Signal processing method for a radioactivity detection device and radioactivity detection device

Abstract

The application provides a signal processing method for a radioactivity detection device and the radioactivity detection device. The signal processing method for the radioactivity detection device comprises the following steps: analyzing a collected nuclear pulse signal to obtain pulse amplitude information; performing spectrum stabilization according to the pulse amplitude information to obtain a stabilized spectrum; and determining a nuclide identification result and a dose rate calculation result based on the stabilized spectrum. The technical scheme of the embodiment of the application can determine the current environmental dose rate level, ensure that the radiation dose received by the staff is within the safety limit, thereby reducing the radiation risk and protecting the health and safety of the staff. In addition, the specific radioactive nuclide can be identified, thereby helping to determine the pollution source.

Description

Technical Field

[0001] This application relates to the field of nuclear radiation monitoring technology, and in particular to a signal processing method and a radioactive detection device for use in radioactive detection equipment. Background Technology

[0002] Personal dosimeters are primarily used for real-time monitoring of the personal dose of workers in radiation-controlled areas to ensure their radiation safety. The core component of existing personal dosimeters is a radiation detector, whose main measurement principle is based on the detector's response to gamma rays. The count level of this response reflects the ambient dose rate level. Therefore, existing personal dosimeters can only determine the current ambient dose rate level and cannot identify nuclides. Summary of the Invention

[0003] This application provides a signal processing method and a radioactivity detection device for use in radioactivity detection equipment, in order to solve the problems existing in related technologies. The technical solution is as follows:

[0004] In a first aspect, embodiments of this application provide a signal processing method for a radioactive detection device, comprising: analyzing a collected nuclear pulse signal to obtain pulse amplitude information; stabilizing the spectrum based on the pulse amplitude information to obtain a stable energy spectrum; and determining the nuclide identification result and dose rate calculation result based on the stable energy spectrum.

[0005] In one embodiment, stabilizing the spectrum based on pulse amplitude information to obtain a stable energy spectrum includes: acquiring the measured energy spectrum within a preset stabilization period based on pulse amplitude information; analyzing the measured energy spectrum to obtain the actual peak address of the reference source; and correcting the measured energy spectrum based on the reference peak address and the actual peak address of the reference source to obtain a stable energy spectrum.

[0006] In one embodiment, before obtaining the measured energy spectrum within a preset stable period based on pulse amplitude information, the method further includes: measuring the reference source within a preset measurement time to obtain a reference energy spectrum; analyzing the reference energy spectrum and searching for peaks to determine reference data of the characteristic peaks of the reference source; wherein the reference data includes the reference peak address.

[0007] In one embodiment, analyzing the measured energy spectrum to obtain the actual peak address of the reference source includes: determining a first measurement address interval based on the reference peak address; traversing multiple measurement addresses within the first measurement address interval in the measured energy spectrum; and determining the actual peak address of the reference source based on the multiple measurement addresses.

[0008] In one embodiment, the reference data further includes energy resolution; determining the actual peak location of the reference source based on multiple measurement locations includes: determining a second measurement location interval corresponding to each measurement location based on energy resolution; calculating the total peak count within each second measurement location interval; and determining the measurement location corresponding to the maximum total peak count as the actual peak location of the reference source.

[0009] In one implementation, determining the nuclide identification result based on the stable spectrum energy spectrum includes: analyzing the stable spectrum energy spectrum and searching for peaks to determine the characteristic peak energy; comparing the characteristic peak energy with data in the nuclide database to obtain the nuclide identification result.

[0010] In one implementation, determining the dose rate calculation result based on the stable spectral energy spectrum includes: performing energy spectrum dose conversion on the stable spectral energy spectrum to obtain the dose rate calculation result.

[0011] Secondly, embodiments of this application provide a radioactive detection device, comprising: a detector for acquiring nuclear pulse signals; a digital processor, the input of which is connected to the output of the detector, the digital processor being used to analyze the acquired nuclear pulse signals to obtain pulse amplitude information; and a controller, the input of which is connected to the output of the digital processor, the controller being used to stabilize the spectrum based on the pulse amplitude information to obtain a stable energy spectrum, and based on the stable energy spectrum, to determine the nuclide identification result and the dose rate calculation result.

[0012] Thirdly, embodiments of this application provide a signal processing apparatus, including a memory and a processor. The memory stores instructions, and the processor executes the instructions stored in the memory. When the processor executes the instructions stored in the memory, it causes the processor to perform the method described in any of the above embodiments.

