Nucleus type rapid identification method and device

Abstract

This invention provides a method and device for rapid identification of nuclide types, relating to the field of radiation detection. The method includes: using a radiation source detector to detect a target radioactive source; acquiring pulse count data and charge integral data collected by the radiation source detector within a target time period while detecting the target radioactive source; determining a target nuclide type factor based on the pulse count data and the charge integral data; wherein the target nuclide type factor is used to characterize the average energy of the radioactive source; and determining the nuclide type of the radioactive source based on the target nuclide type factor and a preset relationship table; wherein the preset relationship table includes multiple preset nuclide type factors and their corresponding preset nuclide types. This method can meet the need for rapid screening in radioactive monitoring scenarios, achieving nuclide identification without relying on energy spectrum analysis and with low hardware costs.

Description

Technical Field

[0001] This invention relates to the field of radiation detection, and more specifically, to a method and device for rapid identification of nuclide types. Background Technology

[0002] In the field of nuclear radiation safety monitoring, rapid and accurate identification of radionuclides is crucial for customs security, nuclear emergency response, nuclear waste management, and nuclear medicine applications. Currently, gamma-ray spectroscopy (such as NaI(Tl) detectors combined with spectral analysis software) is the primary technique for nuclide identification. It relies on the precise measurement and analysis of the full-energy gamma-ray peaks, achieving identification by comparing characteristic peak energies with a nuclide database. In recent years, machine learning-based nuclide identification methods (such as convolutional neural networks (CNNs)) have also been increasingly applied. These methods directly extract features from spectral data, reducing reliance on full-energy peaks and improving identification capabilities under complex spectral conditions.

[0003] However, the above-mentioned radionuclide type identification techniques based on gamma spectroscopy still have the following limitations:

[0004] 1. Slow response speed: Because sufficient full-energy peak counts need to be accumulated in the energy spectrum to form clear full-energy peaks, it usually takes several minutes to measure, which is difficult to meet the needs of real-time monitoring (such as fast customs clearance).

[0005] 2. Limited identification of low-activity samples: Under low count rates, the statistical fluctuations of the full-energy peak are significant, leading to misjudgment or missed detection.

[0006] 3. Dependence on hardware performance: High-precision energy dispersive spectroscopy (EDS) typically requires semiconductor detectors, but these are expensive and difficult to widely apply. Commonly used scintillator detectors, such as sodium iodide detectors, also require the integration of high-performance ADCs (analog-to-digital converters) and digital signal processing modules, further increasing equipment costs. Deep neural networks (such as CNNs) additionally require GPUs or high-performance embedded processors to support real-time inference, further increasing costs.

[0007] In summary, traditional nuclide identification methods rely on multichannel energy dispersive spectroscopy (EDS) systems, which suffer from problems such as complex equipment, high cost, and time-consuming analysis. Therefore, there is a need for a nuclide identification method that balances speed and reliability, enabling preliminary nuclide screening within seconds without waiting for complete EDS analysis, and synergizing with high-precision EDS to improve monitoring efficiency and accuracy in scenarios such as customs and nuclear emergencies. Summary of the Invention

[0008] In view of this, the purpose of the present invention is to provide a method and device for rapid identification of nuclide types, which can meet the needs of rapid screening in radioactive monitoring scenarios and achieve nuclide identification without relying on energy spectrum analysis and with low hardware costs.

[0009] To achieve the above objectives, the technical solutions adopted in the embodiments of the present invention are as follows:

[0010] In a first aspect, the present invention provides a method for rapid identification of nuclide types, comprising the following steps: using a radioactive source detector to detect a target radioactive source; while the radioactive source detector detects the target radioactive source, acquiring pulse count data and charge integral data collected by the radioactive source detector within a target time period; determining a target nuclide type factor based on the pulse count data and the charge integral data; wherein the target nuclide type factor is used to characterize the average energy of the radioactive source; and determining the nuclide type of the radioactive source based on the target nuclide type factor and a preset relationship table; wherein the preset relationship table includes a correspondence between multiple preset nuclide type factors and preset nuclide types.

