Detector arrangement method and device, storage medium and electronic equipment
By acquiring reactor core loading data, determining detector channels and response consistency assessment, the problem of detection inaccuracy caused by the complexity of reactor core loading was solved, and high-accuracy detection of flexible and variable reactor cores was achieved.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2025-10-21
- Publication Date
- 2026-03-13
AI Technical Summary
Because reactor core loading is complex, flexible, and asymmetrical, it is difficult to guarantee the accuracy of core detection by using a fixed-position detection method.
By acquiring reactor core loading data, the core and detector channels are determined. Detectors at different locations in the detector channels are used for detection to obtain detection response data. Based on the response consistency evaluation results, the target locations are determined to deploy detectors to improve detection accuracy.
It enables the adjustment of the target detector position based on different reactor core loading data, and is applicable to various flexible and asymmetric core loading schemes, thereby improving the accuracy of core detection.
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Figure CN121662460A_ABST
Abstract
Description
Technical Field
[0001] This disclosure relates to the field of nuclear power technology, specifically to a detector arrangement method, apparatus, storage medium, and electronic equipment. Background Technology
[0002] During the startup of a nuclear reactor, in order to ensure that the startup process is safe and controllable, multiple physical startup detectors are usually deployed to monitor the neutron flux level in the reactor core in real time, thereby obtaining information on the increase in reactor core power.
[0003] In related technologies, detectors are usually placed in fixed positions. However, due to the complex and flexible nature of reactor core loading, which is asymmetrical, it is difficult to guarantee the accuracy of core detection by using fixed positions. Summary of the Invention
[0004] In view of this, the present disclosure provides a detector arrangement method, device, storage medium and electronic equipment, the main purpose of which is to solve the technical problem that the current related technologies are difficult to guarantee the accuracy of core detection due to the complex and flexible nature of reactor core loading and its asymmetric characteristics, and the detection method based on fixed positions.
[0005] According to a first aspect of this disclosure, a detector arrangement method is provided, the method comprising: Obtain reactor core loading data; Determine the core and detector channels corresponding to the core loading data; The reactor core is detected by detectors at different positions in the detector channel, and the detection response data corresponding to different detectors are obtained. Based on the detection response data of different detectors, the response consistency of different detectors is evaluated, and the response evaluation results of different detectors are obtained. Based on the response evaluation results of different detectors, the target position is determined from different positions of the detector channel. The target position is used to deploy the target detector to detect the core state of the reactor core.
[0006] According to a second aspect of this disclosure, a detector arrangement apparatus is provided, the apparatus comprising: The acquisition module is used to acquire reactor core loading data; The determination module is used to determine the core and detector channels corresponding to the core loading data; The detection module is used to detect the reactor core using detectors at different positions in the detector channel and obtain the detection response data corresponding to different detectors. The evaluation module is used to evaluate the response consistency of different detectors based on the detection response data corresponding to different detectors, and obtain the response evaluation results of different detectors. Based on the response evaluation results of different detectors, the target position is determined from different positions of the detector channel. The target position is used to deploy the target detector to detect the core state of the reactor core.
[0007] According to a third aspect of this disclosure, an electronic device is provided, comprising: at least one processor; and a memory communicatively connected to the at least one processor; wherein the memory stores instructions executable by the at least one processor, the instructions being executed by the at least one processor to enable the at least one processor to perform the method of the first aspect described above.
[0008] According to a fourth aspect of this disclosure, a non-transitory computer-readable storage medium is provided storing computer instructions, wherein the computer instructions are used to cause a computer to perform the method of the first aspect described above.
[0009] Compared with related technologies, the detector arrangement method, apparatus, storage medium, and electronic equipment provided in this disclosure first acquire the reactor core loading data; then determine the core and detector channels corresponding to the core loading data; then use detectors at different positions in the detector channels to detect the core, obtaining detection response data corresponding to different detectors; and based on the detection response data corresponding to different detectors, perform a response consistency assessment on different detectors to obtain response assessment results for different detectors; finally, based on the response assessment results of different detectors, determine the target position from different positions in the detector channels, and the target position is used to arrange the target detector to detect the core state of the reactor core. The scheme disclosed herein can determine the corresponding reactor core and available detector channels based on different reactor core loading data. Then, by using the detectors at different positions in different detector channels to detect the core's response data, a response consistency assessment is performed. Based on the response assessment results of detectors at different positions, multiple target locations with high response consistency are determined. Based on these target locations, multiple corresponding target detectors are arranged in the reactor core. In this way, the target detectors corresponding to different reactor cores are determined based on the response consistency of different detectors. This method is applicable to various flexible and asymmetric reactor core loading schemes, and enables the adjustment of the target positions of the target detectors according to different reactor core loading data, thereby improving the accuracy of reactor core detection. Attached Figure Description
[0010] The accompanying drawings, which are incorporated in and form a part of this specification, illustrate embodiments consistent with this disclosure and, together with the description, serve to explain the principles of this disclosure.
[0011] To more clearly illustrate the technical solutions in the embodiments or related technologies of this disclosure, the accompanying drawings used in the description of the embodiments or related technologies will be briefly introduced below. Obviously, those skilled in the art can obtain other drawings based on these drawings without creative effort.
[0012] Figure 1 This is a schematic flowchart illustrating a detector arrangement method provided in an embodiment of the present disclosure. Figure 2 This is a schematic flowchart illustrating another detector arrangement method provided in an embodiment of this disclosure; Figure 3 This illustration shows a schematic diagram of an ionization chamber channel arrangement provided in an embodiment of this application; Figure 4(a) shows a schematic diagram of an outer ionization chamber channel provided in an embodiment of this application; Figure 4(b) shows a schematic diagram of an inner ionization chamber channel provided in an embodiment of this application; Figure 5 This is a schematic diagram of a detector arrangement device provided in an embodiment of the present disclosure. Detailed Implementation
[0013] The exemplary embodiments of this disclosure are described below with reference to the accompanying drawings, including various details of the embodiments to aid understanding. These should be considered merely exemplary. Therefore, those skilled in the art will recognize that various changes and modifications can be made to the embodiments described herein without departing from the scope and spirit of this disclosure. Similarly, for clarity and brevity, descriptions of well-known functions and structures are omitted in the following description. It should be noted that, unless otherwise specified, the embodiments of this disclosure and the features described therein can be combined with each other.