[0013] Fourthly, embodiments of this application provide a computer-readable storage medium that stores a computer program, wherein when the computer program is run on a computer, the methods in any of the above-described embodiments are executed.

[0014] The advantages or beneficial effects of the above-mentioned technical solution include at least the following: Firstly, it can determine the current environmental dose rate level, ensuring that the radiation dose received by workers is within safe limits, thereby reducing radiation risks and protecting the health and safety of workers. Secondly, it can identify specific radionuclides, thus helping to determine the source of contamination.

[0015] The above overview is for illustrative purposes only and is not intended to be limiting in any way. In addition to the illustrative aspects, embodiments, and features described above, further aspects, embodiments, and features of this application will become readily apparent from the accompanying drawings and the following detailed description. Attached Figure Description

[0016] In the accompanying drawings, unless otherwise specified, the same reference numerals throughout the various drawings denote the same or similar parts or elements. These drawings are not necessarily drawn to scale. It should be understood that these drawings depict only some embodiments disclosed in this application and should not be construed as limiting the scope of this application.

[0017] Figure 1 A schematic flowchart of a signal processing method for a radioactive detection device according to an embodiment of this application is shown;

[0018] Figure 2 and Figure 3 An example diagram of the application of the reference energy spectrum according to an embodiment of this application is shown;

[0019] Figure 4 and Figure 5 The diagram illustrates an application example of measuring the energy spectrum according to an embodiment of this application.

[0020] Figure 6 A graph showing the relationship between the measured track address and the total peak count according to an embodiment of this application;

[0021] Figure 7 The diagram shows an application example of the stable energy spectrum according to an embodiment of this application;

[0022] Figure 8 A structural block diagram of a radioactive detection device according to an embodiment of this application is shown;

[0023] Figure 9 The diagram illustrates an application example of a radioactive detection device according to an embodiment of this application.

[0024] Figure 10 A structural block diagram of a signal processing apparatus according to an embodiment of this application is shown. Detailed Implementation

[0025] In the following description, only certain exemplary embodiments are briefly described. As those skilled in the art will recognize, the described embodiments can be modified in various ways without departing from the spirit or scope of this application. Therefore, the drawings and description are considered to be exemplary in nature and not restrictive.

[0026] In related technologies, personal dosimeters typically suffer from the following problems: First, the energy response error of the detector is relatively large. When using the detector for measurement, it is usually necessary to wrap the detector with a certain thickness of high atomic number material, such as lead or tin. This utilizes the principle that the shielding material attenuates low-energy rays more than high-energy rays to correct the detector's energy response curve. This process is difficult to handle, requires verification using a standard test field, and even after correction, the energy response error is difficult to achieve a high level. Second, the counting response curves of the detectors vary greatly from one detector to another, requiring calibration of each detector's counting response curve. Specifically, multiple calibration points within the range of the standard calibration field need to be selected for counting response calibration, followed by curve fitting calibration. This is costly and time-consuming. Third, personal dosimeters can only determine the current environmental dose rate level and cannot further identify nuclides.

[0027] The first aspect of this application provides a signal processing method for a radioactive detection device to address the problems existing in related technologies. The radioactive detection device may be a personal dosimeter, but is not limited thereto.

[0028] Figure 1 A schematic flowchart illustrating a signal processing method for a radioactive detection device according to an embodiment of this application is shown. Figure 1 As shown, the signal processing method may include:

[0029] Step S101: Analyze the acquired nuclear pulse signal to obtain pulse amplitude information.

[0030] For example, a radioactive detection device may include a detector for acquiring nuclear pulse signals. Specifically, the nuclear pulse signal may be generated by the interaction between nuclear particles and detector materials. Pulse amplitude information may include a pulse amplitude spectrum, which can be obtained by analyzing the acquired nuclear pulse signal using pulse amplitude analysis techniques.

[0031] Step S102: Stabilize the spectrum based on the pulse amplitude information to obtain the stable energy spectrum.

[0032] For example, before step S102, energy calibration can be performed first, that is, the pulse amplitude value can be converted into the corresponding energy value. After the energy calibration is completed, spectrum stabilization is then performed.

[0033] Step S103: Based on the stable energy spectrum, determine the nuclide identification results and dose rate calculation results.