[0011] It should be understood that this application proposes a technique for nuclide type determination based on pulse-charge dual-mode signal fusion. Specifically, it utilizes pulse count data and charge integration data collected simultaneously by a radiation source detector to determine the target nuclide type factor, thereby approximating the average energy of gamma photons emitted by the radiation source. Since different nuclides have different gamma-ray energy distributions, their average energies differ significantly; therefore, this average energy can serve as a preliminary characteristic for nuclide type identification. By comparing the calculated target nuclide type factor with a preset relationship table, preliminary identification of the nuclide type of the target radiation source can be achieved quickly and easily without relying on high-resolution energy spectrum analysis. This method is applicable to various types of detectors (such as scintillators, semiconductors, gas detectors, etc.), possessing good versatility and practicality, and is particularly suitable for rapid on-site screening and dose monitoring scenarios.

[0012] In an optional embodiment, the target nuclide type factor is determined based on the ratio of charge integral data to pulse count data.

[0013] In an optional embodiment, the step of determining the target nuclide type factor based on pulse count data and charge integral data includes: determining the target nuclide type factor according to the following formula: ;in, Indicates the target nuclide type factor. This represents the cumulative amount of charge detected continuously within the target time period. This indicates the cumulative number of pulses detected continuously within the target time period.

[0014] In an optional embodiment, the pulse count data is the net count data after deducting the background pulse count, and the charge integral data is the net charge integral data after deducting the background charge integral.

[0015] In an optional embodiment, the radionuclide type of the radioactive source is determined according to the target nuclide type factor and a preset relationship table, including the following steps: performing similarity matching between the target nuclide type factor and multiple preset nuclide type factors in the preset relationship table to determine the preset nuclide type factor with the highest similarity; and determining the nuclide type of the radioactive source according to the preset nuclide type corresponding to the preset nuclide type factor with the highest similarity.

[0016] In an optional embodiment, the preset relationship table is determined according to the following steps: obtaining standard average energy data of multiple standard sources with different nuclides; performing Monte Carlo simulation based on the multiple standard average energy data to obtain the simulated average energy data of multiple simulated radioactive sources different from the standard sources in the radioactive source detector; and determining the preset relationship table based on the multiple standard average energy data, multiple standard sources, multiple simulated average energy data, and multiple simulated radioactive sources.

[0017] In an optional embodiment, before using a radiation source detector to detect the target radiation source, the method further includes the step of calibrating the radiation source detector with energy using standard sources of multiple different nuclides.

[0018] In an optional embodiment, the steps of acquiring pulse count data and charge integration data collected by the radiation source detector within a target time period include: copying the signal output by the signal output terminal of the radiation source detector into a first signal and a second signal; acquiring pulse count data collected by the radiation source detector within the target time period based on the first signal; and acquiring charge integration data collected by the radiation source detector within the target time period based on the second signal.

[0019] In an optional embodiment, the radiation source detector includes any one of the following detectors: a gas detector, a scintillator detector, or a semiconductor detector.

[0020] In a second aspect, the present invention provides a rapid identification device for radionuclide types, comprising: a radiation source detector and a data processor; the data processor is used to control the radiation source detector to implement the method described in the first aspect.

[0021] Thirdly, the present invention provides a computer-readable storage medium including instructions that, when executed on a data processor of a nuclide type rapid identification device, cause the data processor to implement the method described in any of the embodiments of the first aspect.

[0022] To make the above-mentioned objects, features and advantages of the present invention more apparent and understandable, embodiments of the present invention are described below in detail with reference to the accompanying drawings. Attached Figure Description

[0023] To more clearly illustrate the technical solutions of the embodiments of the present invention, the accompanying drawings used in the embodiments of the present invention will be briefly introduced below. It should be understood that the following drawings only show some embodiments of the present invention and should not be regarded as a limitation on the scope. For those skilled in the art, other related drawings can be obtained based on these drawings without creative effort.