[0014] The detector arrangement method, apparatus, storage medium, and electronic device of this disclosure are described below with reference to the accompanying drawings.
[0015] During nuclear reactor startup, to ensure a safe and controllable startup process, multiple ionization chambers for physical startup are typically deployed to monitor the core neutron flux level in real time, thereby obtaining information on the core power increase. Research reactor core loading is complex, flexible, and asymmetrical, resulting in significant differences in parameter variations among ionization chambers located in different positions during the same startup process, making it difficult to accurately determine the true situation of the research reactor startup. Furthermore, the design of research reactors and their ionization chambers still faces challenges such as insufficient digitization, inadequate rapid modeling methods for complex irradiation devices, and low computational efficiency, all of which need to be addressed.
[0016] This disclosure provides a detector arrangement method, device, storage medium, and electronic equipment. The main purpose is to solve the technical problem in the current related technologies that the accuracy of core detection is difficult to guarantee due to the complex and flexible nature of reactor core loading and its asymmetric characteristics, and the fixed-position detection method.
[0017] like Figure 1 As shown, embodiments of this disclosure provide a detector arrangement method, including: Step 101: Obtain reactor core loading data.
[0018] In some embodiments, reactor core loading data can be obtained based on information such as core loading schemes, refueling design reports, core loading diagrams, reactor operation databases, and other information. Reactors may include, but are not limited to, research reactors, power reactors, production reactors, propulsion reactors, small modular reactors, and fast breeder reactors. Based on neutron energy spectra, they can be classified as thermal reactors and fast reactors; based on coolants, they can be classified as water-cooled, gas-cooled, and liquid metal-cooled. Correspondingly, core loading data may include, but is not limited to, geometric data (such as fuel assembly positions and control rod assembly positions), material property data (such as fuel enrichment and fuel burnup), and operational status data (such as operating cycle, target power level, and control rod status). This data can be used for neutron transport calculations, power distribution prediction, criticality safety assessments, and detector placement optimization.
[0019] Step 102: Determine the core and detector channels corresponding to the core loading data.
[0020] In some embodiments, the physical spatial structure of the reactor can be determined based on the core loading data, and a corresponding reactor model can be constructed. The reactor model may include, but is not limited to, a core model, a channel model, a detector model, etc., to clarify the geometric positions and functional relationships of components such as fuel, control rods, and detectors. The channel model may include multiple detector channels pre-set on the periphery of the core model for installing detectors (such as ionization chambers and fission chambers), which can be pre-set according to the detector channel design drawing.
[0021] Step 103: Use detectors at different positions in the detector channel to detect the reactor core and obtain the detection response data corresponding to different detectors.
[0022] In some embodiments, multiple detection points can be arranged axially within each detector channel. By using different positions (such as height) in different detector channels, the detection response process of the detector to the reactor core at multiple positions can be simulated to obtain detection response data of the detector at different positions. For example, the detection response data may include, but is not limited to, neutron flux rate, reaction rate information, etc., which can be used to evaluate the response consistency of the detector at different positions, such as axial response consistency, radial response consistency, etc.
[0023] Step 104: Based on the detection response data corresponding to different detectors, conduct a response consistency assessment of different detectors and obtain the response assessment results of different detectors.
[0024] In some embodiments, response evaluation rules can be formulated using preset response evaluation indicators (such as root mean square error, correlation coefficient, coefficient of variation, etc.) to process and evaluate the detection response data corresponding to multiple different detectors, thereby obtaining the evaluation results of multiple detectors. The target detector corresponding to different reactor cores can be determined based on the consistency of the responses of different detectors. This is applicable to various flexible and asymmetric reactor core loading schemes, and enables the adjustment of the target position of the target detector according to the different reactor core loading data, thereby improving the accuracy of reactor core detection.
[0025] Step 105: Based on the response evaluation results of different detectors, determine the target position from different positions in the detector channel.
[0026] The target location can be used to deploy target detectors to detect the core state of the reactor core. The target detectors may include a preset number of detectors, which are respectively deployed at the corresponding target locations to monitor the reactor core reaction more comprehensively.
[0027] In some embodiments, multiple detector combinations are obtained by permutation and combination. Based on the response evaluation results of the detection response data of multiple detector combinations, the detector combination with the best response consistency is selected as the target detector. The corresponding channel and the specific position in the channel are determined as the target position. The impact of different channel positions on criticality prediction is evaluated, and real-time mapping between the core state and the monitoring system is realized, thereby improving the accuracy of the target detector in detecting the core.
[0028] Compared with related technologies, this embodiment can determine the corresponding core and available detector channels of a reactor based on different core loading data. Then, it uses the detection response data of the detectors at different positions in different detector channels to perform response consistency evaluation. Based on the response evaluation results of detectors at different positions, it determines multiple target positions with high response consistency. Based on these target positions, it arranges multiple corresponding target detectors in the core. In this way, the target detectors corresponding to different cores are determined based on the response consistency of different detectors. This is applicable to various flexible and asymmetric core loading schemes, and enables the adjustment of the target positions of the target detectors according to different core loading data of the reactor, thereby improving the accuracy of core detection.
[0029] Based on the technical implementation described in the above embodiments, in order to further illustrate the specific implementation process of the method in this embodiment, this embodiment provides the following: Figure 2The specific method shown includes: Step 201: Obtain reactor core loading data.