[0034] In step S103, the nuclide identification result can be determined first based on the stable spectrum energy spectrum, and then the dose rate calculation result can be determined based on the stable spectrum energy spectrum; or the dose rate calculation result can be determined first based on the stable spectrum energy spectrum, and then the nuclide identification result can be determined based on the stable spectrum energy spectrum; or the nuclide identification result and the dose rate calculation result can be determined simultaneously based on the stable spectrum energy spectrum. This application does not limit this.

[0035] The specific dose rate, i.e., the radiation dose received per unit time, can be determined through dose rate calculation, usually expressed in millisieverts per hour (mSv / h) or microsieverts per hour (μSv / h). The type of nuclide can be determined through nuclide identification.

[0036] According to the signal processing method for radioactive detection equipment in this application, by determining the nuclide identification result and dose rate calculation result based on the stable energy spectrum, on the one hand, the current environmental dose rate level can be determined, ensuring that the radiation dose received by staff is within safe limits, thereby reducing radiation risk and protecting the health and safety of staff. On the other hand, specific radionuclides can be identified, thus helping to determine the source of contamination.

[0037] In one embodiment, step S102, stabilizing the spectrum based on the pulse amplitude information to obtain a stable spectrum energy spectrum may include: obtaining the measured energy spectrum within a preset stabilization period based on the pulse amplitude information; analyzing the measured energy spectrum to obtain the actual peak position address of the reference source; and correcting the measured energy spectrum based on the reference peak position address and the actual peak position address of the reference source to obtain a stable spectrum energy spectrum.

[0038] For example, the reference source for a radioactive detection device can be a naturally occurring radionuclide. 40 K. After power-on self-test, the radioactive detection equipment enters the automatic spectrum stabilization mode during the power-on phase. At this time, the above steps can be performed, namely, acquiring the measured energy spectrum within the preset stabilization period based on pulse amplitude information; analyzing the measured energy spectrum to obtain the actual peak position address of the reference source; and correcting the measured energy spectrum based on the reference peak position address and the actual peak position address of the reference source to obtain the stabilized energy spectrum.

[0039] For example, a preset stabilization period of 10 minutes is used as an example. The energy spectrum is obtained immediately after the radioactivity detection equipment is powered on. The measured energy spectrum within the preset stabilization period is the cumulative energy spectrum after 10 minutes of operation. The reference peak address A0 of the reference source can be predetermined. After obtaining the actual peak address A1 of the reference source, the measured energy spectrum can be corrected, with the corrected energy gain A2 = A0 / A1. After obtaining the stabilized energy spectrum, automatic stabilization during the power-on phase is completed. During the use of the radioactivity detection equipment, when the equipment is in a background environment, stabilization can be performed in real time.

[0040] It should be noted that, although the reference source is... 40 The above content is illustrated by K and a preset spectral stabilization period of 10 minutes, but those skilled in the art will understand that this application is not limited thereto.

[0041] In this embodiment, the measured energy spectrum can be corrected based on the reference peak address and the actual peak address of the reference source to obtain a stable energy spectrum. This can eliminate deviations caused by environmental factors or equipment errors, thereby improving the accuracy of nuclide identification results and dose rate calculation results.

[0042] In one embodiment, before obtaining the measured energy spectrum within a preset stable spectral period based on pulse amplitude information, the signal processing method may further include: measuring the reference source within a preset measurement time to obtain a reference energy spectrum; analyzing the reference energy spectrum and searching for peaks to determine reference data of the characteristic peaks of the reference source; wherein the reference data includes the reference peak address.

[0043] Figure 2 and Figure 3 An example diagram illustrating the application of a reference energy spectrum according to an embodiment of this application is shown. Exemplarily, in conjunction with... Figure 2 and Figure 3 With reference source as 40 Let's take K as an example. Since the natural background includes a reference source... 40 Therefore, the natural background spectrum can be continuously measured within a preset measurement time (e.g., 60 minutes) to obtain the reference energy spectrum. Peak searching of the reference energy spectrum can then yield the reference source. 40 K characteristic peak (reference) Figure 2 The cyan part and Figure 3 (The green part in the image). For example, the reference source. 40 The energy value of the K characteristic peak is 1460 keV, which is the reference energy. 40 The energy of the gamma rays released during K decay. (Regarding the reference source) 40 By analyzing and calculating the K characteristic peak, the reference source can be obtained. 40 Reference data for the K characteristic peak. Reference data may include reference peak address, reference full width at half maximum (FWHM), and energy resolution. For example, in... Figure 2 and Figure 3 In the example, the reference source 40 The reference full width at half maximum (FWHM) A3 of the K characteristic peak is 97.37, and the reference source... 40 The reference peak address A0 for the K characteristic peak is 1880.81. The energy resolution η = A3 / A0 = 5.17%.