[0024] Figure 1 A structural block diagram of a rapid nuclide type identification device provided in an embodiment of the present invention;

[0025] Figure 2 A flowchart illustrating a rapid nuclide type identification method provided in an embodiment of the present invention;

[0026] Figure 3 This is another flowchart illustrating a rapid identification method for nuclide types provided in an embodiment of the present invention;

[0027] Figure 4 A flowchart illustrating the process of establishing a nuclide database as provided in an embodiment of the present invention;

[0028] Figure 5 This is a functional block diagram of a data reading and processing module provided in an embodiment of the present invention. Detailed Implementation

[0029] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. The components of the embodiments of the present invention described and shown in the accompanying drawings can generally be arranged and designed in various different configurations.

[0030] Therefore, the following detailed description of the embodiments of the invention provided in the accompanying drawings is not intended to limit the scope of the claimed invention, but merely to illustrate selected embodiments of the invention. All other embodiments obtained by those skilled in the art based on the embodiments of the invention without inventive effort are within the scope of protection of the invention.

[0031] It should be noted that similar labels and letters in the following figures indicate similar items. Therefore, once an item is defined in one figure, it does not need to be further defined and explained in subsequent figures.

[0032] It should be noted that, where there is no conflict, the features in the embodiments of the present invention can be combined with each other.

[0033] This invention provides a technical solution including a method and device for rapid identification of nuclide types, relating to the field of radiation detection. The technical solution provided by this invention will be described below with reference to the accompanying drawings.

[0034] First, we introduce a rapid nuclide type identification device provided in an embodiment of the present invention. Please refer to... Figure 1 The device 100 includes a radiation source detector 110 and a data processor 130.

[0035] Alternatively, the data processor 130 can be integrated as a module into the radiation source detector 110, or it can be a separate device from the radiation source detector 110.

[0036] In this application embodiment, the radiation source detector 110 can refer to any detection device capable of responding to gamma rays, including but not limited to gas detectors, scintillator detectors, or semiconductor detectors. Alternatively, the radiation source detector 110 in this application includes any one of the following detectors: gas detector, scintillator detector, or semiconductor detector.

[0037] For example, the radiation source detector 110 in this application may employ a NaI(Tl) scintillator coupled to a photomultiplier tube architecture.

[0038] It should be noted that "radiation source detector 110" in the text can also be replaced with "radiation detector" without affecting the essence of the technical solution.

[0039] The data processor 130 can be electrically connected to the radiation source detector 110 to receive data acquired by the radiation source detector 110. Specifically, the data processor 130 can be electrically coupled to the radiation source detector 110 and is responsible for acquiring data such as pulse count data and charge integration data output by the detector in real time, without limitation.

[0040] In an optional embodiment, the data processor 130 can be a computing device including a CPU, storage circuitry, and communication interface circuitry (e.g., a laptop, desktop computer, server, etc., without limitation). The data processor 130 can be connected to the radiation source detector 110 via the communication interface circuitry. This connection method can include, but is not limited to, one or more combinations of Ethernet, USB, serial port, or wireless communication modules.

[0041] In an optional embodiment, the radiation source detector 110 can detect a radiation source. When the radiation generated by the radiation source interacts with the scintillator inside the detector, an optical signal is generated. The photoelectric sensor (such as a photomultiplier tube) built into the detector can convert these optical signals into electrical signals, which are then amplified, filtered, and converted from analog to digital by the front-end circuitry, ultimately generating detection data that is output to the data processor 130.

[0042] In this application, the data processor 130 can be used to control the radiation source detector 110 (e.g., including operating parameter configuration and acquisition control) to realize the rapid identification method of nuclide type provided in this application.

[0043] Alternatively, since the original pulse signal is usually very weak, Figure 1 The device 100 shown may also include a preamplifier 120 to enhance the original signal.

[0044] Please refer to Figure 1 The radiation source detector 110 amplifies the detected data via a preamplifier 120, then splits the signal into two data streams via a signal splitter and inputs them into the data processor 130. After acquiring these two data streams, the data processor 130 performs pulse counting on one stream and current integration on the other to obtain pulse count data and charge integration data, and then calculates the average energy. After completing the average energy calculation, the data processor 130 obtains the target nuclide type factor and can retrieve a preset relationship table from a database to match the preset relationship table with the target nuclide type factor, thereby realizing the rapid nuclide type identification method provided in this application. (About...) Figure 1 For detailed implementation methods of each step in the process, please refer to the detailed description in the subsequent method implementation section.