[0030] For example, taking a research reactor as an example, the active region loading scheme can be determined according to the specific tasks and requirements of the research reactor, and the core loading data corresponding to the research reactor can be obtained, which may include, but is not limited to, information such as critical rod positions, fuel burnup distribution, and irradiation devices.
[0031] Step 202: Determine the core and detector channels corresponding to the core loading data.
[0032] In some embodiments, step 202 may specifically include: constructing a core model corresponding to the reactor using core loading data; constructing a pore model corresponding to the reactor based on preset pore data corresponding to the reactor; and determining the core and detector pores corresponding to the core loading data based on the core model after adding the pore model.
[0033] Specifically, a digital interface for physical parameters and information can be constructed based on the ionization chamber pore parameters and core loading schemes of different research reactors, forming a digital matrix readable by the computational model building program. For a given research reactor, the ionization chamber pore information and ionization chamber parameters are fixed, while the core loading scheme and ionization chamber layout vary depending on the operating reactor section. The digital interface allows for independent input of these two parts, facilitating model updates between different operating reactor sections / loading schemes within the same research reactor. Parametric modeling of research reactor information facilitates model modification, improves modeling accuracy and efficiency, and supports model updates for the layout of ionization chambers for multiple physics start-ups.
[0034] For example, the core model may include, but is not limited to, the active region model of the research reactor core, and the pore model may include, but is not limited to, the ionization chamber pore model. Specifically, based on the core loading data corresponding to a specific core loading scheme and the preset pore data of the research reactor, a research reactor core and its outer ionization chamber pore model can be established. The radial height of the model is the height of the active region of the research reactor, and the axial region includes the outer ionization chamber pores and all its internal structures. The preset pore data may include, but is not limited to, pore number, spatial coordinates, direction, length, and diameter. This method enables rapid and accurate establishment of the computational model and rapid iterative updates of the model after parameter updates, significantly improving the design efficiency of the research reactor scheme.
[0035] Step 203: Determine the detection response data corresponding to different detectors based on the regional location of the detector channels corresponding to different detectors.
[0036] The location of the detector channels can include the relative positions of different channels around the active zone of the reactor core, such as the inner layer and the outer layer.
[0037] Optionally, step 203 may specifically include: if the detector channel is an inner detector channel, then the detection response data corresponding to different detectors is directly obtained according to the position of different detectors in the inner detector channel; if the detector channel is an outer detector channel, then the detection response data corresponding to different detectors is obtained based on the calculation accuracy requirements of the detection response data corresponding to the outer detector channel.
[0038] For example, for an ionization chamber located in an inner detector channel (such as an inner ionization chamber channel), neutron flux and reaction rate information can be obtained through a single direct solution. For an ionization chamber located in an outer detector channel (such as an outer ionization chamber channel), due to its distance from the core active region and the thickness of the intermediate water layer, direct transport calculation cannot obtain accurate neutron flux count results. Instead, the particle weighting and variance method can be used to obtain accurate information on neutron flux and reaction rate.
[0039] Optionally, based on the computational accuracy requirements of the detector counting region corresponding to the outer detector channel, the detection response data corresponding to different detectors can be obtained. Specifically, this may include: reconstructing the geometry of the outer ionization chamber channel, determining the deletion element corresponding to the outer ionization chamber channel based on the annular region between the active region corresponding to the core and the outer ionization chamber channel, and obtaining the importance assignment corresponding to the deletion element; and determining the detection response data according to the importance assignment of the deletion element and the computational accuracy requirements of the detection response data.
[0040] In some embodiments, the accurate neutron fluence rate count within the outer ionization chamber channel can be obtained through iterative calculation using the cell weighting method. First, the geometry of the target ionization chamber channel calculation model is reconstructed according to requirements. Then, based on the required calculation accuracy, the calculation results meeting the index requirements can be obtained through iteration of the importance array, ensuring the accuracy of the ionization chamber placement assessment. Compared to direct calculation, the iterative variance reduction method can significantly improve computational efficiency, enabling rapid calculation of neutron information within the outer ionization chamber channel.
[0041] Specifically, the computational model is reconstructed for the ionization chamber channels that need to be counted. The annular region between the active region and the target ionization chamber channel is trimmed twice. The cells within a certain angle range from the center of the active region to the center of the ionization chamber channel are trimmed out separately, and the geometric importance of the trimmed region is assigned. The importance of the cell represents the number of times the calculated particle splits after entering the cell. After splitting, the weight of each particle will decrease to ensure that the total particle weight in the cell remains unchanged.
[0042] Optionally, the detection response data is determined based on the importance assignment of the deleted element and the required accuracy of the detection response data. Specifically, this may include: calculating the detection response data corresponding to the outer ionization chamber channel based on the importance assignment of the deleted element; determining whether the detection response data corresponding to the outer ionization chamber channel meets the required accuracy; if the detection response data corresponding to the outer ionization chamber channel does not meet the required accuracy, then iterating the importance assignment of the deleted element is repeated until the detection response data calculated based on the iterated importance assignment meets the required accuracy.
[0043] In some embodiments, importance assignment requires multiple iterations to determine the final importance value of each gate element, with the initial value determined based on the weights ( imp The calculation formula is determined, and the weights are... imp The formula for calculating ) is: ; In the formula, pop [-1] represents the number of particles used for calculation in the last cell furthest from the active core region in the individually trimmed region. pop [ i [] indicates the number of particles in the individual clipped region that require importance assignment. After each cell in the individual clipped region completes its importance assignment, the transport calculation is repeated. If the statistical standard deviation of the ionization chamber counting region is less than or equal to the target value, the calculation result is saved and the calculation ends. If the statistical standard deviation is greater than the target value, a second round of importance assignment iteration is performed. The formula for the second round of importance assignment is: ; In the formula, imp [ i [This is the new weight array.] pr_imp [ i [This is the weight array from the previous generation.] Importance assignment completes the iteration and forms a new weight array. imp [ i After that, the uniformity of the weight distribution is determined by a formula, which is: ; The calculation ends and the result is saved when the weights are evenly distributed and the statistical standard deviation of the calculation result is less than the target value. If the weights are evenly distributed but the statistical standard deviation still does not meet the requirements, the importance assignment is repeated until the statistical standard deviation is less than the target value.