[0044] In this embodiment, by analyzing and locating the peaks of the reference energy spectrum, the reference peak address of the characteristic peak of the reference source can be determined. The reference peak address can then be used as a benchmark to compare with the actual peak address, thereby effectively correcting the measured energy spectrum and obtaining an accurate stable energy spectrum.

[0045] In one implementation, analyzing the measured energy spectrum to obtain the actual peak address of the reference source may include: determining a first measurement address interval based on the reference peak address; traversing multiple measurement addresses within the first measurement address interval in the measured energy spectrum; and determining the actual peak address of the reference source based on the multiple measurement addresses.

[0046] Figure 4 and Figure 5 The diagram illustrates an application example of the measured energy spectrum according to an embodiment of this application. For example, a preset stabilization period of 10 minutes is used as an example. The measured energy spectrum within the preset stabilization period is the cumulative energy spectrum 10 minutes after the radioactivity detection device is turned on (e.g., ...). Figure 4 and Figure 5 (As shown). The first measurement address interval can be determined based on the reference peak address A0. For example, the first measurement address interval can be [A0×0.8, A0×1.2]. Figure 2 and Figure 3 In the example, the reference peak address A0 is 1880.81, then the first measurement address interval is [1504, 2257] (refer to...). Figure 5 (The cyan part in the image). By traversing multiple measurement addresses A4 within the first measurement address interval [1504, 2257], the actual peak address A1 of the reference source can be determined.

[0047] In this embodiment, the actual peak address of the reference source can be determined, thereby determining the offset of the actual peak address relative to the reference peak address. Based on the offset of the actual peak address relative to the reference peak address, the measured energy spectrum can be corrected to obtain an accurate stable energy spectrum.

[0048] In one implementation, the reference data may further include energy resolution. Determining the actual peak location of the reference source based on multiple measurement locations may include: determining a second measurement location interval corresponding to each measurement location based on the energy resolution; calculating the total peak count within each second measurement location interval; and determining the measurement location corresponding to the maximum total peak count as the actual peak location of the reference source.

[0049] Figure 6 A graph showing the relationship between the measured track address and the total peak count according to an embodiment of this application; Figure 7 An example diagram illustrating the application of a stable energy spectrum according to an embodiment of this application is shown. Exemplarily, refer to... Figure 5 and Figure 6After traversing multiple measurement addresses A4 within the first measurement address interval [1504, 2257], the second measurement address interval corresponding to each measurement address A4 can be determined based on the energy resolution η. Each measurement address A4 corresponds to one second measurement address interval, which can be [A4 - A4 × η, A4 + A4 × η]. After calculating the total peak count within each second measurement address interval, the measurement address corresponding to the largest total peak count (i.e., the largest peak count) is determined as the actual peak position address A1 of the reference source. For example, in... Figure 6 In the example, the total count of the maximum peak region is 259, and the measurement address corresponding to the total count of the maximum peak region is 1650. Therefore, the actual peak address A1 of the reference source is 1650. Based on the reference peak address A0 and the actual peak address A1 of the reference source, the measured energy spectrum can be corrected. The corrected energy spectrum gain A2 = A0 / A1 = 1880.81 / 1650 = 1.14. The stable energy spectrum obtained after correction is as follows: Figure 7 As shown.

[0050] In this way, by determining the measurement address corresponding to the total count of the maximum peak region as the actual peak address of the reference source, the actual peak address of the reference source can be effectively determined. This allows us to determine the offset of the actual peak address relative to the reference peak address, and then correct the measured energy spectrum based on the offset of the actual peak address relative to the reference peak address to obtain an accurate stable energy spectrum.

[0051] In one implementation, step S103, determining the nuclide identification result based on the stable energy spectrum, may include: analyzing the stable energy spectrum and searching for peaks to determine the characteristic peak energy; comparing the characteristic peak energy with data in the nuclide database to obtain the nuclide identification result. This allows for accurate identification of specific radionuclides, thereby helping to determine pollution sources and improve environmental safety.