[0045] Based on the aforementioned equipment, this embodiment of the invention provides a rapid nuclide type identification method that can be applied to the aforementioned equipment. The rapid nuclide type identification method can be executed by the data processor 130 in the equipment to meet the needs of rapid screening in radioactive monitoring scenarios, achieving nuclide identification without relying on energy spectrum analysis and with low hardware costs.

[0046] Please see Figure 2 , Figure 2 This is a flowchart illustrating a rapid nuclide type identification method provided by an embodiment of the present invention. The method may include the following steps S210-S240, which are described sequentially below:

[0047] S210 uses radiation source detector 110 to detect the target radiation source.

[0048] For example, in a radiation monitoring scenario, the operator points the radiation source detector 110 towards or near the target radiation source to be measured and initiates the corresponding procedure. The radiation source detector 110 begins to collect radiation signals in real time. The target radiation source can be a common radionuclide such as Cs137 or Co60, or it can be an unknown type of radiation source; there are no restrictions on this.

[0049] S220, when the radiation source detector 110 detects the target radiation source, it acquires the pulse count data and charge integration data collected by the radiation source detector 110 within the target time period.

[0050] Pulse count data can be data reflecting the number of pulses. For example, pulse count data can be the number of radiation events detected by the radiation source detector 110 per unit time.

[0051] Charge integral data can be data that reflects the amount of charge integral. For example, charge integral data can be the amount of charge accumulated by the radiation source detector 110 during the detection process per unit time.

[0052] For example, the target time period can be set according to actual monitoring needs, such as 1 second to 60 seconds.

[0053] During this period, the radiation source detector 110 continuously detects the target radiation source, and the data processor 130 simultaneously acquires and stores pulse count data and charge integration data.

[0054] In an optional embodiment, the steps of acquiring pulse count data and charge integration data collected by the radiation source detector 110 within the target time period include the following steps 1.1-1.3:

[0055] Step 1.1: At the signal output terminal of the radiation source detector 110, the signal output from the signal output terminal is copied into a first signal and a second signal.

[0056] Step 1.2: Based on the first signal, acquire the pulse count data collected by the radiation source detector 110 within the target time period.

[0057] Step 1.3: Based on the second signal, acquire the charge integral data collected by the radiation source detector 110 within the target time period.

[0058] For example, the signal output from the radiation source detector 110 can be copied into two identical signals (including a first signal and a second signal) and output to the data processor 130 by a circuit (such as a signal splitter) that has the function of copying the signal into two outputs.

[0059] The data processor 130 can be configured with two channels: one for pulse counting and the other for charge integration. Each of these two channels can receive the first signal and the second signal mentioned above, respectively.

[0060] The first signal can be input to the pulse counting channel. The data processor 130 can use the signal from this channel to perform pulse counting, thereby obtaining the pulse count data collected within the target time period.

[0061] The second signal can be input into the charge integration channel. The data processor 130 can use the signal from this channel to perform charge integration, thereby obtaining the charge integration data acquired within the target time period. This data is positively correlated with the energy deposition of the incident radiation.

[0062] S230, based on pulse count data and charge integral data, determines the target nuclide type factor.

[0063] Among them, the target nuclide type factor is used to characterize the average energy of the radioactive source.

[0064] Specifically, the target nuclide type factor can be determined based on the ratio of charge integral data to pulse count data. For example, target nuclide type factor = charge integral data / pulse count data.

[0065] In an optional embodiment, S230, determining the target nuclide type factor based on pulse count data and charge integration data may include: determining the target nuclide type factor according to the following formula:

[0066] ;

[0067] in, Indicates the target nuclide type factor. This represents the cumulative amount of charge detected continuously within the target time period. This indicates the cumulative number of pulses detected continuously within the target time period.

[0068] It is understandable that, assuming the controlled variables and the type of the target radiation source remain constant, It is proportional to Therefore, it can be used The average energy of the incident gamma photon is approximated. Thus, the target nuclide type factor has good distinguishability between different types of nuclides; for example, the target nuclide type factor values ​​for Cs137 and Co60 differ significantly, thereby enabling rapid identification of nuclide types.

