Monitoring data sampling uniformity correction method of nuclear facility pipeline and corresponding system

Abstract

The invention discloses a nuclear facility pipeline monitoring data sampling uniformity correction method and a corresponding system. The method comprises the steps that modeling software is used for conducting modeling and mesh generation on a target pipeline of the nuclear facility, a space mesh model is imported into fluid mechanics software, and simulation is conducted based on the set model and parameters according to different working conditions; based on the local flow field and nuclide concentration distribution in the target pipeline in the simulation result, determining a numerical simulation result of the uniform mixing point meeting the set speed and concentration standard; under the same working condition, multiple pieces of actual monitoring data of an existing sampling opening in the target pipeline are obtained; performing comparative analysis on the numerical simulation result and a plurality of actual monitoring data, and establishing a sampling uniformity correction model; and acquiring current monitoring data of the existing sampling port, and substituting the current monitoring data into the sampling uniformity correction model for correction to obtain uniformly sampled monitoring data. Therefore, it is ensured that the corrected monitoring data are more real, and real, reliable and accurate monitoring data are provided for subsequent nuclear safety supervision.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear radiation assessment, specifically to the technical fields of data monitoring and uniformity correction of airborne effluents of nuclear facility pipelines, and in particular to a method for uniformity correction of monitoring data sampling of nuclear facility pipelines and a corresponding system. Background Art

[0002] The radioactive airborne effluent data of nuclear facilities are important empirical data for the operation of nuclear facilities. The accuracy of the data is related to nuclear safety as well as in-process and post-process supervision.

[0003] The existing nuclear base environmental monitoring data is generally obtained by sampling the sampling ports set up in the nuclear facility pipelines. However, some nuclear facilities were designed earlier, and the sampling ports were not designed in accordance with the latest ANSI / HPSN13.1-201 and ISO 2889-2010, resulting in the original sampling ports being located in areas with uneven concentration distribution. The monitoring data has a large deviation and is insufficient to reflect the actual environmental emission level, which in turn leads to inaccurate monitoring data, affecting the regulatory safety of nuclear facilities. Summary of the invention

[0004] The present application provides a method for correcting the uniformity of sampling monitoring data of a nuclear facility pipeline and a corresponding system to solve the problem that the existing acquired monitoring data is inaccurate and thus affects the regulatory safety of nuclear facilities.

[0005] The technical solution is as follows:

[0006] In a first aspect, a method for correcting uniformity of sampling of monitoring data of a nuclear facility pipeline is provided, the method comprising:

[0007] Use modeling software to perform proportional 3D modeling of target pipelines of nuclear facilities, and mesh the established 3D model to obtain a spatial mesh model;

[0008] After the spatial grid model is imported into the fluid mechanics software, models and parameters related to numerical solutions are set according to different working conditions, and the movement distribution of radioactive nuclide particles inside the target pipeline is simulated; wherein the models and parameters related to numerical solutions at least include: material properties, boundary conditions, initial conditions and discrete phase models,

[0009] The local flow field and the nuclide concentration distribution in the target pipeline are respectively obtained from a plurality of simulation results obtained according to different working conditions, the mixing uniformity at different sections in the target pipeline is compared and analyzed, a mixing uniform point that meets the set judgment standard is determined, and the nuclide concentration at the mixing uniform point is obtained as a numerical simulation result;

[0010] Under the same working conditions as the numerical simulation results, a large number of nuclide concentrations at existing sampling ports in the target pipeline are obtained as a plurality of actual monitoring data;

[0011] Comparing and analyzing the numerical simulation results with the actual monitoring data, and establishing a sampling uniformity correction model, wherein the numerical simulation results in the sampling uniformity correction model and the actual monitoring data are in a linear fitting relationship or a nonlinear fitting relationship;

[0012] The current monitoring data of the existing sampling ports in the target pipeline are obtained, and the current monitoring data are substituted into the sampling uniformity correction model for correction to obtain sampling uniformity monitoring data.

[0013] In a possible implementation, a target pipeline of a nuclear facility is modeled in 3D in proportion using modeling software, specifically including:

[0014] Using SOLIDWORKS modeling software, a proportional three-dimensional pipeline geometry model is established for the target pipeline of the nuclear facility, where the model parameters include at least the pipeline shape, pipe length, and pipe diameter.

[0015] In a possible implementation, when meshing the established three-dimensional model, meshes in areas close to the pipe wall and at pipe bends are encrypted.

[0016] In a possible implementation, the fluid mechanics software used in the simulation is FLUENT;

[0017] The initial conditions set during the simulation include at least: initial temperature and initial velocity in the pipeline; the boundary conditions include at least: pipeline boundary conditions and wall boundary conditions; wherein the inlet adopts a velocity inlet boundary, the outlet adopts a pressure outlet boundary, and the pipe wall adopts a no-slip boundary.

