtain the dry concrete creep coefficient according to the initial creep coefficient and the dry shrinkage strain of the concrete.

[0148] Preferably, the first obtaining unit comprises:

[0149] The first obtaining sub-unit is configured to obtain the average value of the compressive strength of the concrete cylinder at a certain time and the characteristic value of the compressive strength of the concrete cylinder.

[0150] The first concrete adjustment coefficient obtaining sub-unit is configured to calculate a first concrete adjustment coefficient according to the average value of the compressive strength of the concrete cylinder and the characteristic value of the compressive strength of the concrete cylinder.

[0151] Referring to Figure 8 , a structural block diagram of an embodiment of a comparison device for structural parameters of a nuclear power plant containment is shown, and can specifically include the following modules:

[0152] The request data obtaining module 401 is configured to obtain request data from a three-dimensional model system of the nuclear power plant containment, wherein the request data includes coordinate data.

[0153] The measuring point image generating module 402 is configured to associate the coordinate data with the measuring points of the containment to generate a measuring point image.

[0154] The calculating module 403 is configured to calculate an age-adjusted effective modulus of the structure.

[0155] The strain and displacement theoretical value obtaining module 404 is configured to obtain strain and displacement theoretical values according to the age-adjusted effective modulus.

[0156] The comparison module 405 is configured to compare the strain and displacement theoretical values with strain and displacement actual values to obtain a comparison result.

[0157] Preferably, the device further includes:

[0158] The uniqueness checking module is configured to perform data uniqueness checking on the request data to obtain a checking result.

[0159] Preferably, the step of associating the coordinate data with the measuring points of the containment to generate a measuring point image includes:

[0160] The structured data generating sub-module is configured to associate the device data to generate structured data.

[0161] The measuring point image generating sub-module is configured to establish an index relationship between the graphics obtained from the three-dimensional model system and the coordinate data to generate a measuring point image.

[0162] The above-mentioned modules of the device for obtaining and comparing structural parameters of a nuclear power plant containment can be realized by software, hardware, or a combination thereof, in whole or in part. The above-mentioned modules can be embedded in or independent of a processor in a computer device in hardware form, or can be stored in a memory in a computer device in software form, so as to be called and executed by a processor to perform the operations corresponding to the above-mentioned modules.

[0163] The structure parameter acquisition and comparison device for a nuclear power plant containment provided in the above embodiment can be used to execute the structure parameter acquisition and comparison method for a nuclear power plant containment provided in any of the above embodiments, and has the corresponding functions and advantages.

[0164] In one embodiment, a computer device, which can be a terminal, is provided, and an internal structure diagram of the computer device can be as shown in Figure 9 The computer device includes a processor, a memory, a network interface, a display screen and an input device connected through a system bus. The processor of the computer device is configured 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 and a computer program. The internal memory provides an environment for running the operating system and the computer program in the non-volatile storage medium. The network interface of the computer device is configured to communicate with external terminals through a network connection. The computer program is executed by the processor to implement a structure parameter acquisition and comparison method for a nuclear power plant containment. The display screen of the computer device can be a liquid crystal display screen or an electronic ink display screen. The input device of the computer device can be a touch layer overlaid on the display screen, or can be a key, trackball or touchpad arranged on the shell of the computer device, or can be an external keyboard, touchpad or mouse, etc.

[0165] Those skilled in the art can understand that Figure 9 the structure shown in the above embodiment is only a block diagram of part of the structure related to the scheme of the present application, and does not constitute a limitation on the computer device to which the scheme of the present application is applied. The specific computer device can include more or fewer components than those shown in the figure, or combine certain components, or have a different arrangement of components.

[0166] In one embodiment, a computer device is provided, which includes a memory and a processor. The memory stores a computer program, and the processor executes the computer program to implement the steps of the above Figures 1 to 6 embodiment.

[0167] In one embodiment, a computer readable storage medium is provided, which stores a computer program. The computer program is executed by a processor to implement the steps of the above Figures 1 to 6 embodiment.

[0168] Each of the embodiments in the present specification is described in a progressive manner, and each embodiment focuses on the differences from other embodiments. The same and similar parts between the embodiments can be referred to each other.