[0052] In one embodiment, step S103, determining the dose rate calculation result based on the stable energy spectrum, may include: performing energy spectrum dose conversion on the stable energy spectrum to obtain the dose rate calculation result. Therefore, by performing energy spectrum dose conversion on the stable energy spectrum, for radioactive detection equipment of the same specifications, the energy spectrum data can be directly used for dose rate calculation without the need for individual energy response correction, reducing the complexity and potential errors in the measurement process. Moreover, for radioactive detection equipment of the same specifications, the responses and performance between different radioactive detection equipment are basically consistent. Using energy spectrum dose conversion results in high dose rate calculation accuracy, eliminates the need for individual calibration, and effectively saves time and labor costs.

[0053] In one embodiment, the signal processing method for a radiation detection device may further include: generating an alarm message when the dose rate calculation result indicates that the ambient dose rate is greater than a preset radiation threshold. Exemplarily, the radiation detection device may include an alarm. For example, generating an alarm message when the ambient dose rate is greater than the preset radiation threshold causes the alarm to emit an alarm signal, thereby preventing personnel from accidentally entering the radiation area. Optionally, the alarm may include an indicator light, a buzzer, etc., but is not limited thereto.

[0054] A second aspect of this application provides a radioactive detection device. Figure 8 A structural block diagram of a radioactive detection device according to an embodiment of this application is shown. Figure 8 As shown, the radioactive detection device includes a detector 810, a digital processor 820, and a controller 830. Specifically, the detector 810 is used to acquire nuclear pulse signals. The input terminal of the digital processor 820 is connected to the output terminal of the detector 810, and the digital processor 820 is used to analyze the acquired nuclear pulse signals to obtain pulse amplitude information. The input terminal of the controller 830 is connected to the output terminal of the digital processor 820, and the controller 830 is used to stabilize the spectrum based on the pulse amplitude information to obtain the stabilized energy spectrum, and based on the stabilized energy spectrum, determine the nuclide identification result and the dose rate calculation result.

[0055] For example, the digital processor 820 can be a Field-Programmable Gate Array (FPGA), which may include logic modules, flip-flops, programmable interconnect networks, digital signal processing modules, and storage modules. The logic modules can be used to classify and process received digital electrical signals, and perform various logical operations, such as determining the amplitude and timing characteristics of the digital electrical signals. The flip-flops can store processed pulse amplitude information, ensuring that the energy spectrum data is transmitted to the controller 830 at the appropriate clock cycle. The programmable interconnect network allows users to flexibly adjust the processing path of the digital electrical signals, enabling data to be processed according to specific timing and order to meet different experimental needs. The digital signal processing module can be used for high-precision signal analysis, such as advanced processing of digital electrical signals including filtering, integration, and differentiation, helping to extract key information such as pulse amplitude more accurately. The storage module can be used to store pulse data, such as intermediate processing results and pulse counts, and can also be used to buffer acquired data for subsequent processing or transmission. The controller 830 can be an embedded microprocessor, but is not limited to this.

[0056] The functions of the detector 810, digital processor 820, and controller 830 in the device of this application embodiment can be found in the corresponding descriptions in the above methods, and will not be repeated here.

[0057] Figure 9The diagram illustrates an application example of a radioactive detection device according to an embodiment of this application. In one example, such as... Figure 9 As shown, the radioactive detection device may also include a preamplifier 840, an analog-to-digital converter 850, a display screen 860, and an alarm 870. The detector 810 may include a scintillator crystal and a silicon photomultiplier tube. The scintillator crystal is used to detect nuclear pulse signals and emit light, while the silicon photomultiplier tube is connected to the scintillator crystal and is used to convert scintillating photons into analog electrical signals. For example, the scintillator crystal can be a CsI crystal, NaI crystal, etc. By incorporating a scintillator crystal and a silicon photomultiplier tube connected to it, the silicon photomultiplier tube has advantages such as small size, resistance to shock and vibration, and insensitivity to magnetic fields, thereby allowing the detector 810 to be smaller, more accurate, and more stable.