[0018] In a possible implementation, the local flow field and the nuclide concentration distribution in the target pipeline are respectively obtained from a plurality of simulation results obtained according to different working conditions, the mixing uniformity at different sections in the target pipeline is compared and analyzed, a mixing uniform point that meets the set judgment criteria is determined, and the nuclide concentration at the mixing uniform point is obtained as a numerical simulation result, specifically including:

[0019] Acquire the local flow field and the nuclide concentration distribution in the target pipeline respectively from the plurality of simulation results, and determine the velocity distribution and the concentration distribution of the nuclide in different cross sections in the target pipeline based on the acquired local flow field and the nuclide concentration distribution in the target pipeline;

[0020] Obtaining the velocity distribution and concentration distribution of the nuclides in the cross section where the existing sampling port is located in the target pipeline, and performing comparative analysis on the mixing uniformity of the nuclides in the cross section where the existing sampling port is located;

[0021] If the velocity distribution and concentration distribution of the nuclide in the cross section where the existing sampling port is located do not meet the set judgment criteria, then find a cross section that meets the set criteria from multiple cross sections in the target pipeline as a uniform mixing point; wherein the set criteria at least include: the average cyclone angle of the entire cross section is not greater than a preset angle, the velocity variation coefficient on the center 2 / 3 area of ​​the cross section is not greater than a first threshold, the variation coefficient of the tracer gas concentration on the center 2 / 3 area of ​​the cross section is not greater than a second threshold, the difference between the maximum tracer gas concentration and the average concentration of the entire cross section is not greater than a third threshold, and the variation coefficient of the aerosol concentration on the center 2 / 3 area of ​​the cross section is not greater than a fourth threshold;

[0022] The nuclide concentration at the mixing uniformity point is obtained as the numerical simulation result.

[0023] In a possible implementation, when performing mixing uniformity analysis on the internal flow field of the target pipeline, CFD-POST post-processing software is used to process the simulation results.

[0024] In a possible implementation, the sampling uniformity correction model is y=ax b , where y is the numerical simulation result, x is the actual monitoring data, and a and b are correction factors; or

[0025] The sampling uniformity correction model is y=ax 2 +b, where y is the numerical simulation result, x is the actual monitoring data, and a and b are correction factors.

[0026] In a second aspect, a monitoring data sampling uniformity correction system for a nuclear facility pipeline is provided, comprising:

[0027] A modeling module is used to perform proportional three-dimensional modeling of target pipelines of nuclear facilities using modeling software, and to perform grid division on the established three-dimensional model to obtain a spatial grid model;

[0028] A simulation module is used to set models and parameters related to numerical solution according to different working conditions after the spatial grid model is imported into the fluid mechanics software, and simulate the movement distribution of radioactive nuclide particles inside the target pipeline; wherein the models and parameters related to numerical solution at least include: material properties, boundary conditions, initial conditions and discrete phase model,

[0029] An analysis module, used to obtain the local flow field and nuclide concentration distribution in the target pipeline from multiple simulation results obtained according to different working conditions, compare and analyze the mixing uniformity on different sections in the target pipeline, determine the mixing uniform point that meets the set judgment standard, and obtain the nuclide concentration of the mixing uniform point as a numerical simulation result;

[0030] An acquisition module, used for acquiring a large number of nuclide concentrations of existing sampling ports in the target pipeline as a plurality of actual monitoring data under the same working conditions as the numerical simulation results;

[0031] A fitting module, used for comparing and analyzing the plurality of numerical simulation results with the plurality of actual monitoring data, and establishing a sampling uniformity correction model, wherein a linear fitting relationship or a nonlinear fitting relationship is present between the numerical simulation results and the actual monitoring data in the sampling uniformity correction model;

[0032] The correction module is used to obtain the current monitoring data of the existing sampling port in the target pipeline, and substitute the current monitoring data into the sampling uniformity correction model for correction to obtain sampling uniform monitoring data.

[0033] In a third aspect, a computer-readable storage medium is provided, wherein at least one instruction is stored in the storage medium, and the at least one instruction is loaded and executed by a processor to implement the method of the above-mentioned aspect and any possible implementation manner.

[0034] According to a fourth aspect, a computer program product is provided, comprising a computer program, wherein when the computer program is executed by a processor, the computer program implements the above-mentioned aspects and any possible implementation method.

[0035] The beneficial effects of the technical solution provided by this application include at least:

[0036] It can be seen from the above technical solution that the embodiment of the present application can use computational fluid dynamics CFD simulation technology to model the pipelines that discharge gas-borne effluents in nuclear facilities, simulate the pipeline flow field for numerical calculation, and correct the actual monitoring data currently acquired based on the uniformity correction model obtained by fitting multiple simulated numerical calculation results with a large amount of actual monitoring data. Thereby, it is ensured that the corrected monitoring data is more realistic, providing real, reliable and accurate monitoring data for subsequent nuclear safety supervision.

[0037] It should be understood that the content described in this section is not intended to identify the key or important features of the embodiments of the present application, nor is it intended to limit the scope of the present application. Other features of the present application will become easily understood through the following description. BRIEF DESCRIPTION OF THE DRAWINGS

[0038] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings required for use in the description of the embodiments will be briefly introduced below. Obviously, the drawings described below are only some embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on these drawings without creative work.

[0039] Figure 1 It is a schematic diagram of the steps of a method for correcting uniformity of monitoring data sampling of a nuclear facility pipeline provided in an embodiment of the present application.

[0040] Figure 2 It is a flow chart of a method for correcting uniformity of monitoring data sampling of a nuclear facility pipeline provided in an embodiment of the present application.

[0041] Figure 3 It is a structural block diagram of a monitoring data sampling uniformity correction system for a nuclear facility pipeline provided by an embodiment of the present application.

