Signal processing method for radioactivity detection equipment and radioactivity detection equipment

Abstract

The invention provides a signal processing method for radioactivity detection equipment and the radioactivity detection equipment, and the signal processing method for the radioactivity detection equipment comprises the steps: analyzing a collected nuclear pulse signal, and obtaining pulse amplitude information; performing spectrum stabilization according to the pulse amplitude information to obtain a spectrum-stabilized energy spectrum; and determining a nuclide identification result and a dose rate calculation result based on the spectrum-stabilized energy spectrum. According to the technical scheme, on one hand, the current environment dose rate level can be determined, it is ensured that the radiation dose received by workers is within the safety limit value, and therefore the radiation risk can be reduced, and the health and safety of the workers are guaranteed; and on the other hand, specific radionuclides can be identified, so that the pollution source can be determined.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear radiation monitoring, and in particular to a signal processing method for a radioactive detection device and a radioactive detection device. Background Art

[0002] Personal dosimeters are mainly used for real-time monitoring of personal doses of workers in radiation control areas to ensure radiation safety of workers. The core component of existing personal dosimeters is the radiation detector, and its main measurement principle is that the radiation detector responds to gamma rays and reflects the current environmental dose rate level of the device through the count level of the response. Therefore, existing personal dosimeters can only determine the current environmental dose rate level, but cannot identify nuclides. Summary of the invention

[0003] The embodiment of the present application provides a signal processing method for a radioactive detection device and a radioactive detection device to solve the problems existing in the related art. The technical solution is as follows:

[0004] In a first aspect, an embodiment of the present application provides a signal processing method for radioactive detection equipment, comprising: analyzing the collected nuclear pulse signal to obtain pulse amplitude information; performing spectrum stabilization according to the pulse amplitude information to obtain a stabilized spectrum energy spectrum; and determining nuclide identification results and dose rate calculation results based on the stabilized spectrum energy spectrum.

[0005] In one embodiment, spectrum stabilization is performed according to pulse amplitude information to obtain a stabilized spectrum energy spectrum, including: obtaining a measured energy spectrum within a preset spectrum stabilization period based on the pulse amplitude information; analyzing the measured energy spectrum to obtain an actual peak position channel address of a reference source; and correcting the measured energy spectrum based on a reference peak position channel address and an actual peak position channel address of the reference source to obtain a stabilized spectrum energy spectrum.

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

[0007] In one embodiment, the measurement energy spectrum is analyzed to obtain the actual peak address of the reference source, including: determining a first measurement address interval based on the reference peak address; traversing multiple measurement addresses in the first measurement address interval in the measurement 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 also includes energy resolution; determining the actual peak position channel address of the reference source based on multiple measurement channel addresses, including: determining the second measurement channel address interval corresponding to each measurement channel address based on the energy resolution; calculating the total peak area count within each second measurement channel address interval; and determining the measurement channel address corresponding to the maximum peak area total count as the actual peak position channel address of the reference source.

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

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

[0011] In the second aspect, an embodiment of the present application provides a radioactive detection device, including: a detector for collecting nuclear pulse signals; a digital processor, the input end of the digital processor is connected to the output end of the detector, and the digital processor is used to analyze the collected nuclear pulse signals to obtain pulse amplitude information; a controller, the input end of the controller is connected to the output end of the digital processor, and the controller is used to stabilize the spectrum according to the pulse amplitude information to obtain a stabilized spectrum energy spectrum, and determine the nuclide identification result and the dose rate calculation result based on the stabilized spectrum energy spectrum.

[0012] In a third aspect, an embodiment of the present application provides a signal processing device, comprising: a memory and a processor. The memory is used to store instructions, and the processor is used to execute the instructions stored in the memory, and when the processor executes the instructions stored in the memory, the processor executes the method in any one of the above-mentioned embodiments.

[0013] In a fourth aspect, an embodiment of the present application provides a computer-readable storage medium, which stores a computer program. When the computer program runs on a computer, the method in any one of the above-mentioned embodiments is executed.

[0014] The advantages or beneficial effects of the above technical solution include at least: on the one hand, the current environmental dose rate level can be determined to ensure that the radiation dose received by the workers is within the safe limit, thereby reducing the radiation risk and ensuring the health and safety of the workers. On the other hand, specific radionuclides can be identified, which helps to determine the source of contamination.