[0044] For example, Figure 3The diagram shows the typical ionization chamber channel layout of a research reactor, including 7 inner ionization chamber channels (numbered 13-19) and 12 outer ionization chamber channels (numbered 1-12). Figures 4(a) and 4(b) show the arrangement of the outer and inner ionization chamber channels in the calculation model built according to the specific core loading scheme. According to the above calculation method, the statistical standard deviation of the ion flux rate count in the ionization chamber region can be reduced to 3.4% after 2 iterations, while the statistical standard deviation of the direct calculation result without using the variance reduction method is 34.0%.
[0045] This iterative variance reduction method, applicable to outer ionization chamber channels, achieves high-confidence calculation results through multiple iterations based on the cell weighting method for specific ionization chamber channels. The efficient and accurate variance reduction method can quickly obtain counting results for ionization chambers located at different positions under different loading schemes. It improves the accuracy of neutron flux rate counting within outer ionization chamber channels using the same computing resources, providing reliable data support for ionization chamber location selection and evaluation. This method can serve the design and evaluation of ionization chamber layout schemes, solving the problem that the accuracy of physical calculation results decreases or even fails to obtain counts when the ionization chamber is located outside the active region of the research reactor core, thus failing to guide the selection of ionization chamber locations.
[0046] Step 204: Use detectors at different positions in the detector channel to detect the reactor core and obtain the detection response data corresponding to different detectors.
[0047] Optionally, step 204 may specifically include: constructing a detector model corresponding to the reactor based on the detector structure data corresponding to the reactor; arranging detector models at different positions in different channels of the channel model; using the detector models to detect the reactor core in the core model; and obtaining the detection response data corresponding to the detector models.
[0048] For example, detector structure data may include physical composition, geometric dimensions, material composition, etc., which can be used to build a detector model, such as an ionization chamber model. This model may include, but is not limited to, external electrodes, fission chambers, coatings, internal electrodes, and external cladding layers, which constitute the main structure of the ionization chamber. Then, the ionization chamber model can be placed in a specific ionization chamber channel, so that the ionization chamber model is located in the active region of the reactor core and the neutron flux information at the corresponding location can be obtained based on the calculation results.
[0049] Optionally, multiple models corresponding to the reactor can be processed independently. For example, the active core region model, ionization chamber channel model, and ionization chamber model of the research reactor can be separated. For the same research reactor, the parameters of the ionization chamber channel will not change each time the model is built. The active core region model of the research reactor changes in real time according to the specific core loading, and the specific core loading information is digitized and converted into matrix information of cell number-component type-burnup. The geometry and material information of the detector model will not change, but its position information can be arbitrarily changed according to the specific core loading scheme and other requirements. By making the models independent, it is helpful to manage and update the data of different models, thereby improving the construction efficiency of reactor models.
[0050] For example, information about the research reactor itself, the ionization chamber channels, and the ionization chamber can be stored, modified, and transmitted in the form of multiple digital matrices, enabling calls and information interaction between multiple modules / processes, thereby realizing the digitization of reactor core loading information.
[0051] Step 205: Based on the detection response data corresponding to different detectors, conduct a response consistency assessment of different detectors and obtain the response assessment results of different detectors.
[0052] Optionally, step 205 may specifically include: determining different detector combinations based on different positions in the different detector channels; and using consistency evaluation indicators to evaluate the response consistency of different detector combinations based on the detection response data corresponding to different detector combinations, thereby obtaining the response evaluation results corresponding to different detector combinations.
[0053] In some embodiments, the detector placement can be selected and evaluated based on the count consistency of different detector combinations at different locations. Consistency evaluation indicators may include, but are not limited to, the root mean square error (RMSE) of neutron flux rate counts. For example, the role of the ionization chamber in the research reactor physics startup is to provide real-time and accurate feedback of the core power state during the core startup phase. Based on this, the principle for ionization chamber placement is the consistency of counts, meaning that the count changes between ionization chamber regions at different heights of different ionization chamber channels under different startup rod positions are consistent. The counts at all possible ionization chamber placement positions are calculated according to the determined research reactor core calculation model, forming a count matrix between startup rod position, ionization chamber channel, and height. The MSE of all data in each dimension of the matrix is then calculated; a smaller MSE indicates higher consistency among the data.
[0054] Optionally, the number of detectors corresponding to the detector combination can be determined based on the preset number of detectors.
[0055] For example, the research reactor has three ionization chambers for physical startup, arranged at different heights within three different ionization chamber channels. The placement of the ionization chambers is determined based on the consistency of the count changes in the three ionization chambers during startup, ensuring that all three ionization chambers reflect the changes in the total power of the research reactor core. Specifically, the consistency of the response of the ionization chamber placement positions can be evaluated by the root mean square error (RMSE) of the count results at different heights within the same ionization chamber channel. For example, a smaller MSE of the counts at different heights within the same ionization chamber channel indicates better consistency for that ionization chamber channel, and a smaller MSE of the counts at the same height across different ionization chamber channels indicates better consistency at that height. Based on this, a relative count matrix of ion flux rate in the ionization chamber region can be formed, representing the ionization chamber channel-axial height. The MSE of the counts under each combination is calculated using a permutation and combination method, and finally, the three ionization chamber placement positions with the best consistency are selected. This allows us to construct a multidimensional counting matrix and calculate the mean square error between the data in each dimension to measure the consistency between the ionization chamber location and the parameter changes during reactor startup, thus guiding the selection of the ionization chamber location.