[0042] Figure 4 It is a block diagram of an electronic device according to an embodiment of the present application. DETAILED DESCRIPTION

[0043] The following is a description of exemplary embodiments of the present application in conjunction with the accompanying drawings, including various details of the embodiments of the present application to facilitate understanding, which should be considered as merely exemplary. Therefore, it should be recognized by those of ordinary skill in the art that various changes and modifications can be made to the embodiments described herein without departing from the scope and spirit of the present application. Similarly, for the sake of clarity and conciseness, the description of well-known functions and structures is omitted in the following description.

[0044] Obviously, the described embodiments are only part of the embodiments of the present application, but not all of the embodiments. Based on the embodiments in the present application, all other embodiments obtained by ordinary technicians in the field without creative work are within the scope of protection of the present application.

[0045] It should be noted that the terminal devices involved in the embodiments of the present application may include but are not limited to mobile phones, personal digital assistants (PDAs), wireless handheld devices, tablet computers and other smart devices; display devices may include but are not limited to personal computers, televisions and other devices with display functions.

[0046] In addition, the term "and / or" in this article is only a description of the association relationship between the associated objects, indicating that there can be three relationships. For example, A and / or B can represent: A exists alone, A and B exist at the same time, and B exists alone. In addition, the character " / " in this article generally indicates that the associated objects before and after are in an "or" relationship.

[0047] Given that the nuclear facility was designed earlier, the sampling port was not designed in accordance with the latest ANSI / HPSN13.1-201 and ISO 2889-2010, resulting in the original sampling port being located at a location with uneven concentration distribution, which in turn resulted in inaccurate monitoring data, affecting the regulatory safety of the nuclear facility. Considering that field test verification in the chimney pipeline flow field is limited by various factors, and that only operating conditions and a limited number of locations can be measured during service, this application uses computational fluid dynamics CFD simulation technology to model the pipelines that discharge airborne effluents in nuclear facilities, simulates the pipeline flow field for numerical calculation, and corrects the actual monitoring data currently obtained based on the uniformity correction model obtained by fitting the numerical calculation results with a large amount of actual monitoring data. This ensures that the corrected monitoring data is more realistic, providing true, reliable and accurate monitoring data for subsequent nuclear safety supervision.

[0048] Reference Figure 1 As shown, it is a schematic diagram of the steps of a method for uniformity correction of monitoring data sampling of nuclear facility pipelines provided in an embodiment of the present application. It should be noted that the execution subject of the method may be a uniformity correction system for monitoring data sampling of nuclear facility pipelines, which may be a hardware device or software module with data processing and storage functions, such as a computer, a tablet computer, a smart phone, a smart wearable device, etc., or a functional module or a combination of multiple functional modules integrated in the above hardware devices, etc.

[0049] like Figure 1 As shown, the method for correcting uniformity of sampling of monitoring data of nuclear facility pipelines may include the following steps:

[0050] Step 102: Use modeling software to perform proportional three-dimensional modeling of the target pipeline of the nuclear facility, and mesh the established three-dimensional model to obtain a spatial mesh model.

[0051] Optionally, a target pipeline of the nuclear facility is modeled in proportional three-dimensional manner using modeling software. Specifically, SOLIDWORKS modeling software can be used to establish a proportional three-dimensional pipeline geometric model of the target pipeline of the nuclear facility, wherein the model parameters include at least pipeline shape, pipe length, and pipe diameter.

[0052] Optionally, when meshing the established three-dimensional model, meshes in areas close to the pipe wall and at pipe bends are encrypted.

[0053] Step 104: After the spatial grid model is imported into the fluid mechanics software, models and parameters related to numerical solutions are set according to different working conditions, and the movement distribution of radioactive nuclide particles inside the target pipeline is simulated; wherein the models and parameters related to numerical solutions include at least: material properties, boundary conditions, initial conditions, and discrete phase models.

[0054] Optionally, the fluid mechanics software used in the simulation is FLUENT; the initial conditions set during the simulation include at least: the initial temperature and initial velocity in the pipeline; the boundary conditions include at least: pipeline boundary conditions and wall boundary conditions; wherein the inlet adopts a velocity inlet boundary, the outlet adopts a pressure outlet boundary, and the pipe wall adopts a no-slip boundary.

[0055] Step 106: respectively obtain the local flow field and nuclide concentration distribution in the target pipeline from a plurality of simulation results obtained according to different working conditions, compare and analyze the mixing uniformity at different sections in the target pipeline, determine the mixing uniform point that meets the set judgment criteria, and obtain the nuclide concentration of the mixing uniform point as the numerical simulation result.

[0056] Optionally, in the scheme of the present application, the local flow field and nuclide concentration distribution in the target pipeline are obtained from multiple simulation results, and based on the obtained local flow field and nuclide concentration distribution in the target pipeline, the velocity distribution and concentration distribution of the nuclide in different sections of the target pipeline are determined; the velocity distribution and concentration distribution of the nuclide in the section where the existing sampling port in the target pipeline is located are obtained, and the mixing uniformity of the nuclide in the section where the existing sampling port is located is compared and analyzed; if the velocity distribution and concentration distribution of the nuclide in the section where the existing sampling port is located do not meet the set judgment criteria, then find a section that meets the set criteria from multiple sections in the target pipeline as a mixing uniform point; wherein the set judgment criteria at least include: the average cyclone angle of the entire section is not greater than a preset angle, the coefficient of variation of the velocity on the center 2 / 3 area of ​​the section is not greater than the first threshold, the coefficient of variation of the tracer gas concentration on the center 2 / 3 area of ​​the section is not greater than the second threshold, the difference between the maximum tracer gas concentration and the average concentration of the entire section is not greater than the third threshold, and the coefficient of variation of the aerosol concentration on the center 2 / 3 area of ​​the section is not greater than the fourth threshold; the nuclide concentration of the mixing uniform point is obtained as a numerical simulation result.