[0015] The above summary 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 the present application will be readily apparent by reference to the accompanying drawings and the following detailed description. BRIEF DESCRIPTION OF THE DRAWINGS

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

[0017] Figure 1 A schematic flow chart showing a signal processing method for a radioactive detection device according to an embodiment of the present application;

[0018] Figure 2 and Figure 3 An example diagram showing an application of a reference energy spectrum according to an embodiment of the present application;

[0019] Figure 4 and Figure 5 An example diagram showing an application of measuring energy spectrum according to an embodiment of the present application;

[0020] Figure 6 A curve relationship diagram showing the measurement track address and the total count of the peak area according to an embodiment of the present application;

[0021] Figure 7 An example diagram showing the application of a spectrum stabilization energy spectrum according to an embodiment of the present application;

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

[0023] Fig. 9 An example diagram showing an application of a radioactive detection device according to an embodiment of the present application;

[0024] Fig.10 A structural block diagram of a signal processing device according to an embodiment of the present application is shown. DETAILED DESCRIPTION

[0025] In the following, only some exemplary embodiments are briefly described. As those skilled in the art will appreciate, the described embodiments may be modified in various ways without departing from the spirit or scope of the present application. Therefore, the drawings and descriptions are considered to be exemplary and non-restrictive in nature.

[0026] In the related art, personal dosimeters usually have the following problems: First, the energy response error of the detector is large. When using the detector for measurement, it is usually necessary to wrap a certain thickness of high atomic number material, such as lead, tin, etc., on the outside of the detector, and use the principle that the shielding material attenuates low-energy rays more than high-energy rays to correct the energy response curve of the detector. This process is difficult to handle and needs to be verified using a standard test field, and the corrected energy response error is also difficult to reach a high level. Second, the counting response curve of the detector has large individual differences, and the counting response curve of each detector needs to be calibrated. Specifically, it is necessary to select multiple scale points within the range of the standard calibration field for counting response calibration, and then fit the curve to scale, which has a high investment cost and takes a lot of time. Third, the personal dosimeter can only determine the current environmental dose rate level, but cannot further identify the nuclide.

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

[0028] Figure 1 FIG. 1 is a flow chart showing a signal processing method for a radioactive detection device according to an embodiment of the present application. Figure 1 As shown, the signal processing method may include:

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

[0030] Exemplarily, the radioactive detection device may include a detector for collecting nuclear pulse signals. Specifically, the nuclear pulse signal may be generated by the interaction between nuclear particles and the detector material. The pulse amplitude information may include a pulse amplitude spectrum, which may be obtained by analyzing the collected nuclear pulse signal using a pulse amplitude analysis technique.

[0031] Step S102: performing spectrum stabilization according to the pulse amplitude information to obtain a spectrum stabilization energy spectrum.

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

[0033] Step S103: Determine the nuclide identification result and the dose rate calculation result based on the stabilized spectrum.

[0034] In step S103, the nuclide identification result can be determined based on the stable spectrum energy spectrum first, and then the dose rate calculation result can be determined based on the stable spectrum energy spectrum; the dose rate calculation result can be determined based on the stable spectrum energy spectrum first, and then the nuclide identification result can be determined based on the stable spectrum energy spectrum; or the nuclide identification result can be determined based on the stable spectrum energy spectrum and the dose rate calculation result can be determined based on the stable spectrum energy spectrum at the same time, which is not limited in the present application.

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

[0036] According to the signal processing method for radioactive detection equipment of the embodiment of the present application, by determining the nuclide identification result and the dose rate calculation result based on the stable spectrum energy spectrum, on the one hand, the current environmental dose rate level can be determined to ensure that the radiation dose received by the staff is within the safety limit, thereby reducing the radiation risk and ensuring the health and safety of the staff. On the other hand, specific radioactive nuclides can be identified, which helps to determine the source of contamination.

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

[0038] Exemplarily, the reference source of the radioactive detection device can be a natural radionuclide 40 K. After the power-on self-test, the radioactive detection equipment enters the automatic spectrum stabilization mode of the power-on stage. At this time, the above steps can be performed, that is, based on the pulse amplitude information, the measured energy spectrum within the preset spectrum stabilization period is obtained; the measured energy spectrum is analyzed to obtain the actual peak position channel address of the reference source; based on the reference peak position channel address and the actual peak position channel address of the reference source, the measured energy spectrum is corrected to obtain the stabilized spectrum energy spectrum.