[0056] In this way, a transformation path was constructed between the physical model, the database, and unified indicators, realizing the two-dimensional matrixing of detector placement information. The data calculation results within the two-dimensional matrix were used to evaluate the detector placement scheme. Specifically, the mean square error of detector counts at different locations was used to assess the consistency of the data. Data consistency can directly reflect the accuracy and uniformity of the detection location technology in studying the overall parameter changes of the reactor core, and thus determine representative detector placement locations.
[0057] Step 206: Based on the response evaluation results of different detectors, determine the target position from different positions of the detector channel.
[0058] Optionally, step 206 may specifically include: determining the target detector combination from different detector combinations based on the consistency evaluation index corresponding to different detector combinations; determining the detector channel corresponding to the target detector combination as the target channel, and determining the target position corresponding to the target detector combination in the target channel.
[0059] The target location can be used to deploy target detectors to detect the core state of the reactor core. The target detectors can include detectors corresponding to a preset number of detectors, and the target location can include locations corresponding to a preset number of detectors.
[0060] Optionally, the target location can be determined from different locations of the detector channels. Specifically, this may include: using a preset location selection model, generating a counting matrix corresponding to different detectors based on the core loading data and the detector channels; the preset location selection model is used to predict different detector combinations corresponding to different core loading data, as well as consistency evaluation indicators corresponding to different detector combinations; and determining the target detector combination from different detector combinations based on the counting matrix.
[0061] In some embodiments, a training database can be constructed based on machine learning methods, using the numerical matrix of the reactor core and the location of the ionization chambers as the input set, and the counting matrix and the mean square error results as the output set. This database can be automatically updated as the number of operating reactor sections in the research reactor increases. By training the neural network through the training database, a preset location selection model (such as an ionization chamber layout location selection model) can be formed, which can directly obtain the output set parameters through the input set parameters without physical calculations. This further shortens the design time of the ionization chamber layout scheme and enables rapid evaluation of different ionization chamber layout locations. Specifically, during the training process of the ionization chamber placement location selection model, a neural network training database can be constructed first. Each cell in the active region of the historical core loading data is numbered, and the components arranged within each cell and the burnup of the fuel are recorded as the input set. The historical count matrix calculated from the start-up rod positions in the historical core loading data is used as the output set. The detector combination methods and the root mean square error of the counts at different locations are also used as the output set. The input and output sets are stored to form the training set. The results of existing loading schemes and each new loading scheme are integrated and stored in the training set format to form the final training database. Then, the ionization chamber placement location selection model can be trained based on the training database. The neural network simulates the mapping relationship between core loading and the root mean square error of the ionization chamber count matrix, generating a neural network combination with specific functions. The neural network model is trained using the training database, while a database update interface is reserved to add data to the training database and train the ionization chamber placement location selection model in real time.
[0062] In this way, the selection of ionization chamber locations is automatically completed based on the core loading scheme. The converted core loading layout digital matrix can be automatically read, and the ionization chamber location selection model can be automatically invoked to obtain consistency information of the ionization chamber location. The ionization chamber location selection model can obtain a highly consistent ionization chamber layout scheme based on the specific core loading scheme without performing core transport calculations, thereby improving the efficiency of location selection. Secondly, the model's training database comes from existing loading schemes and can be updated and supplemented as the research reactor operates, and the model can be autonomously trained after the database is updated.
[0063] Step 207: Arrange the target detector in the target channel according to the coordinate information corresponding to the target position.
[0064] In some embodiments, after determining the target location, the target channel corresponding to the target location and its specific position in the target channel can be obtained, and the coordinate information of the target location in the core model can be obtained. The target detectors are then arranged according to the coordinate information and applied to the subsequent reactor status monitoring. In this way, after obtaining the target detector arrangement scheme, the part of the calculation model involving the core loading and detectors of the research reactor can be updated, and the calculation model under the current loading of the research reactor can be obtained in real time for scientific research and design work. This enables flexible adjustment of the corresponding detector positions according to different core loading schemes, thereby improving the accuracy of the detection results.
[0065] Optionally, the method in this embodiment may further include: using an evolutionary algorithm to automatically generate and optimize ion chamber layout schemes by calling an ion chamber placement location selection model for different design criteria. Its input parameters include, but are not limited to, the number of ion chambers, the number of startup steps, and the core loading digital matrix. The calculation process of the ion chamber placement location selection model is used as the solution process for the fitness function. Finally, the final mean square error of different ion chamber layout schemes is used as the solution of the fitness function, thereby achieving iterative optimization and selection of ion chamber layout schemes. After the automatic optimization of the ion chamber layout scheme is completed, the parameters of the final scheme are recorded and fed back into the digital matrix of the computational model building program, automatically generating the computational model of the final scheme for design and development use. This automatically optimizes the target layout scheme, enabling calls between the computational model, evaluation model, and surrogate model, and improving the design efficiency of the ion chamber layout scheme.
[0066] In this way, this embodiment enables rapid and automatic modeling of the reactor core loading scheme and the ionization chamber channels and regions outside the core. It constructs a method for selecting and evaluating the placement of ionization chambers for reactor physics startup, establishes an iterative variance reduction method for outer ionization chambers, a model for selecting ionization chamber placement, and an automatic scheme optimization method. This addresses the current problems of insufficient representativeness, poor consistency, and low calculation accuracy for certain operating conditions in reactor physics startup ionization chambers. This embodiment includes methods for establishing a reactor computational model, iterative variance reduction methods, placement selection and evaluation methods, placement selection models, and automatic optimization of placement schemes. These methods can be applied to the iterative optimization of ionization chamber placement schemes for reactor physics startup and provide technical support for reactor core design optimization. It solves the problem that current reactor physics startup ionization chambers cannot accurately reflect the overall core parameter changes during startup due to parameter variations between ionization chambers at different locations.