[0058] The input of preamplifier 840 is connected to the output of silicon photomultiplier tube, and preamplifier 840 is used to amplify analog electrical signals. The input of analog-to-digital converter 850 is connected to the output of preamplifier 840, and analog-to-digital converter 850 is used to convert analog electrical signals into digital electrical signals. The input of digital processor 820 is connected to the output of analog-to-digital converter 850. Display screen 860 and alarm 870 are both connected to controller 830. After determining the nuclide identification result and dose rate calculation result based on the stable energy spectrum, controller 830 can display the nuclide identification result and dose rate calculation result on display screen 860. When the ambient dose rate is greater than a preset radiation threshold, controller 830 generates alarm information and controls alarm 870 to issue an alarm signal, thereby preventing personnel from accidentally entering the radiation area. Furthermore, the radioactivity detection equipment may also include high-voltage circuits and power supply batteries, etc.

[0059] Figure 10 A structural block diagram of a signal processing apparatus according to an embodiment of the present invention is shown. Figure 10 As shown, the signal processing apparatus includes a memory 1010 and a processor 1020. The memory 1010 stores a computer program that can run on the processor 1020. When the processor 1020 executes the computer program, it implements the signal processing method for a radioactive detection device described in the above embodiments. The number of memories 1010 and processors 1020 can be one or more.

[0060] The signal processing device also includes:

[0061] The communication interface 1030 is used to communicate with external devices and perform data exchange and transmission.

[0062] If the memory 1010, processor 1020, and communication interface 1030 are implemented independently, they can be interconnected via a bus to communicate with each other. This bus can be an Industry Standard Architecture (ISA) bus, a Peripheral Component Interconnect (PCI) bus, or an Extended Industry Standard Architecture (EISA) bus, etc. This bus can be divided into address bus, data bus, control bus, etc. For ease of representation, Figure 10 The bus is represented by a single thick line, but this does not mean that there is only one bus or one type of bus.

[0063] Optionally, in a specific implementation, if the memory 1010, processor 1020 and communication interface 1030 are integrated on a single chip, then the memory 1010, processor 1020 and communication interface 1030 can communicate with each other through an internal interface.

[0064] This invention provides a computer-readable storage medium storing a computer program that, when executed by a processor, implements the method provided in this application.

[0065] This application also provides a chip, which includes a processor for calling and executing instructions stored in a memory, causing a communication device on which the chip is installed to perform the method provided in this application.

[0066] This application also provides a chip, including: an input interface, an output interface, a processor, and a memory. The input interface, output interface, processor, and memory are connected through an internal connection path. The processor is used to execute code in the memory. When the code is executed, the processor is used to execute the method provided in the application embodiment.

[0067] It should be understood that the aforementioned processor can be a Central Processing Unit (CPU), or other general-purpose processors, digital signal processors (DSPs), application-specific integrated circuits (ASICs), field-programmable gate arrays (FPGAs), or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. General-purpose processors can be microprocessors or any conventional processor. It is worth noting that the processor can be a processor supporting the Advanced Reduced Instruction Set Computing (RISC) machine (ARM) architecture.

[0068] Further, optionally, the aforementioned memory may include read-only memory and random access memory, and may also include non-volatile random access memory. The memory may be volatile or non-volatile, or may include both. Non-volatile memory may include read-only memory (ROM), programmable read-only memory (PROM), erasable programmable read-only memory (EPROM), electrically erasable programmable read-only memory (EEPROM), or flash memory. Volatile memory may include random access memory (RAM), which serves as an external cache. Many forms of RAM are available by way of example, but not limitation. Examples include static random access memory (SRAM), dynamic random access memory (DRAM), synchronous dynamic random access memory (SDRAM), double data rate synchronous dynamic random access memory (DDR SDRAM), enhanced synchronous dynamic random access memory (ESDRAM), synchronous linked dynamic random access memory (SLDRAM), and direct rambus RAM (DR RAM).

[0069] In the above embodiments, implementation can be achieved, in whole or in part, through software, hardware, firmware, or any combination thereof. When implemented in software, it can be implemented, in whole or in part, as a computer program product. A computer program product includes one or more computer instructions. When the computer program instructions are loaded and executed on a computer, all or part of the flow or function according to this application is generated. The computer can be a general-purpose computer, a special-purpose computer, a computer network, or other programmable device. The computer instructions can be stored in a computer-readable storage medium or transferred from one computer-readable storage medium to another.

[0070] In the description of this specification, the references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of this application. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Moreover, without contradiction, those skilled in the art can combine and integrate the different embodiments or examples described in this specification, as well as the features of those different embodiments or examples.

[0071] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this application, "a plurality of" means two or more, unless otherwise explicitly specified.