[0039] Exemplarily, the preset stabilization period is 10 minutes as an example. The energy spectrum can be obtained after the radioactive detection equipment is turned on, and the measured energy spectrum within the preset stabilization period is the cumulative energy spectrum 10 minutes after the radioactive detection equipment is turned on. 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, and the corrected energy spectrum gain A2=A0 / A1. After obtaining the stable spectrum energy spectrum, the automatic stabilization of the power-on stage is completed. During the use of the radioactive detection equipment, when the radioactive detection equipment is in a background environment, the spectrum can be stabilized in real time.

[0040] It should be noted that although the reference source is 40 The above content is introduced as an example in which K and the preset spectrum stabilization period are 10 minutes, but those skilled in the art will appreciate that the present application is not limited thereto.

[0041] In this embodiment, the measured energy spectrum can be corrected based on the reference peak position channel address and the actual peak position channel address of the reference source to obtain a stable spectrum energy spectrum, which 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 stabilization period based on the pulse amplitude information, the signal processing method may further include: measuring a reference source within a preset measurement time to obtain a reference energy spectrum; analyzing and peak searching the reference energy spectrum to determine reference data of a characteristic peak of the reference source; wherein the reference data includes a reference peak position address.

[0043] Figure 2 and Figure 3 FIG. 1 shows an example diagram of the application of the reference energy spectrum according to an embodiment of the present application. Figure 2 and Figure 3 , with the reference source as 40 K is used as an example. Since the natural background includes the reference source 40 K, so the natural background spectrum can be continuously measured within the preset measurement time (such as 60 minutes) to obtain the reference energy spectrum. Peak search for the reference energy spectrum can obtain the reference source 40 K characteristic peak (refer to Figure 2 The cyan part and Figure 3 For example, refer to the source 40 The energy value of the K characteristic peak is 1460keV, which is the reference source 40 The energy of the gamma rays released during K decay. 40 K characteristic peaks can be analyzed and calculated to obtain the reference source 40 Reference data of K characteristic peak. Reference data may include reference peak position, reference half-height width and energy resolution. Figure 2 and Figure 3 In the example, the reference source 40 The reference half-height width A3 of the K characteristic peak is 97.37, and the reference source 40 The reference peak address A0 of the K characteristic peak is 1880.81. The energy resolution η = A3 / A0 = 5.17%.

[0044] In this embodiment, by analyzing and searching for peaks in the reference energy spectrum, the reference peak position channel address of the characteristic peak of the reference source can be determined, so that the reference peak position channel address can be used as a benchmark and compared with the actual peak position channel address, thereby effectively correcting the measured energy spectrum and obtaining an accurate stable spectrum energy spectrum.

[0045] In one embodiment, 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 following is an example diagram of an application of measuring energy spectrum according to an embodiment of the present application. For example, the preset spectrum stabilization period is 10 minutes. The measured energy spectrum within the preset spectrum stabilization period is the accumulated energy spectrum after the radioactive detection device is turned on for 10 minutes (e.g. Figure 4 and Figure 5 The first measurement track address interval can be determined based on the reference peak track address A0. For example, the first measurement track address interval can be [A0×0.8, A0×1.2]. Figure 2 and Figure 3 In the example, the reference peak channel address A0 is 1880.81, so the first measurement channel address interval is [1504,2257] (refer to Figure 5 By traversing multiple measurement track addresses A4 in the first measurement track address interval [1504,2257], the actual peak track address A1 of the reference source can be determined.

[0047] In this embodiment, the actual peak position channel address of the reference source can be determined, so that the offset of the actual peak position channel address compared to the reference peak position channel address can be determined, and then the measured energy spectrum can be corrected based on the offset of the actual peak position channel address compared to the reference peak position channel address to obtain an accurate stable spectrum energy spectrum.

[0048] In one embodiment, the reference data may also include energy resolution. Determining the actual peak position channel address of the reference source according to multiple measurement channel addresses may include: determining the second measurement channel address interval corresponding to each measurement channel address based on the energy resolution; calculating the total peak area count within each second measurement channel address interval; and determining the measurement channel address corresponding to the maximum peak area total count as the actual peak position channel address of the reference source.