[0069] In an optional embodiment, the above It can also be replaced by the amount of charge per unit time during continuous detection in the target time period. Alternatively, it can be replaced by pulse counting per unit time during continuous detection within the target time period without affecting the essence of the technical solution.

[0070] In an optional embodiment, the pulse count data is the net count data after deducting the environmental background pulse count, and the charge integral data is the net charge integral data after deducting the environmental background charge integral. The specific deduction method can be found below. Figure 3 The illustrated embodiment.

[0071] S240, determine the type of radionuclide in the radioactive source based on the target nuclide type factor and the preset relationship table.

[0072] The preset relationship table includes the correspondence between multiple preset nuclide type factors and preset nuclide types.

[0073] For example, the preset relationship table can be stored in the storage medium of the data processor 130, or it can be stored in a database connected to the data processor 130 so that the data processor 130 can retrieve the preset relationship table from the database during the nuclide type determination process.

[0074] During the nuclide type determination process, the data processor 130 can obtain the preset relationship table, and then compare the target nuclide type factor with the value in the preset relationship table to determine the nuclide type.

[0075] Specifically, determining the nuclide type of the radioactive source based on the target nuclide type factor and a preset relationship table may include the following steps 2.1 and 2.2:

[0076] Step 2.1: Perform similarity matching between the target nuclide type factor and multiple preset nuclide type factors in the preset relationship table to determine the preset nuclide type factor with the highest similarity.

[0077] Step 2.2: Determine the nuclide type of the radioactive source based on the preset nuclide type factor corresponding to the preset nuclide type factor with the highest similarity.

[0078] For example, matching algorithms such as least squares or nearest neighbor can be used to calculate the difference between the value of the target nuclide type factor and multiple preset nuclide type factors in the preset relationship table, and select the nuclide type corresponding to the preset nuclide type factor with the smallest difference, thereby realizing nuclide type determination.

[0079] In an optional embodiment, the similarity matching between the target nuclide type factor and multiple preset nuclide type factors in a preset relationship table can be calculated using the following formula:

[0080] ;

[0081] Where P represents the matching degree, Indicates the target nuclide type factor. This represents the preset nuclide type factor in the preset relation table. express The uncertainty.

[0082] In an optional embodiment, the preset relationship table can be determined according to the following steps 3.1-3.3:

[0083] Step 3.1: Obtain standard average energy data from multiple standard sources with different nuclides.

[0084] The standard average energy data can be obtained from a known database, or it can be obtained, for example, by acquiring standard sources of multiple known nuclides (such as Cs137, Co60, etc.), and measuring their standard average energy data (i.e., standard average energy data) using the aforementioned detector in a standard laboratory environment. Each standard source can be measured multiple times and averaged to ensure accuracy.

[0085] Step 3.2: Perform Monte Carlo simulation based on multiple standard average energy data to obtain the simulated average energy data of multiple simulated radioactive sources different from the standard source in the radioactive source detector 110.

[0086] For example, a geometric model and physical processes of the detector are established using simulation software and Monte Carlo simulation methods. By adjusting simulation parameters, the expected responses of more types of nuclides in the detector are simulated, i.e., simulated average energy data, to expand the coverage of the preset relational table.

[0087] Step 3.3: Determine the preset relationship table based on multiple standard average energy data, multiple standard sources, multiple simulated average energy data, and multiple simulated radioactive sources.

[0088] For example, by merging measured standard source data with simulation data, nuclide names and average energy data (i.e., The mapping relationship table is stored (e.g., in a database or in the data processor 130 mentioned above).

[0089] In an optional embodiment, for the above Figure 1 The method embodiment shown includes the following step before using the radiation source detector 110 to detect the target radiation source: calibrating the radiation source detector 110 with energy using standard sources of multiple different nuclides.

[0090] Specifically, before the equipment is put into use or during routine maintenance, calibration measurements are performed using standard sources such as Cs137 and Co60, and their respective average energy data (i.e., This is then compared with the expected value. If a deviation exists, it is adjusted using a software correction factor to ensure the accuracy of the preset relationship table.