[0057] Optionally, when performing mixing uniformity analysis on the internal flow field of the target pipeline, CFD-POST post-processing software is used to process the simulation results.

[0058] Step 108: Under the same working conditions as the numerical simulation results, a large number of nuclide concentrations of existing sampling ports in the target pipeline are obtained as a plurality of actual monitoring data.

[0059] Step 110: Compare and analyze the multiple numerical simulation results with the multiple actual monitoring data to establish a sampling uniformity correction model, wherein the numerical simulation results in the sampling uniformity correction model and the actual monitoring data present a linear fitting relationship or a nonlinear fitting relationship.

[0060] Step 112: obtaining current monitoring data of existing sampling ports in the target pipeline, and substituting the current monitoring data into the sampling uniformity correction model for correction to obtain sampling uniformity monitoring data.

[0061] Optionally, the sampling uniformity correction model is y=ax b , where y is the numerical simulation result, x is the actual monitoring data, a and b are correction factors; or; the sampling uniformity correction model is y=ax 2 +b, where y is the numerical simulation result, x is the actual monitoring data, and a and b are correction factors.

[0062] Through the above technical solution, computational fluid dynamics (CFD) simulation technology can be used to model the pipelines that discharge gas-borne effluents in nuclear facilities, simulate the pipeline flow field for numerical calculation, and correct the actual monitoring data currently acquired based on the uniformity correction model obtained by fitting multiple numerical calculation results of the simulation with a large amount of actual monitoring data. Thus, the corrected monitoring data is guaranteed to be more realistic, providing true, reliable and accurate monitoring data for subsequent nuclear safety supervision.

[0063] Reference Figure 2 As shown, it is a flow chart of a method for correcting uniformity of monitoring data sampling of a nuclear facility pipeline provided in an embodiment of the present application.

[0064] Step 202: Establish a nuclear facility pipeline geometry model for sampling and monitoring of radioactive airborne effluents.

[0065] Specifically, modeling software such as SOLIDWORKS and Gambit can be used for modeling, including parameters such as pipe shape, pipe length, and pipe diameter.

[0066] Step 204: meshing the geometric model, and encrypting the meshes in the area close to the pipe wall and at the pipe bends to obtain a mesh model.

[0067] Since the velocity gradient in the area close to the pipe wall is large and the flow field changes at the pipe bends are more complex, the grids in these areas need to be encrypted to make the grid layout relatively reasonable, ensuring the accuracy of the calculation results while speeding up the solution.

[0068] Step 206: Import the mesh model into FLUENT software, set material properties, pipeline boundary conditions, wall boundary conditions, initial temperature and initial velocity in the pipeline, etc., and simulate the movement and distribution of radioactive aerosol particles inside the nuclear facility pipeline.

[0069] In this embodiment, in addition to using FLUENT for calculation, other fluid mechanics software such as ANSYS, ANSYS CFX, STAR-CCM+, etc. may also be used.

[0070] In this embodiment, the inlet adopts a velocity inlet boundary, the outlet adopts a pressure outlet boundary, and the pipe wall adopts a no-slip boundary.

[0071] Step 208: For the existing sampling ports, set different working conditions to conduct on-site sampling of radioactive airborne effluents, and carry out relevant radionuclide analysis and determination work to obtain a large amount of aerosol concentration monitoring data and complete actual data monitoring.

[0072] Step 210: Evaluate the mixing uniformity of the flow field inside the numerically simulated pipeline, obtain the velocity distribution and concentration distribution on the cross section where the existing sampling position is located, and analyze the representativeness and rationality of the existing aerosol sampling position.

[0073] Step 212: Determine whether the gas has reached a "fully mixed" state. If the gas has not reached a "fully mixed" state, determine that the sampling results of the existing sampling positions are not uniform.

[0074] Step 214: According to the judgment standard of "mixing uniformity" proposed by ISO2889, the mixing uniformity on different sections of the pipeline is compared and analyzed to find the "mixing uniformity point" that meets the standard requirements.

[0075] In this embodiment, the judgment criteria are: the average cyclone angle of the entire cross section is not greater than 20°, the velocity variation coefficient over the center 2 / 3 area of ​​the cross section is not greater than 20%, the variation coefficient of the tracer gas concentration over the center 2 / 3 area of ​​the cross section is not greater than 20%, the difference between the maximum tracer gas concentration and the average concentration over the entire cross section is not greater than 30%, and the variation coefficient of the aerosol concentration over the center 2 / 3 area of ​​the cross section is not greater than 20%. That is, if these five conditions are met at the same time, it is determined to be a mixing uniform point that meets the standard requirements.