[0067] As one possible implementation method, the specific calculation and analysis process for the ionization chamber arrangement method may include the following steps: Step 1: Build a calculation model of the ionization chamber for the physics start-up of the research reactor. Based on the core loading scheme, establish a model of the research reactor core and its outer ionization chamber channels. Based on the ionization chamber structure data, construct the ionization chamber model and place the ionization chamber model into the specific ionization chamber channels so that the ionization chamber model is located in the active region of the core and the neutron flux information at the corresponding location can be obtained from the calculation results. Step 2: Based on the computational model established in Step 1, conduct neutron and photon transport calculations in the reactor core. The counting regions are the ionization chamber coating and the fission chamber. Different calculation methods are used for the ionization chambers in the inner and outer ionization chamber channels. Step 3: Calculate the response data of the ionization chamber within the outer ionization chamber channel based on iterative variance reduction; Step 4: Conduct a consistency assessment based on the root mean square error of the counts corresponding to ionization chambers at different locations, and determine the location of the ionization chambers based on the consistency assessment results; Step 5: Train the model for selecting the location of the ionization chamber; Step 6: Automated selection of ionization chamber placement locations is performed using an ionization chamber placement location selection model. The arrangement data within each gate cell of the active region is digitized and used as input parameters to the ionization chamber placement location selection model. The model outputs the corresponding ionization chamber counting matrix. Optionally, the deviation of the ionization chamber counting matrix obtained in this step can be evaluated. If the deviation is less than a preset deviation threshold, this step replaces the permutation and combination method in Step 3, and the ionization chamber placement location is determined based on the obtained ionization chamber counting matrix. If the deviation is not less than the preset deviation threshold, the permutation and combination method in Step 3 is used to determine the ionization chamber placement location. Step 7: After obtaining the location of the ionization chamber, the coordinate information of the location is automatically generated. The ionization chamber is placed at the corresponding coordinates in the calculation model built in Step 1, forming the final calculation model of the ionization chamber for the research reactor physics start-up, which is used for scientific research and engineering applications.
[0068] In this way, this embodiment can establish an ionization chamber calculation model based on the reactor core loading scheme, establish an iterative variance reduction method and process for the outer ionization chamber channels, establish a method for selecting and evaluating the ionization chamber layout location, form a training database for the ionization chamber location selection model according to the specific reactor core loading scheme, and realize a machine learning-based ionization chamber layout location selection model. This model can realize the autonomous updating and training of the training database and model, and use evolutionary algorithms to construct a method and program that can automatically select the ionization chamber layout location for physical start-up, and realize the updating of the calculation model after the ionization chamber layout location for physical start-up is selected.
[0069] Compared with related technologies, this embodiment can determine the corresponding reactor core and available detector channels based on different reactor core loading data. Then, it uses the detection response data of the detectors at different positions in different detector channels to perform response consistency evaluation. Based on the response evaluation results of detectors at different positions, it determines multiple target positions with high response consistency. Based on these target positions, it arranges multiple target detectors in the reactor core. In this way, the target detectors corresponding to different reactor cores are determined based on the response consistency of different detectors. This is applicable to various flexible and asymmetric reactor core loading schemes, and it realizes the adjustment of the target positions of the target detectors according to different reactor core loading data, thereby improving the accuracy of reactor core detection. Secondly, different detection response data calculation methods can be used for the regional positions of the detector chamber channels. For the outer detector channels, the cell weighting method is used to obtain high-confidence calculation results through multiple iterations. Under the same computing resources, the neutron fluence rate counting accuracy in the outer ionization chamber channels is improved. Furthermore, a preset position selection model can be used to determine the target positions, obtaining a highly consistent detector arrangement scheme without performing reactor core transport calculations, thus improving the efficiency of position selection.
[0070] Based on the above Figure 1 and Figure 2 The specific implementation of the method shown in this embodiment provides a detector arrangement device, such as... Figure 5 As shown, the device includes: an acquisition module 31, a determination module 32, a detection module 33, and an evaluation module 34; Acquisition module 31 is used to acquire reactor core loading data; Module 32 is used to determine the core and detector channels corresponding to the core loading data; The detection module 33 is used to detect the reactor core using detectors at different positions in the detector channel and obtain detection response data corresponding to different detectors. The evaluation module 34 is used to evaluate the response consistency of different detectors based on the detection response data corresponding to different detectors, and obtain the response evaluation results of different detectors; based on the response evaluation results of different detectors, the target position is determined from different positions of the detector channel, and the target position is used to deploy the target detector to detect the core state of the reactor core.
[0071] In some examples of this embodiment, the determining module 32 is specifically configured to determine the detection response data corresponding to different detectors based on the regional position of the detector channels corresponding to different detectors; determining the detection response data corresponding to different detectors based on the regional position of the detector channels corresponding to different detectors includes: if the detector channel is an inner layer detector channel, then the detection response data corresponding to different detectors is directly obtained based on the position of different detectors in the inner layer detector channel; if the detector channel is an outer layer detector channel, then the detection response data corresponding to different detectors is obtained based on the calculation accuracy requirements of the detection response data corresponding to the outer layer detector channel.
[0072] In some examples of this embodiment, the acquisition module 31 is specifically configured to reconstruct the geometry of the outer ionization chamber channel, determine the deletion element corresponding to the outer ionization chamber channel based on the annular region between the active region corresponding to the core and the outer ionization chamber channel, obtain the importance assignment corresponding to the deletion element, and determine the detection response data according to the importance assignment of the deletion element and the calculation accuracy requirements of the detection response data.