[0091] The following will take the architecture of the radiation source detector using a NaI(Tl) scintillator coupled with a photomultiplier tube as an example, combined with... Figure 3 , Figure 4 The method steps in the above method embodiments are illustrated with examples.

[0092] Please refer to Figure 3 , Figure 3 The method embodiment shown includes the following steps:

[0093] S310, detecting radioactive sources.

[0094] Specifically, a radiation source detector is used to collect raw pulse signals in order to detect radiation sources.

[0095] At the detector's analog signal output, the signal can be processed in two paths: one path is used for current integration to measure the amount of charge Q per unit time (corresponding to the charge integration data mentioned above); the other path is used for pulse counting to measure the number of pulses N per unit time (corresponding to the pulse counting data mentioned above).

[0096] Optionally, to eliminate the influence of ambient background radiation, ambient background data can be collected in advance to deduct the contribution of ambient background radiation at the start of detection. For example, under conditions without a radioactive source, the acquisition time T can be set to ≥30 seconds to calculate the background pulse count per unit time. and background charge The formula is as follows:

[0097] , (T≥30s)

[0098] When starting the detection, it can be done through N N =NN B The net count is obtained through Q. N =QQ B The net charge is obtained.

[0099] Furthermore, it can be achieved through E A =Q N / N N The average energy of the incident gamma photons per unit time is obtained (corresponding to the target nuclide type factor in the above method embodiments).

[0100] S320, determine if a radioactive source exists.

[0101] For example, the presence of a radioactive source can be determined based on the real-time detected pulse count. If the radioactive source exists, proceed to step S330. If the radioactive source does not exist, proceed to step S370.

[0102] S330, obtain the currently measured average energy EA.

[0103] In an optional embodiment, when a radioactive source is detected, the amount of charge accumulated during the continuous detection time t (corresponding to the target time period mentioned above) can be utilized. And the cumulative number of pulses Calculate E A The specific formula is as follows:

[0104]

[0105] in, and This can be the data after deducting the contribution of background environmental radiation.

[0106] S340, perform database traversal and comparison, and calculate the matching degree between EA and the nuclide database.

[0107] Once a radioactive source is detected, the nuclide matching algorithm is activated, and the process automatically terminates when no radioactive source is detected, while retaining the detection record.

[0108] Specifically, it can detect E in real time A and nuclide E in the nuclide database ref The nuclides are matched for similarity, and the nuclide with the highest matching degree is selected first.

[0109] The matching degree can be calculated using the following formula:

[0110]

[0111] Where P is the matching degree. It can also represent the target nuclide type factor. It can also represent the preset nuclide type factor in the preset relation table. express The uncertainty.

[0112] S350 outputs the nuclide with the highest matching degree.

[0113] S360 identifies nuclides and records them in a database.

[0114] Once the nuclide is matched, the detection record can be entered into the database for subsequent data analysis or system learning.

[0115] S370, terminate matching.

[0116] Please refer to Figure 4 , Figure 4 The embodiment shown illustrates the process of establishing a nuclide database, corresponding to the process of obtaining the preset relationship table in steps 3.1-3.3 above. Figure 4 The process shown includes the following steps:

[0117] S410, experimentally measured commonly used nuclides, and obtained average energy measurement data of commonly used nuclides.

[0118] S420 uses a Monte Carlo simulation detector to measure the corresponding nuclide in the experiment.

[0119] S430 uses Monte Carlo simulation to simulate data from other nuclides.

[0120] S440, forming a nuclide database.

[0121] Specifically, the average energy information of commonly used nuclides measured in the radiation detector can be extracted experimentally first. Then, the detector is characterized by comparing and verifying experimental and simulation data to ensure the accuracy of the Monte Carlo simulation results. Next, Monte Carlo simulations are used to obtain the average energy of more nuclides measured in the radiation detector. Finally, these various nuclides and their corresponding average energy information form a nuclide database.

[0122] Understandable. Figure 4 For a more detailed explanation of each step of the process shown, please refer to the relevant explanations of steps 3.1-3.3 above.