[0076] In this embodiment, when evaluating the mixing uniformity of the internal flow field of the numerically simulated pipeline, post-processing software such as CFD-POST can be used to process the simulation results, and the local flow field and the aerosol concentration distribution diagram on different cross sections can be used for analysis.

[0077] Step 216: Obtain the simulated value of the nuclide concentration of the “mixing uniformity point” under multiple working conditions.

[0078] Step 218: Compare and analyze the simulated value of the nuclide concentration at the "mixing uniform point" with the measured data, and establish a correction model y=axb (y represents the simulated value, x represents the measured value, and a and b are correction coefficients) for the existing sampling port monitoring data.

[0079] In this embodiment, establishing the correction model requires statistical analysis based on a large amount of simulation data and measured data.

[0080] Step 220: sampling is performed at the existing sampling port to obtain the aerosol concentration monitoring data at the location, and the aerosol concentration data at the truly “evenly mixed” location can be obtained by substituting the data into the correction model y=axb.

[0081] Through the above technical solution, computational fluid dynamics (CFD) simulation technology is used to model the pipelines that discharge gas-borne effluents in nuclear facilities, simulate the pipeline flow field for numerical calculation, and correct the actual monitoring data currently acquired based on the uniformity correction model obtained by fitting the numerical calculation results with a large amount of actual monitoring data. In this way, the corrected monitoring data is guaranteed to be more realistic, providing true, reliable and accurate monitoring data for subsequent nuclear safety supervision.

[0082] It should be noted that, for the aforementioned method embodiments, for the sake of simplicity, they are all expressed as a series of action combinations, but those skilled in the art should be aware that the present application is not limited by the described order of actions, because according to the present application, certain steps can be performed in other orders or simultaneously. Secondly, those skilled in the art should also be aware that the embodiments described in the specification are all preferred embodiments, and the actions and modules involved are not necessarily required by the present application.

[0083] In the above embodiments, the description of each embodiment has its own emphasis. For parts that are not described in detail in a certain embodiment, reference can be made to the relevant descriptions of other embodiments.

[0084] Figure 3 FIG. 1 shows a structural block diagram of a monitoring data sampling uniformity correction system for a nuclear facility pipeline provided by an embodiment of the present application. Figure 3As shown. The monitoring data sampling uniformity correction system 300 of the nuclear facility pipeline of this embodiment may include a modeling module 301, a simulation module 302, an analysis module 303, an acquisition module 304, a fitting module 305 and a correction module 306. Among them, the modeling module 301 is used to use the modeling software to perform proportional three-dimensional modeling of the target pipeline of the nuclear facility, and to mesh the established three-dimensional model to obtain a spatial grid model. The simulation module 302 is used to set the model and parameters related to the numerical solution according to different working conditions after importing the spatial grid model into the fluid mechanics software, and simulate the movement distribution of the radioactive nuclide particles inside the target pipeline; wherein the model and parameters related to the numerical solution at least include: material properties, boundary conditions, initial conditions and discrete phase models. The analysis module 303 is used to respectively obtain the local flow field and nuclide concentration distribution in the target pipeline from multiple simulation results obtained according to different working conditions, compare and analyze the mixing uniformity on different sections in the target pipeline, determine the mixing uniform point that meets the set judgment standard, and obtain the nuclide concentration of the mixing uniform point as the numerical simulation result. The acquisition module 304 is used to obtain a large number of nuclide concentrations of the existing sampling ports in the target pipeline as multiple actual monitoring data under the same working conditions as the numerical simulation results. The fitting module 305 is used to compare and analyze the multiple numerical simulation results with the multiple actual monitoring data to establish a sampling uniformity correction model, wherein the numerical simulation results and the actual monitoring data in the sampling uniformity correction model are linearly fitted or nonlinearly fitted. The correction module 306 is used to obtain the current monitoring data of the existing sampling ports in the target pipeline, and substitute the current monitoring data into the sampling uniformity correction model for correction to obtain sampling uniform monitoring data.

[0085] Optionally, in a possible implementation of this embodiment, when the modeling module 301 uses the modeling software to perform proportional three-dimensional modeling of the target pipeline of the nuclear facility, it specifically uses SOLIDWORKS modeling software to establish a proportional three-dimensional pipeline geometric model of the target pipeline of the nuclear facility, wherein the model parameters include at least pipeline shape, pipe length, and pipe diameter.

[0086] Optionally, in a possible implementation of this embodiment, when meshing the established three-dimensional model, meshes in areas close to the pipe wall and at pipe bends are encrypted.

[0087] Optionally, in a possible implementation of this embodiment, the fluid mechanics software used for the simulation is FLUENT; the initial conditions set during the simulation include at least: the initial temperature and initial velocity in the pipeline; the boundary conditions include at least: pipeline boundary conditions and wall boundary conditions; wherein the inlet adopts a velocity inlet boundary, the outlet adopts a pressure outlet boundary, and the pipe wall adopts a no-slip boundary.