[0049] Figure 6 A curve relationship diagram showing the measurement track address and the total count of the peak area according to an embodiment of the present application; Figure 7 An example diagram of the application of the spectrum stabilization energy spectrum according to an embodiment of the present application is shown. Figure 5 and Figure 6, after traversing multiple measurement channel addresses A4 in the first measurement channel address interval [1504,2257], the second measurement channel address interval corresponding to each measurement channel address A4 can be determined based on the energy resolution η. Each measurement channel address A4 corresponds to a second measurement channel address interval, and the second measurement channel address interval corresponding to each measurement channel address A4 can be [A4-A4×η, A4+A4×η]. After calculating the total peak area counts in each second measurement channel address interval, the measurement channel address corresponding to the largest one of the multiple peak area total counts (i.e., the maximum peak area total count) is determined as the actual peak position channel address A1 of the reference source. For example, in Figure 6 In the example, the maximum peak area total count is 259, and the measurement channel address corresponding to the maximum peak area total count is 1650, so the actual peak channel address A1 of the reference source is 1650. Based on the reference peak channel address A0 and the actual peak channel 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 corrected stable spectrum energy spectrum is as follows Figure 7 shown.

[0050] In this way, by determining the measurement channel address corresponding to the maximum peak area total count as the actual peak channel address of the reference source, the actual peak channel address of the reference source can be effectively determined, so that the offset of the actual peak channel address compared to the reference peak channel address can be determined, and then the measured energy spectrum can be corrected based on the offset of the actual peak channel address compared to the reference peak channel address to obtain an accurate stable spectrum energy spectrum.

[0051] In one embodiment, in step S103, based on the stable spectrum energy spectrum, determining the nuclide identification result may include: analyzing the stable spectrum energy spectrum and searching for peaks to determine the characteristic peak energy; comparing the characteristic peak energy with the data in the nuclide database to obtain the nuclide identification result. In this way, specific radioactive nuclides can be accurately identified, thereby helping to determine the pollution source and improve environmental safety.

[0052] In one embodiment, in step S103, based on the stable spectrum energy spectrum, determining the dose rate calculation result may include: performing spectrum-dose conversion on the stable spectrum energy spectrum to obtain the dose rate calculation result. Thus, by performing spectrum-dose conversion on the stable spectrum energy spectrum, for radioactive detection equipment of the same specification, the energy spectrum data can be directly used for dose rate calculation without the need to perform energy response correction one by one, thereby reducing the complexity and potential errors in the measurement process. Moreover, for radioactive detection equipment of the same specification, the response and performance between different radioactive detection equipment are basically the same. By using the spectrum-dose conversion method, the dose rate calculation accuracy is high, and there is no need to perform calibration one by one, which effectively saves time and labor costs.

[0053] In one embodiment, the signal processing method for a radioactive detection device may further include: generating an alarm message when the dose rate calculation result is that the environmental dose rate is greater than a preset radiation threshold. Exemplarily, the radioactive detection device may include an alarm. For example, when the environmental dose rate is greater than a preset radiation threshold, an alarm message is generated so that the alarm sends an alarm signal, thereby preventing people from mistakenly 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 the present application provides a radioactive detection device. Figure 8 FIG. 2 shows a structural block diagram of a radioactive detection device according to an embodiment of the present application. 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 collect nuclear pulse signals. The input end of the digital processor 820 is connected to the output end of the detector 810, and the digital processor 820 is used to analyze the collected nuclear pulse signals to obtain pulse amplitude information. The input end of the controller 830 is connected to the output end of the digital processor 820, and the controller 830 is used to stabilize the spectrum according to the pulse amplitude information to obtain a stabilized spectrum energy spectrum, and determine the nuclide identification result and the dose rate calculation result based on the stabilized spectrum energy spectrum.

[0055] Exemplarily, the digital processor 820 may be a programmable logic device (Field-Programmable Gate Array, FPGA), which may include a logic module, a trigger, a programmable interconnect network, a digital signal processing module, and a storage module. Among them, the logic module may be used to classify and process the received digital electrical signals, and perform various logic operations, such as determining the amplitude and time characteristics of the digital electrical signals. The trigger may store the processed pulse amplitude information to ensure that the energy spectrum data is transmitted to the controller 830 at an appropriate clock cycle. The programmable interconnect network allows the user to flexibly adjust the processing path of the digital electrical signal so that the data can be processed in a specific timing and order to meet different experimental requirements. The digital signal processing module may be used for high-precision signal analysis, such as filtering, integration, differentiation, and other advanced processing of the digital electrical signal, to help more accurately extract key information such as pulse amplitude. The storage module may be used to store pulse data, such as intermediate processing results, pulse counts, etc., and may also be used to cache the collected data, waiting for subsequent processing or transmission. The controller 830 may be an embedded microprocessor, but is not limited thereto.