[0073] In some examples of this embodiment, the determining module 32 is specifically configured to calculate the detection response data corresponding to the outer ionization chamber channel based on the importance assignment of the deleted element; determine whether the detection response data corresponding to the outer ionization chamber channel meets the calculation accuracy requirements; if the detection response data corresponding to the outer ionization chamber channel does not meet the calculation accuracy requirements, then iterate the importance assignment of the deleted element until the detection response data calculated based on the iterated importance assignment meets the calculation accuracy requirements.
[0074] In some examples of this embodiment, the evaluation module 34 is specifically configured to determine different detector combinations based on different positions in different detector channels; and to evaluate the response consistency of different detector combinations using a consistency evaluation index based on the detection response data corresponding to different detector combinations, thereby obtaining the response evaluation results corresponding to different detector combinations.
[0075] In some examples of this embodiment, the evaluation module 34 is specifically configured to use a preset location selection model to generate a counting matrix corresponding to different detectors based on the core loading data and detector channels. The preset location selection model is used to predict different detector combinations corresponding to different core loading data, as well as consistency evaluation indicators corresponding to different detector combinations. The target detector combination is determined from different detector combinations based on the counting matrix.
[0076] In some examples of this embodiment, the determining module 32 is specifically configured to determine the target detector combination from different detector combinations based on the consistency evaluation index corresponding to different detector combinations; determine the detector channel corresponding to the target detector combination as the target channel; and determine the target position corresponding to the target detector combination in the target channel.
[0077] In some examples of this embodiment, the determining module 32 is further configured to arrange a target detector in the target channel according to the coordinate information corresponding to the target position.
[0078] In some examples of this embodiment, the determining module 32 is specifically configured to use core loading data to construct a core model corresponding to the reactor; construct a pore model corresponding to the reactor based on preset pore data corresponding to the reactor; and determine the core and detector pores corresponding to the core loading data based on the core model after adding the pore model.
[0079] In some examples of this embodiment, the detection module 33 is specifically configured to construct a detector model corresponding to the reactor based on the detector structure data corresponding to the reactor; arrange the detector model at different positions in different channels of the channel model; use the detector model to detect the core in the core model; and obtain the detection response data corresponding to the detector model.
[0080] Based on the above, Figure 1 and Figure 2 Accordingly, this embodiment also provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a processor, implements the above-described method. Figure 1 and Figure 2 The method shown.
[0081] Based on this understanding, the technical solution disclosed herein can be embodied in the form of a software product, which can be stored in a non-volatile storage medium (such as a CD-ROM, USB flash drive, or portable hard drive) and includes several instructions to cause a computer device (such as a personal computer, server, or network device) to execute the methods of various implementation scenarios of this disclosure.
[0082] Based on the above, Figure 1 and Figure 2 The method shown, and Figure 5 To achieve the above objectives, this disclosure also provides an electronic device, comprising a storage medium and a processor; the storage medium for storing a computer program; and the processor for executing the computer program to implement the above-described virtual device embodiments. Figure 1 and Figure 2 The method shown.
[0083] Optionally, the aforementioned physical devices may also include a user interface, a network interface, a camera, radio frequency (RF) circuitry, sensors, audio circuitry, a Wi-Fi module, etc. The user interface may include a display screen, input units such as a keyboard, etc., and optional user interfaces may also include USB interfaces, card reader interfaces, etc. The network interface may optionally include standard wired interfaces, wireless interfaces (such as Wi-Fi interfaces), etc.
[0084] Those skilled in the art will understand that the physical device structure provided in this embodiment does not constitute a limitation on the physical device, and may include more or fewer components, or combine certain components, or have different component arrangements.
[0085] The storage medium may also include an operating system and a network communication module. The operating system is a program that manages the hardware and software resources of the aforementioned physical device, supporting the operation of information processing programs and other software and / or programs. The network communication module is used to enable communication between the various components within the storage medium, as well as communication with other hardware and software in the information processing physical device.
[0086] Through the above description of the embodiments, those skilled in the art can clearly understand that this disclosure can be implemented using software plus necessary general-purpose hardware platforms, or it can be implemented in hardware. The solution of this disclosure can determine the corresponding reactor core and available detector channels based on different reactor core loading data. Then, by using the detectors at different positions in different detector channels to measure the core detection response data, a response consistency assessment is performed. Based on the response assessment results of detectors at different positions, multiple target positions with high response consistency are determined. Based on these target positions, multiple corresponding target detectors are arranged in the reactor core. This method determines the target detectors corresponding to different reactor cores based on the response consistency of different detectors. It is applicable to various flexible and asymmetric reactor core loading schemes, enabling the adjustment of the target positions of the target detectors according to different reactor core loading data, thereby improving the accuracy of core detection. Secondly, different detection response data calculation methods can be adopted for the regional location of the detection chamber channel. For the outer detector channel, the high-confidence calculation results can be obtained through multiple iterations based on the grid element weight method. Under the same computing resources, the neutron fluence rate counting accuracy in the outer ionization chamber channel can be improved. Furthermore, the target location can be determined by using a preset location selection model. A highly consistent detector layout scheme can be obtained without performing core transport calculations, thereby improving the efficiency of location selection.
[0087] It should be noted that, in this document, relational terms such as "first" and "second" are used merely to distinguish one entity or operation from another, and do not necessarily require or imply any such actual relationship or order between these entities or operations. Furthermore, the term "comprising" or any other variations thereof is intended to cover non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements includes not only those elements but also other elements not expressly listed, or elements inherent to such a process, method, article, or apparatus. Without further limitations, an element defined by the phrase "comprising one..." does not exclude the presence of other identical elements in the process, method, article, or apparatus that includes the element.