[0123] Based on the above embodiments, it can be understood that:

[0124] The method of this application achieves rapid estimation of the average energy of a radioactive source by simultaneously acquiring pulse count data and charge integral data, thereby preliminarily identifying the nuclide type. Specifically, this application starts with measured data of common nuclides, extracting their average energy characteristics, i.e., reflecting the average deposition energy through the ratio of the total charge integral to the total pulse count; further, it combines Monte Carlo simulation methods to extend to more types of nuclides, constructing an "average energy – nuclide type" mapping database, thus achieving rapid and preliminary identification of radionuclides.

[0125] Specifically:

[0126] According to the principle of radiation detection, when a gamma detector detects gamma rays, the actual average energy of the gamma photons interacting with the detector's sensitive volume is correlated with the average energy deposited by these gamma photons within the detector's sensitive volume (a linear relationship exists over most of the energy range). In a gamma detector, the energy deposited by gamma photons within the detector's sensitive volume has a linear relationship primarily with the pulse signal amplitude and the pulse signal charge.

[0127] Therefore, the approach of this application for measuring average energy is to use the traditional pulse counting method to obtain the number N of gamma photons that interact with the detector's sensitive volume within a time period t. N Then, by integrating the current, we obtain the charge Q generated by the energy deposited by these gamma photons within the detector's sensitive volume during this time t. N (The pulse count data and charge integration data can be processed by signal amplification and background subtraction). Since the type of radiation source remains unchanged, Q... N Proportional to N N Therefore, EA=Q can be used. N / N N This is used to approximate the average energy of the incident gamma photon.

[0128] The average energy of incident gamma photons can serve as an important characteristic of nuclides, because different nuclides emit various gamma photons with different energies and emission rates, and the average energy of the gamma photons they emit is also different. Therefore, the average energy can be used as a preliminary and rapid criterion for screening nuclides.

[0129] Furthermore, this application applies to almost all spectral and non-spectral detectors. The detector can be any type of gas detector, scintillator detector, semiconductor detector, etc., and there are no limitations on this.

[0130] According to the above method embodiments, this application can achieve the following beneficial effects:

[0131] 1. The nuclide type determination method proposed in this application has an extremely fast response speed, capable of making a preliminary determination of the nuclide type almost simultaneously with the detection of a radioactive source, significantly improving the real-time response capabilities in scenarios such as customs, border security checks, and nuclear emergencies; 2. The nuclide type determination method proposed in this application has broad detector compatibility, and can be attempted using almost any type of radiation detector; 3. In many nuclear safety detection and nuclear emergency scenarios, the nuclide type determination method proposed in this application can significantly reduce reliance on expensive equipment, greatly reducing equipment costs, and achieving faster detection and screening results; 4. In high-traffic frontline security inspection scenarios such as customs, airports, and ports, traditional methods may lead to missed detections or misjudgments due to insufficient energy spectrum acquisition time. The nuclide type determination method proposed in this application can enhance the reliability and efficiency of nuclear safety detection.

[0132] In order to perform the corresponding steps in the above embodiments and various possible methods, this application also provides a data reading and processing module, which can be set in a data processor to control the radiation source detector and thus realize the above method embodiments.

[0133] The following describes one implementation method for a data reading and processing module. Please refer to [link / reference]. Figure 5 , Figure 5 A functional block diagram of a data reading and processing module 500 according to an embodiment of the present invention is shown. This data reading and processing module 500 can be used to implement the above-described... Figure 1 The method is shown. It should be noted that the data reading and processing module 500 provided in this embodiment has the same basic principle and technical effects as the embodiments described above. For the sake of brevity, any parts not mentioned in this embodiment can be referred to the corresponding content in the above embodiments. The data reading and processing module 500 may include: a transceiver unit 510 and a processing unit 520.

[0134] Optionally, the transceiver unit 510 and processing unit 520 described above can be stored in the memory of the data processor in the form of software or firmware, or embedded in the data reading and processing module 500 of the data processor provided by the present invention, and can be executed by the data reading and processing module 300. Meanwhile, the data, program code, etc., required to execute the above units can be stored in the memory.