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

[0057] Fig. 9FIG. 1 shows an example of an application of a radioactive detection device according to an embodiment of the present application. In one example, Fig. 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, the silicon photomultiplier tube is connected to the scintillator crystal, and the silicon photomultiplier tube is used to convert scintillation photons into analog electrical signals. For example, the scintillator crystal may be a CsI crystal, a NaI crystal, etc. By providing a scintillator crystal and a silicon photomultiplier tube connected to the scintillator crystal, the silicon photomultiplier tube has the advantages of being small in size, resistant to shock and vibration, and insensitive to magnetic fields, so that the detector 810 can be smaller in size, higher in precision, and better in stability.

[0058] The input end of the preamplifier 840 is connected to the output end of the silicon photomultiplier tube, and the preamplifier 840 is used to amplify the analog electrical signal. The input end of the analog-to-digital converter 850 is connected to the output end of the preamplifier 840, and the analog-to-digital converter 850 is used to convert the analog electrical signal into a digital electrical signal. The input end of the digital processor 820 is connected to the output end of the analog-to-digital converter 850. The display screen 860 and the alarm 870 are both connected to the controller 830. After the controller 830 determines the nuclide identification result and the dose rate calculation result based on the stable spectrum energy spectrum, the nuclide identification result and the dose rate calculation result can be displayed on the display screen 860. When the environmental dose rate is greater than the preset radiation threshold, the controller 830 generates an alarm message and controls the alarm 870 to send an alarm signal, thereby preventing people from mistakenly entering the radiation area. Furthermore, the radioactive detection equipment may also include a high-voltage circuit and a power supply battery.

[0059] Fig.10 FIG. 4 is a block diagram showing a structure of a signal processing device according to an embodiment of the present invention. Fig.10 As shown, the signal processing device includes: a memory 1010 and a processor 1020, wherein the memory 1010 stores a computer program that can be run on the processor 1020. When the processor 1020 executes the computer program, the signal processing method for the radioactive detection device in the above embodiment is implemented. The number of the memory 1010 and the processor 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 transmission.

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

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

[0064] An embodiment of the present invention provides a computer-readable storage medium storing a computer program, which implements the method provided in the embodiment of the present application when the program is executed by a processor.

[0065] An embodiment of the present application also provides a chip, which includes a processor for calling and executing instructions stored in the memory from the memory, so that a communication device equipped with the chip executes the method provided by the embodiment of the present application.

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

[0067] It should be understood that the processor may be a central processing unit (CPU), or other general-purpose processors, digital signal processors (DSP), application specific integrated circuits (ASIC), field programmable gate arrays (FPGA) or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. The general-purpose processor may be a microprocessor or any conventional processor, etc. It is worth noting that the processor may be a processor supporting the advanced RISC machines (ARM) architecture.

[0068] Further, optionally, the above-mentioned memory may include a read-only memory and a random access memory, and may also include a non-volatile random access memory. The memory may be a volatile memory or a non-volatile memory, or may include both volatile and non-volatile memories. Among them, the non-volatile memory may include a read-only memory (ROM), a programmable read-only memory (PROM), an erasable programmable read-only memory (EPROM), an electrically erasable programmable read-only memory (EEPROM), or a flash memory. The volatile memory may include a random access memory (RAM), which is used as an external cache. By way of example but not limitation, many forms of RAM are available. For example, static RAM (SRAM), dynamic random access memory (DRAM), synchronous DRAM (SDRAM), double data rate synchronous dynamic random access memory (DDR SDRAM), enhanced synchronous dynamic random access memory (ESDRAM), synchronous link dynamic random access memory (SLDRAM) and direct rambus RAM (DR RAM).

[0069] In the above embodiments, it can be implemented in whole or in part by software, hardware, firmware or any combination thereof. When implemented using software, it can be implemented in whole or in part in the form of a computer program product. The computer program product includes one or more computer instructions. When the computer program instructions are loaded and executed on a computer, the process or function according to the present application is generated in whole or in part. The computer can be a general-purpose computer, a special-purpose computer, a computer network, or other programmable devices. The computer instructions can be stored in a computer-readable storage medium, or transmitted from one computer-readable storage medium to another computer-readable storage medium.

[0070] In the description of this specification, the description with reference to the terms "one embodiment", "some embodiments", "example", "specific example", or "some examples" means that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present application. Moreover, the specific features, structures, materials or characteristics described may be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art may combine and combine different embodiments or examples described in this specification and the features of different embodiments or examples, unless they are contradictory.