[0072] Any process or method description in the flowchart or otherwise herein can be understood as representing a module, segment, or portion of code comprising one or more executable instructions for implementing a particular logical function or process. Furthermore, the scope of the preferred embodiments of this application includes additional implementations in which functions may be performed not in the order shown or discussed, including substantially simultaneously or in reverse order depending on the functionality involved.

[0073] The logic and / or steps represented in the flowchart or otherwise described herein, for example, can be considered as a sequenced list of executable instructions for implementing logical functions, and can be embodied in any computer-readable medium for use by, or in conjunction with, an instruction execution system, apparatus or device (such as a computer-based system, a processor-included system or other system that can fetch and execute instructions from, an instruction execution system, apparatus or device).

[0074] It should be understood that various parts of this application can be implemented using hardware, software, firmware, or a combination thereof. In the above embodiments, multiple steps or methods can be implemented using software or firmware stored in memory and executed by a suitable instruction execution system. All or part of the steps of the methods in the above embodiments can be implemented by a program instructing related hardware, the program being stored in a computer-readable storage medium, which, when executed, includes one or a combination of the steps of the method embodiments.

[0075] Furthermore, the functional units in the various embodiments of this application can be integrated into a processing module, or each unit can exist physically separately, or two or more units can be integrated into a module. The integrated module can be implemented in hardware or as a software functional module. If the integrated module is implemented as a software functional module and sold or used as an independent product, it can also be stored in a computer-readable storage medium. This storage medium can be a read-only memory, a disk, or an optical disk, etc.

[0076] The above are merely specific embodiments of this application, but the scope of protection of this application is not limited thereto. Any person skilled in the art can easily conceive of various variations or substitutions within the technical scope disclosed in this application, and these should all be included within the scope of protection of this application. Therefore, the scope of protection of this application should be determined by the scope of the claims.

Claims

1. A signal processing method for a radioactivity detection device, characterized in that, The method comprises: analyzing the collected nuclear pulse signals to obtain pulse amplitude information; measuring a reference source within a preset measurement time to obtain a reference energy spectrum, analyzing the reference energy spectrum and searching for peaks to determine reference data of a reference source characteristic peak, wherein the reference data comprises a reference peak channel address and an energy resolution, and the energy resolution is a ratio of a reference full width at half maximum to the reference peak channel address; based on the pulse amplitude information, obtaining a measurement energy spectrum within a preset stable spectrum period, determining a first measurement channel address interval according to the reference peak channel address, traversing a plurality of measurement channel addresses within the first measurement channel address interval in the measurement energy spectrum, determining a second measurement channel address interval corresponding to each measurement channel address based on the energy resolution, calculating a peak region total count within each second measurement channel address interval, and determining a measurement channel address corresponding to a maximum peak region total count as an actual peak channel address of the reference source; determining an energy spectrum gain based on the reference peak channel address of the reference source and the actual peak channel address, correcting the measurement energy spectrum according to the energy spectrum gain to obtain the stable spectrum energy spectrum; and based on the stable spectrum energy spectrum, determining a nuclide identification result and a dose rate calculation result. Based on the stable spectrum energy spectrum, determining a nuclide identification result comprises:

2. The method of claim 1, wherein, analyzing the stable spectrum energy spectrum and searching for peaks to determine a characteristic peak energy; comparing the characteristic peak energy with data in a nuclide database to obtain a nuclide identification result. Based on the stable spectrum energy spectrum, determining a dose rate calculation result comprises:

3. The method according to claim 1 or 2, characterized in that, performing energy spectrum dose conversion on the stable spectrum energy spectrum to obtain a dose rate calculation result. The method comprises:

4. A radiation detection device for use in the method of any one of claims 1-3, characterized in that, a detector for collecting nuclear pulse signals; a digital processor, an input end of the digital processor being connected to an output end of the detector, the digital processor being configured to analyze the collected nuclear pulse signals to obtain pulse amplitude information; a controller, an input end of the controller being connected to an output end of the digital processor, the controller being configured to perform stable spectrum according to the pulse amplitude information to obtain a stable spectrum energy spectrum, and determine a nuclide identification result and a dose rate calculation result based on the stable spectrum energy spectrum. The method comprises:

5. A signal processing device, characterized by a processor and a memory, the memory storing instructions, the instructions being loaded and executed by the processor to implement the method according to any one of claims 1-3.

6. A computer readable storage medium, the computer readable storage medium storing a computer program, the computer program being executed by a processor to implement the method according to any one of claims 1-3. ​

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