[0169] Those skilled in the art will appreciate that embodiments of the present application can be readily used as a method, apparatus, or computer program product. Accordingly, embodiments of the present application can take the form of an entirely hardware embodiment, an entirely software embodiment or an embodiment combining software and hardware aspects. Furthermore, embodiments of the present application can take the form of a computer program product on one or more computer-usable storage media (including, but not limited to, disk storage, CD-ROMs, optical storage devices, and the like) embodying computer program instructions.

[0170] Embodiments of the present application are described herein with reference to the drawings, which are as follows: Figure 1 Figure 1 an apparatus for performing each function specified in a flow or multiple flows and / or blocks in the flowchart and / or block diagram.

[0171] These computer program instructions can also be stored in a computer- readable memory that can direct a computer or other programmable data processing apparatus to function in a particular manner, such that the instructions stored in the computer-readable memory produce an article of manufacture including instructions which implement the flow Figure 1 Figure 1 an apparatus for performing each function specified in a flow or multiple flows and / or blocks in the flowchart and / or block diagram.

[0172] These computer program instructions can also be loaded onto a computer or other programmable data processing apparatus to cause a series of operational steps to be performed on the computer or other programmable apparatus to produce a computer-implemented process such that the instructions which execute on the computer or other programmable apparatus provide steps for implementing the flow Figure 1 Figure 1 an apparatus for performing each function specified in a flow or multiple flows and / or blocks in the flowchart and / or block diagram.

[0173] While preferred embodiments of the present application have been described, additional variations and modifications can be made to these embodiments by those skilled in the art once they learn of the basic inventive concepts. Therefore, the appended claims are intended to cover all such variations and modifications as fall within the scope of the present application.

[0174] ​​​Finally, it is noted that, as used herein, the terminology "first" and "second", and / or the like, are only used to distinguish one entity or action from another entity or action, and do not necessarily require or imply any actual such relationship or order between such entities or actions. Moreover, the terms "comprises", "comprising", or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but can include other elements not expressly listed or inherent to such process, method, article, or apparatus. An element proceeded by "comprises... a" does not, without more constraints, exclude the existence of additional identical elements in the process, method, article, or apparatus that comprises the element.

[0175] The method for obtaining a structure parameter of a nuclear power plant containment, the comparison method for a structure parameter of a nuclear power plant containment, the device for obtaining a structure parameter of a nuclear power plant containment, the comparison device for a structure parameter of a nuclear power plant containment, the computer equipment and the storage medium are described in detail above, the principle and implementation mode of the present application are described by applying specific examples in the present application, the above description of the embodiments is only used to help understand the method of the present application and its core idea; meanwhile, for the general technical personnel in the art, according to the idea of the present application, the specific implementation mode and application range will be changed, and the above description should not be understood as the limitation of the present application.

Claims

1. A method of obtaining a structural parameter of a containment of a nuclear power plant, characterized by, The method comprises the following steps: obtaining the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient of the nuclear power plant containment; obtaining the age-adjusted effective modulus according to the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient according to a preset rule; The method comprises the following steps: obtaining the concrete basic creep coefficient and the concrete dry creep coefficient of the nuclear power plant containment; obtaining the concrete creep coefficient according to the basic creep coefficient and the concrete dry creep coefficient; The method comprises the following steps: obtaining the ultimate creep coefficient of the basic creep and the first concrete adjustment coefficient of the silica fume concrete or the non-silica fume concrete; and obtaining the time parameter of the concrete; obtaining the concrete basic creep coefficient according to the ultimate creep coefficient of the basic creep, the first concrete adjustment coefficient and the time parameter; obtaining the initial creep coefficient of the silica fume concrete or the non-silica fume concrete; obtaining the concrete dry shrinkage strain at different times; obtaining the concrete dry creep coefficient according to the initial creep coefficient and the concrete dry shrinkage strain; The method comprises the following steps: obtaining the average value of the concrete cylinder compressive strength at a certain time and the characteristic value of the concrete cylinder compressive strength; calculating the first concrete adjustment coefficient according to the average value of the concrete cylinder compressive strength and the characteristic value of the concrete cylinder compressive strength; The basic creep coefficient is The formula is as follows: Wherein, the difference between t0 moment and t moment is the time passed by the concrete, Ultimate creep coefficient, β bc First concrete adjustment coefficient; ； ； f ck fc is the characteristic value of the compressive strength of the concrete cylinder; f cm (t0) is the average value of the compressive strength of the concrete cylinder at time t0.