[0135] It is understood that the transceiver unit 510 and the processing unit 520 can be used to support the data reading and processing module 500 in performing the relevant steps in the above method embodiments, and / or other processes used in the technology described herein, such as those described above. Figure 1 The method embodiments shown and the various method embodiments described above are not intended to limit the scope of the invention.

[0136] Based on the above method embodiments, this invention also provides a computer-readable storage medium storing a computer program, which, when run by a processor, executes the above method embodiments. Specifically, the storage medium can be a general-purpose storage medium, such as a removable disk or hard disk, and the computer program on the storage medium, when run, can execute the methods described in the above embodiments.

[0137] The above description is merely an embodiment of the present invention and is not intended to limit the scope of protection of the present invention. For those skilled in the art, the present invention can have various modifications and variations. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. A method for rapid identification of nuclide types, characterized in that, Includes the following steps: Use a radiation source detector to detect the target radiation source; When the radiation source detector detects the target radiation source, it acquires pulse count data and charge integration data collected by the radiation source detector within the target time period; wherein, the pulse count data is the number of radiation events detected by the radiation source detector per unit time, and the charge integration data is the amount of charge accumulated by the radiation source detector during the detection process per unit time. Based on the pulse count data and the charge integral data, a target nuclide type factor is determined; wherein, the target nuclide type factor is used to characterize the average energy of the radioactive source; The radionuclide type of the radioactive source is determined according to the target nuclide type factor and the preset relationship table; wherein, the preset relationship table includes the correspondence between multiple preset nuclide type factors and preset nuclide types; The target nuclide type factor is determined based on the ratio of the charge integral data and the pulse count data.

2. The rapid identification method for nuclide types according to claim 1, characterized in that, The step of determining the target nuclide type factor based on the pulse count data and the charge integral data includes: The target nuclide type factor is determined according to the following formula: ； in, This represents the target nuclide type factor. This represents the cumulative amount of charge continuously detected within the target time period. This indicates the cumulative number of pulses detected continuously within the target time period.

3. The rapid identification method for nuclide types according to claim 1, characterized in that, The pulse count data is the net count data after deducting the background pulse count, and the charge integral data is the net charge integral data after deducting the background charge integral.

4. The rapid identification method for nuclide types according to claim 1, characterized in that, The radionuclide type of the radioactive source is determined based on the target nuclide type factor and a preset relationship table, including the following steps: The target nuclide type factor and multiple preset nuclide type factors in the preset relationship table are matched for similarity to determine the preset nuclide type factor with the highest similarity. The radionuclide type of the radioactive source is determined based on the preset nuclide type factor corresponding to the preset nuclide type factor with the highest similarity.

5. The rapid identification method for nuclide types according to any one of claims 1-4, characterized in that, The preset relationship table is determined according to the following steps: Obtain standard average energy data from multiple standard sources with different nuclides; Monte Carlo simulations were performed based on multiple standard average energy data to obtain simulated average energy data of multiple simulated radioactive sources different from the standard sources in the radioactive source detector. The preset relationship table is determined based on multiple standard average energy data, multiple standard sources, multiple simulated average energy data, and multiple simulated radioactive sources.

6. The rapid identification method for nuclide types according to any one of claims 1-4, characterized in that, Before using a radiation source detector to detect the target radiation source, the method further includes the following steps: The radiation source detector was calibrated using standard sources with multiple different nuclides.

7. The rapid identification method for nuclide types according to any one of claims 1-4, characterized in that, The steps for acquiring pulse count data and charge integration data collected by the radiation source detector within a target time period include: At the signal output terminal of the radiation source detector, the signal output from the signal output terminal is copied into a first signal and a second signal; Based on the first signal, obtain the pulse count data collected by the radiation source detector within the target time period; Based on the second signal, the charge integral data collected by the radiation source detector within the target time period is obtained.

8. The rapid identification method for nuclide types according to any one of claims 1-4, characterized in that, The radiation source detector includes any one of the following detectors: gas detector, scintillator detector, semiconductor detector.

9. A rapid identification device for nuclide types, characterized in that, include: Radiation source detector and data processor; The data processor is used to control the radiation source detector to implement the method as described in any one of claims 1 to 8.

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