[0088] The above are merely specific embodiments of this disclosure, enabling those skilled in the art to understand or implement this disclosure. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the general principles defined herein may be implemented in other embodiments without departing from the spirit or scope of this disclosure. Therefore, this disclosure is not to be limited to these embodiments, but is to be accorded the widest scope consistent with the principles and novel features claimed herein.
Claims
1. A detector arrangement method, characterized in that, include: Obtain reactor core loading data; Determine the core and detector channels corresponding to the core loading data; The reactor core is detected by detectors at different positions in the detector channel to obtain detection response data corresponding to different detectors; Based on the detection response data corresponding to the different detectors, the response consistency of the different detectors is evaluated, and the response evaluation results of the different detectors are obtained. Based on the response evaluation results of the different detectors, a target position is determined from different positions of the detector channels. The target position is used to deploy a target detector to detect the core state of the reactor core.
2. The method according to claim 1, characterized in that, Before evaluating the response consistency of the different detector combinations using a consistency evaluation index based on the detection response data corresponding to the different detector combinations, the method further includes: The detection response data corresponding to the different detectors is determined based on the regional location of the detector channels corresponding to the different detectors. The step of determining the detection response data corresponding to different detectors based on the regional location of the detector channels corresponding to different detectors includes: If the detector channel is an inner layer detector channel, then the detection response data corresponding to the different detectors can be directly obtained according to the positions of the different detectors in the inner layer detector channel; If the detector channel is an outer detector channel, then based on the calculation accuracy requirements of the detection response data corresponding to the outer detector channel, the detection response data corresponding to the different detectors are obtained.
3. The method according to claim 2, characterized in that, The calculation accuracy requirement based on the detector counting region corresponding to the outer detector channel, and the acquisition of detection response data corresponding to different detectors, includes: The geometry of the outer ionization chamber channel is reconstructed, and the deletion element corresponding to the outer ionization chamber channel is determined based on the annular region between the active region corresponding to the core and the outer ionization chamber channel. The importance value corresponding to the deletion element is then obtained. The detection response data is determined based on the importance assignment of the deleted element and the required accuracy of the detection response data calculation.
4. The method according to claim 3, characterized in that, The step of determining the detection response data based on the importance assignment of the deleted element and the calculation accuracy requirements of the detection response data includes: Calculate the detection response data corresponding to the outer ionization chamber channel based on the importance assignment of the deleted element; Determine whether the detection response data corresponding to the outer ionization chamber channel meets the calculation accuracy requirements; If the detection response data corresponding to the outer ionization chamber channel does not meet the calculation accuracy requirement, the importance assignment of the deleted element is iterated repeatedly until the detection response data calculated based on the iterated importance assignment meets the calculation accuracy requirement.
5. The method according to claim 1, characterized in that, The step of evaluating the response consistency of the different detectors based on the detection response data corresponding to the different detectors, and obtaining the response evaluation results of the different detectors, includes: Different detector combinations are determined based on the different positions within the different detector channels; Based on the detection response data corresponding to the different detector combinations, the response consistency of the different detector combinations is evaluated using the consistency evaluation index, and the response evaluation results corresponding to the different detector combinations are obtained.
6. The method according to claim 5, characterized in that, The step of determining the target location from different positions in the detector channel based on the response evaluation results of the different detectors includes: Based on the consistency evaluation index corresponding to different detector combinations, the target detector combination is determined from the different detector combinations; The detector channel corresponding to the target detector assembly is defined as the target channel, and the target position corresponding to the target detector assembly is determined in the target channel.
7. The method according to claim 6, characterized in that, Determining the target detector combination from the different detector combinations includes: Using a preset location selection model, a counting matrix corresponding to different detectors is generated based on the core loading data and the detector channels. The preset location selection model is used to predict different detector combinations corresponding to different core loading data, as well as consistency evaluation indicators corresponding to different detector combinations. The target detector combination is determined from the different detector combinations based on the counting matrix.
8. The method according to claim 6, characterized in that, After determining the target location from different positions of the detector channel based on the response evaluation results of the different detectors, the method further includes: The target detector is arranged in the target channel according to the coordinate information corresponding to the target position.
9. The method according to claim 1, characterized in that, Determining the core and detector aperture corresponding to the core loading data includes: Using the core loading data, a core model corresponding to the reactor is constructed; Based on the preset pore data corresponding to the reactor, construct the pore model corresponding to the reactor; Based on the core model after adding the channel model, the core and detector channels corresponding to the core loading data are determined.
10. The method according to claim 1, characterized in that, The process of using detectors at different positions within the detector channel to probe the reactor core and obtain detection response data corresponding to different detectors includes: Based on the detector structure data corresponding to the reactor, construct the detector model corresponding to the reactor; The detector model is arranged at different positions in different channels of the channel model, and the core in the core model is detected by the detector model to obtain the detection response data corresponding to the detector model.
11. A detector arrangement device, characterized in that, include: The acquisition module is used to acquire reactor core loading data; The determination module is used to determine the core and detector aperture corresponding to the core loading data; The detection module is used to detect the reactor core using detectors at different positions in the detector channel, and obtain detection response data corresponding to different detectors; The evaluation module is used to evaluate the response consistency of the different detectors based on the detection response data corresponding to the different detectors, and obtain the response evaluation results of the different detectors; based on the response evaluation results of the different detectors, the target position is determined from different positions of the detector channels, and the target position is used to deploy the target detector to detect the core state of the reactor core.
12. An electronic device, characterized in that, include: At least one processor; as well as A memory communicatively connected to the at least one processor; wherein, The memory stores instructions executable by the at least one processor, which, when executed by the at least one processor, enables the at least one processor to perform the method of any one of claims 1-10.
13. A non-transitory computer-readable storage medium storing computer instructions, wherein, The computer instructions are used to cause the computer to perform the method according to any one of claims 1-10.