[0088] Optionally, in a possible implementation of the present embodiment, the analysis module 303 is specifically used to obtain the local flow field and nuclide concentration distribution in the target pipeline from the simulation results, compare and analyze the mixing uniformity at different sections in the target pipeline, determine the mixing uniformity point that meets the set velocity and concentration standards, and obtain the nuclide concentration of the mixing uniformity point as the numerical simulation result, and is specifically used to obtain the local flow field and nuclide concentration distribution in the target pipeline from the simulation results, and determine the velocity distribution and concentration distribution of the nuclides in different sections in the target pipeline based on the obtained local flow field and nuclide concentration distribution in the target pipeline; obtain the velocity distribution and concentration distribution of the nuclides in the section where the existing sampling port in the target pipeline is located, and perform a numerical simulation on the nuclide concentration at the existing sampling port. A comparative analysis is performed on the mixing uniformity of the nuclides in the cross section; if the velocity distribution and concentration distribution of the nuclides in the cross section where the existing sampling port is located do not meet the set judgment criteria, a cross section that meets the set criteria is found from multiple cross sections in the target pipeline as a mixing uniformity point; wherein the set criteria at least include: the average cyclone angle of the entire cross section is not greater than a preset angle, the velocity variation coefficient over the center 2 / 3 area of ​​the cross section is not greater than a first threshold value, the variation coefficient of the tracer gas concentration over the center 2 / 3 area of ​​the cross section is not greater than a second threshold value, the difference between the maximum tracer gas concentration and the average concentration of the entire cross section is not greater than a third threshold value, and the variation coefficient of the aerosol concentration over the center 2 / 3 area of ​​the cross section is not greater than a fourth threshold value; the nuclide concentrations at the mixing uniformity point are obtained as numerical simulation results.

[0089] Optionally, in a possible implementation of this embodiment, when performing mixing uniformity analysis on the internal flow field of the target pipeline, CFD-POST post-processing software is used to process the simulation results.

[0090] Optionally, in a possible implementation of this embodiment, the sampling uniformity correction model is y=ax b , where y is the numerical simulation result, x is the actual monitoring data, and a and b are correction factors; or;

[0091] The sampling uniformity correction model is y=ax 2 +b, where y is the numerical simulation result, x is the actual monitoring data, and a and b are correction factors.

[0092] In this embodiment, the pipelines for discharging gaseous effluents in nuclear facilities can be modeled by computational fluid dynamics (CFD) simulation technology, the pipeline flow field can be simulated for numerical calculation, and the actual monitoring data currently acquired can be corrected based on the uniformity correction model obtained by fitting the numerical calculation results with a large amount of actual monitoring data. Thus, the corrected monitoring data is guaranteed to be more authentic, providing authentic, reliable and accurate monitoring data for subsequent nuclear safety supervision.

[0093] An embodiment of the present application provides a computer-readable storage medium, wherein the storage medium stores at least one instruction, and the at least one instruction is loaded and executed by a processor to implement the above-mentioned method for correcting uniformity of monitoring data sampling of a nuclear facility pipeline.

[0094] An embodiment of the present application provides a computer program product, including a computer program, which, when executed by a processor, implements the above-mentioned method for correcting uniformity of sampling monitoring data of a nuclear facility pipeline.

[0095] An embodiment of the present application provides an electronic device, which includes a processor and a memory, wherein the memory stores at least one instruction, and the instruction is loaded and executed by the processor to implement the monitoring data sampling uniformity correction method for the nuclear facility pipeline as described above.

[0096] In the technical solution of this application, the collection, storage, use, processing, transmission, provision and disclosure of user personal information involved are in compliance with the relevant laws and regulations and do not violate public order and good morals.

[0097] Figure 4 A schematic block diagram of an example electronic device 400 that can be used to implement an embodiment of the present application is shown. The electronic device is intended to represent various forms of digital computers, such as laptop computers, desktop computers, workbenches, personal digital assistants, servers, blade servers, mainframe computers, and other suitable computers. The electronic device can also represent various forms of mobile devices, such as personal digital processing, cellular phones, smart phones, wearable devices, and other similar computing devices. The components shown herein, their connections and relationships, and their functions are merely examples and are not intended to limit the implementation of the present application described and / or required herein.

[0098] like Figure 4As shown, the electronic device 400 includes a computing unit 401, which can perform various appropriate actions and processes according to a computer program stored in a read-only memory (ROM) 402 or a computer program loaded from a storage unit 408 into a random access memory (RAM) 403. In the RAM 403, various programs and data required for the operation of the electronic device 400 can also be stored. The computing unit 401, the ROM 402, and the RAM 403 are connected to each other via a bus 404. An input / output (I / O) interface 405 is also connected to the bus 404.

[0099] Multiple components in the electronic device 400 are connected to the I / O interface 405, including: an input unit 406, such as a keyboard, a mouse, etc.; an output unit 407, such as various types of displays, speakers, etc.; a storage unit 408, such as a disk, an optical disk, etc.; and a communication unit 409, such as a network card, a modem, a wireless communication transceiver, etc. The communication unit 409 allows the electronic device 400 to exchange information / data with other devices through a computer network such as the Internet and / or various telecommunication networks.