2. A method of comparing structural parameters of a containment of a nuclear power plant, characterized in that, The method comprises the following steps: obtaining the request data from the three-dimensional model system of the nuclear power plant containment; wherein the request data comprises coordinate data; associating the coordinate data with the containment measuring points to generate a measuring point image; calculating the age-adjusted effective modulus of the structure according to the structure parameter acquisition method of claim 1; obtaining the strain and displacement theoretical values according to the age-adjusted effective modulus; comparing the strain and displacement theoretical values with the strain and displacement actual values to obtain a comparison result.

3. The method of claim 2, wherein The method further comprises the following steps: performing data uniqueness checking on the request data to obtain a checking result.

4. The method of claim 2, wherein The method of associating the coordinate data with the containment measuring points to generate a measuring point image comprises the following steps: associating the device data to generate structured data; establishing an index relationship between the graphics obtained from the three-dimensional model system and the coordinate data to generate a measuring point image.

5. A device for acquiring structural parameters of a nuclear power plant containment vessel, characterized in that, The method comprises the following steps: a first acquisition module for obtaining the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient of the nuclear power plant containment; an age-adjusted effective modulus obtaining module for obtaining the age-adjusted effective modulus according to the concrete elastic modulus, the concrete aging coefficient and the concrete creep coefficient according to a preset rule; The method comprises the following steps: obtaining the concrete basic creep coefficient and the concrete dry creep coefficient of the nuclear power plant containment; obtaining the concrete creep coefficient according to the basic creep coefficient and the concrete dry creep coefficient; The basic creep coefficient and the dry creep coefficient of the concrete of the containment of the nuclear power plant are obtained, including: The ultimate creep coefficient and the first concrete adjustment coefficient of the basic creep of the silica fume concrete or the non-silica fume concrete are obtained; And a time parameter of the concrete is obtained; The basic creep coefficient of the concrete is obtained according to the ultimate creep coefficient, the first concrete adjustment coefficient and the time parameter of the basic creep; The initial creep coefficient of the silica fume concrete or the non-silica fume concrete is obtained; And the dry shrinkage strain of the concrete at different times is obtained; The dry creep coefficient of the concrete is obtained according to the initial creep coefficient and the dry shrinkage strain of the concrete; The ultimate creep coefficient and the first concrete adjustment coefficient of the basic creep of the silica fume concrete or the non-silica fume concrete are obtained, including: The average value and the characteristic value of the compressive strength of the concrete cylinder at a certain time are obtained; The first concrete adjustment coefficient is calculated according to the average value and the characteristic value of the compressive strength of the concrete cylinder; The basic creep coefficient is The formula is as follows: Wherein, the difference between t0 moment and t moment is the time passed by the concrete, Ultimate creep coefficient, β bc First concrete adjustment coefficient; ； ； f ck fc is the characteristic value of the compressive strength of the concrete cylinder; f cm (t0) is the average value of the compressive strength of the concrete cylinder at time t0.

6. A device for comparing structural parameters of a containment of a nuclear power plant, characterized in that, Including: A request data obtaining module is configured to obtain request data from a three-dimensional model system of a containment of a nuclear power plant, wherein the request data comprises coordinate data; A measuring point image generating module is configured to associate the coordinate data with measuring points of the containment to generate a measuring point image; A calculating module is configured to calculate an age adjustment effective modulus of a structure according to the structure parameter obtaining method of claim 1; A strain and displacement theoretical value obtaining module is configured to obtain strain and displacement theoretical values according to the age adjustment effective modulus; A comparing module is configured to compare the strain and displacement theoretical values with strain and displacement actual values to obtain a comparison result. 7.A computer device, comprising a memory and a processor, wherein the memory stores a computer program, and the computer device is configured to perform the method according to any one of claims 1-6 when the computer program is executed by the processor. The processor executes the computer program to realize the method of any one of claims 1 to 4.

8. A computer-readable storage medium having stored thereon a computer program, characterized in that, The computer program is executed by the processor to realize the method of any one of claims 1 to 4.

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