[0071] In addition, the terms "first" and "second" are used for descriptive purposes only and should not be understood as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Therefore, a feature defined as "first" or "second" may explicitly or implicitly include at least one of the features. In the description of this application, the meaning of "plurality" is two or more, unless otherwise clearly and specifically defined.

[0072] Any process or method description in the flow chart or otherwise described herein can be understood to represent a module, fragment or portion of a code including one or more executable instructions for implementing the steps of a specific logical function or process. And the scope of the preferred embodiment of the present application includes other implementations, in which the functions may not be performed in the order shown or discussed, including in a substantially simultaneous manner or in a reverse order according to the functions involved.

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

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

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

[0076] The above are only specific implementations of the present application, but the protection scope of the present application is not limited thereto. Any technician familiar with the technical field can easily think of various changes or substitutions within the technical scope disclosed in the present application, which should be included in the protection scope of the present application. Therefore, the protection scope of the present application should be based on the protection scope of the claims.

Claims

1. A signal processing method for a radioactive detection device, characterized in that: include: Analyze the collected nuclear pulse signal to obtain pulse amplitude information; Perform spectrum stabilization according to the pulse amplitude information to obtain a spectrum stabilization energy spectrum; Based on the stabilized spectrum, a nuclide identification result and a dose rate calculation result are determined.

2. The method according to claim 1, characterized in that Stabilizing the spectrum according to the pulse amplitude information to obtain a stabilized spectrum energy spectrum includes: Based on the pulse amplitude information, obtaining a measurement energy spectrum within a preset spectrum stabilization period; Analyzing the measured energy spectrum to obtain the actual peak position address of the reference source; Based on the reference peak position channel address of the reference source and the actual peak position channel address, the measured energy spectrum is corrected to obtain the stabilized spectrum energy spectrum.

3. The method according to claim 2, characterized in that Before obtaining the measured energy spectrum within a preset spectrum stabilization period based on the pulse amplitude information, the method further includes: The reference source is measured within a preset measurement time to obtain a reference energy spectrum; The reference energy spectrum is analyzed and peaks are found to determine reference data of characteristic peaks of the reference source; wherein the reference data includes reference peak position addresses.

4. The method according to claim 3, characterized in that The measured energy spectrum is analyzed to obtain the actual peak position of the reference source, including: Determine a first measurement track address interval according to the reference peak track address; In the measurement energy spectrum, traverse a plurality of measurement channels within the first measurement channel interval; The actual peak position track address of the reference source is determined according to the multiple measurement track addresses.

5. The method according to claim 4, characterized in that The reference data also includes energy resolution; determining the actual peak position channel address of the reference source according to the multiple measurement channel addresses includes: Based on the energy resolution, determining a second measurement track address interval corresponding to each of the measurement track addresses; Calculate the total number of peak areas within each of the second measurement channel address intervals; The measurement channel address corresponding to the maximum peak area total count is determined as the actual peak position channel address of the reference source.

6. The method according to claim 1, characterized in that Based on the stable spectrum energy spectrum, determining a nuclide identification result includes: Analyzing and peak searching the stable spectrum to determine the energy of characteristic peaks; The characteristic peak energy is compared with the data in the nuclide database to obtain a nuclide identification result.

7. The method according to any one of claims 1 to 6, characterized in that Based on the stabilized spectrum, a dose rate calculation result is determined, including: The stable spectrum is converted into a spectrum dose to obtain a dose rate calculation result.

8. A radioactive detection device, characterized in that: include: Detector, used to collect nuclear pulse signals; A digital processor, wherein the input end of the digital processor is connected to the output end of the detector, and the digital processor is used to analyze the collected nuclear pulse signal to obtain pulse amplitude information; A controller, wherein the input end of the controller is connected to the output end of the digital processor, and the controller is used to perform spectrum stabilization according to the pulse amplitude information to obtain a stabilized spectrum energy spectrum, and determine a nuclide identification result and a dose rate calculation result based on the stabilized spectrum energy spectrum.

9. A signal processing device, characterized in that: include: A processor and a memory, wherein the memory stores instructions, and the instructions are loaded and executed by the processor to implement the method according to any one of claims 1 to 7.

10. A computer-readable storage medium, wherein a computer program is stored in the computer-readable storage medium, and when the computer program is executed by a processor, the method according to any one of claims 1 to 7 is implemented.

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