[0100] The computing unit 401 may be a variety of general and / or special processing components with processing and computing capabilities. Some examples of the computing unit 401 include, but are not limited to, a central processing unit (CPU), a graphics processing unit (GPU), various dedicated artificial intelligence (AI) computing chips, various computing units running machine learning model algorithms, digital signal processors (DSPs), and any appropriate processors, controllers, microcontrollers, etc. The computing unit 401 performs the various methods and processes described above, such as the method of blind spot detection. For example, in some embodiments, the method of blind spot detection may be implemented as a computer software program, which is tangibly contained in a machine-readable medium, such as a storage unit 408. In some embodiments, part or all of the computer program may be loaded and / or installed on the electronic device 400 via the ROM 402 and / or the communication unit 409. When the computer program is loaded into the RAM 403 and executed by the computing unit 401, one or more steps of the method of blind spot detection described above may be performed. Alternatively, in other embodiments, the computing unit 401 may be configured to perform the method of blind spot detection in any other appropriate manner (e.g., by means of firmware).

[0101] Various implementations of the systems and techniques described above herein can be implemented in digital electronic circuit systems, integrated circuit systems, field programmable gate arrays (FPGAs), application specific integrated circuits (ASICs), application specific standard products (ASSPs), systems on chips (SOCs), complex programmable logic devices (CPLDs), computer hardware, firmware, software, and / or combinations thereof. These various implementations can include: being implemented in one or more computer programs that can be executed and / or interpreted on a programmable system including at least one programmable processor, which can be a special purpose or general purpose programmable processor that can receive data and instructions from a storage system, at least one input device, and at least one output device, and transmit data and instructions to the storage system, the at least one input device, and the at least one output device.

[0102] The program code for implementing the method of the present application can be written in any combination of one or more programming languages. These program codes can be provided to a processor or controller of a general-purpose computer, a special-purpose computer, or other programmable data processing device, so that the program code, when executed by the processor or controller, implements the functions / operations specified in the flow chart and / or block diagram. The program code can be executed entirely on the machine, partially on the machine, partially on the machine and partially on a remote machine as a stand-alone software package, or entirely on a remote machine or server.

[0103] In the context of the present application, a machine-readable medium may be a tangible medium that may contain or store a program for use by or in conjunction with an instruction execution system, device, or equipment. A machine-readable medium may be a machine-readable signal medium or a machine-readable storage medium. A machine-readable medium may include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, device, or equipment, or any suitable combination of the foregoing. A more specific example of a machine-readable storage medium may include an electrical connection based on one or more lines, a portable computer disk, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or flash memory), an optical fiber, a portable compact disk read-only memory (CD-ROM), an optical storage device, a magnetic storage device, or any suitable combination of the foregoing.

[0104] To provide interaction with a user, the systems and techniques described herein can be implemented on a computer having: a display device (e.g., a CRT (cathode ray tube) or LCD (liquid crystal display) monitor) for displaying information to the user; and a keyboard and pointing device (e.g., a mouse or trackball) through which the user can provide input to the computer. Other types of devices can also be used to provide interaction with the user; for example, the feedback provided to the user can be any form of sensory feedback (e.g., visual feedback, auditory feedback, or tactile feedback); and input from the user can be received in any form (including acoustic input, voice input, or tactile input).

[0105] The systems and techniques described herein may be implemented in a computing system that includes back-end components (e.g., as a data server), or a computing system that includes middleware components (e.g., an application server), or a computing system that includes front-end components (e.g., a user computer with a graphical user interface or a web browser through which a user can interact with implementations of the systems and techniques described herein), or a computing system that includes any combination of such back-end components, middleware components, or front-end components. The components of the system may be interconnected by any form or medium of digital data communication (e.g., a communication network). Examples of communication networks include: a local area network (LAN), a wide area network (WAN), and the Internet.

[0106] A computer system may include a client and a server. The client and the server are generally remote from each other and usually interact through a communication network. The relationship of client and server is generated by computer programs running on respective computers and having a client-server relationship with each other. The server may be a cloud server, a server of a distributed system, or a server combined with a blockchain.

[0107] It should be understood that the various forms of processes shown above can be used to reorder, add or delete steps. For example, the steps disclosed in this application can be performed in parallel, sequentially or in different orders, as long as the desired results of the technical solution disclosed in this application can be achieved, and this document does not limit this.

[0108] The above specific implementations do not constitute a limitation on the protection scope of this application. It should be understood by those skilled in the art that various modifications, combinations, sub-combinations and substitutions can be made according to design requirements and other factors. Any modifications, equivalent substitutions and improvements made within the spirit and principles of this application should be included in the protection scope of this application.

Claims

1. A method for correcting uniformity of sampling monitoring data of a nuclear facility pipeline, characterized in that: The method comprises: Use modeling software to perform proportional 3D modeling of target pipelines of nuclear facilities, and mesh the established 3D model to obtain a spatial mesh model; After the spatial grid model is imported into the fluid mechanics software, models and parameters related to numerical solution are set according to different working conditions, and the motion distribution of radioactive nuclide particles inside the target pipeline is simulated; wherein the models and parameters related to numerical solution at least include: material properties, boundary conditions, initial conditions and discrete phase model; The local flow field and the nuclide concentration distribution in the target pipeline are respectively obtained from a plurality of simulation results obtained according to different working conditions, the mixing uniformity at different sections in the target pipeline is compared and analyzed, a mixing uniform point that meets the set judgment standard is determined, and the nuclide concentration at the mixing uniform point is obtained as a numerical simulation result; Under the same working conditions as the numerical simulation results, a large number of nuclide concentrations at existing sampling ports in the target pipeline are obtained as a plurality of actual monitoring data; Comparing and analyzing the multiple numerical simulation results with the multiple actual monitoring data, and establishing a sampling uniformity correction model, wherein the numerical simulation results in the sampling uniformity correction model and the actual monitoring data present a linear fitting relationship or a nonlinear fitting relationship; The current monitoring data of the existing sampling ports in the target pipeline are obtained, and the current monitoring data are substituted into the sampling uniformity correction model for correction to obtain sampling uniformity monitoring data.

2. The method according to claim 1, characterized in that Use modeling software to carry out proportional 3D modeling of target pipelines of nuclear facilities, including: Using SOLIDWORKS modeling software, a proportional three-dimensional pipeline geometry model is established for the target pipeline of the nuclear facility, where the model parameters include at least the pipeline shape, pipe length, and pipe diameter.

3. The method according to claim 1, characterized in that When meshing the established three-dimensional model, the meshes in the area close to the pipe wall and at the pipe bends are encrypted.

4. The method according to claim 1, characterized in that The fluid mechanics software used in the simulation is FLUENT; The initial conditions set during the simulation include at least: initial temperature and initial velocity in the pipeline; the boundary conditions include at least: pipeline boundary conditions and wall boundary conditions; wherein the inlet adopts a velocity inlet boundary, the outlet adopts a pressure outlet boundary, and the pipe wall adopts a no-slip boundary.

5. The method according to claim 1, characterized in that The local flow field and the nuclide concentration distribution in the target pipeline are respectively obtained from a plurality of simulation results obtained according to different working conditions, the mixing uniformity at different sections in the target pipeline is compared and analyzed, a mixing uniform point that meets the set standard is determined, and the nuclide concentration at the mixing uniform point is obtained as a numerical simulation result, specifically including: Acquire the local flow field and the nuclide concentration distribution in the target pipeline respectively from the plurality of simulation results, and determine the velocity distribution and the concentration distribution of the nuclide in different cross sections in the target pipeline based on the acquired local flow field and the nuclide concentration distribution in the target pipeline; Obtaining the velocity distribution and concentration distribution of the nuclides in the cross section where the existing sampling port is located in the target pipeline, and performing comparative analysis on the mixing uniformity of the nuclides in the cross section where the existing sampling port is located; If the velocity distribution and concentration distribution of the nuclide in the cross section where the existing sampling port is located do not meet the set judgment criteria, then find a cross section that meets the set criteria from multiple cross sections in the target pipeline as a uniform mixing point; wherein the set judgment criteria at least include: the average cyclone angle of the entire cross section is not greater than a preset angle, the velocity variation coefficient on the center 2 / 3 area of ​​the cross section is not greater than a first threshold, the variation coefficient of the tracer gas concentration on the center 2 / 3 area of ​​the cross section is not greater than a second threshold, the difference between the maximum tracer gas concentration and the average concentration of the entire cross section is not greater than a third threshold, and the variation coefficient of the aerosol concentration on the center 2 / 3 area of ​​the cross section is not greater than a fourth threshold; The nuclide concentration at the mixing uniformity point is obtained as the numerical simulation result.

6. The method according to claim 5, characterized in that When analyzing the mixing uniformity of the flow field inside the target pipeline, CFD-POST post-processing software is used to process the simulation results.

7. The method according to any one of claims 1 to 6, characterized in that: The sampling uniformity correction model is y=ax b , where y is the numerical simulation result, x is the actual monitoring data, and a and b are correction factors; or; The sampling uniformity correction model is y=ax 2 +b, where y is the numerical simulation result, x is the actual monitoring data, and a and b are correction factors.

8. A monitoring data sampling uniformity correction system for nuclear facility pipelines, characterized in that: include: A modeling module is used to perform proportional three-dimensional modeling of target pipelines of nuclear facilities using modeling software, and to perform grid division on the established three-dimensional model to obtain a spatial grid model; A simulation module, which is used to set models and parameters related to numerical solution according to different working conditions after importing the spatial grid model into fluid mechanics software, and simulate the movement distribution of radioactive nuclide particles inside the target pipeline; wherein the models and parameters related to numerical solution at least include: material properties, boundary conditions, initial conditions and discrete phase model; An analysis module, used to obtain the local flow field and nuclide concentration distribution in the target pipeline from multiple simulation results obtained according to different working conditions, compare and analyze the mixing uniformity on different sections in the target pipeline, determine the mixing uniform point that meets the set judgment standard, and obtain the nuclide concentration of the mixing uniform point as a numerical simulation result; An acquisition module, used for acquiring a large number of nuclide concentrations of existing sampling ports in the target pipeline as a plurality of actual monitoring data under the same working conditions as the numerical simulation results; A fitting module, used for comparing and analyzing the plurality of numerical simulation results with the plurality of actual monitoring data, and establishing a sampling uniformity correction model, wherein a linear fitting relationship or a nonlinear fitting relationship is present between the numerical simulation results and the actual monitoring data in the sampling uniformity correction model; The correction module is used to obtain the current monitoring data of the existing sampling port in the target pipeline, and substitute the current monitoring data into the sampling uniformity correction model for correction to obtain sampling uniform monitoring data.

9. A non-transitory computer-readable storage medium storing computer instructions, wherein: The computer instructions are used to cause the computer to execute the method according to any one of claims 1-7.

10. A computer program product, comprising a computer program, which, when executed by a processor, implements the method according to any one of claims 1 to 7.

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