Nuclear radiation monitoring system and apparatus

Abstract

The invention belongs to the technical field of nuclear radiation monitoring, and particularly relates to a nuclear radiation monitoring system and device.The nuclear radiation monitoring system comprises a scintillator detector unit used for converting incident gamma rays and / or X rays into electric pulse signals; the signal processing unit is in signal connection with the scintillator detector unit and is used for processing the electric pulse signal to output a trigger signal and a peak voltage; and the data processing unit is in signal connection with the signal processing unit, and is used for counting the trigger signals to obtain a dose rate, accumulating the peak voltage to obtain energy spectrum data, and uploading the dose rate and the energy spectrum data to a cloud platform, so that the cloud platform determines a nuclear radiation monitoring result based on the dose rate and the energy spectrum data. Therefore, the precision and the reliability of nuclear radiation monitoring are remarkably improved, the hardware complexity and the cost are reduced, and the environmental adaptability of the system is improved.

Description

Technical Field

[0001] This invention belongs to the field of nuclear radiation monitoring technology, and particularly relates to a nuclear radiation monitoring system and equipment. Background Technology With the widespread development of nuclear power generation and the increasing application of radioactive materials in fields such as medicine and industrial testing, the monitoring of ionizing radiation in the environment has become particularly important. Real-time and accurate radiation monitoring is required around nuclear power plants, hospital radiology departments, and industrial non-destructive testing sites to ensure public health and environmental safety. Especially in nuclear accident emergency response, the rapid identification of radioactive nuclides plays a crucial role in accident severity assessment, contamination scope definition, and subsequent response decisions.

[0002] However, most commercially available equipment can only measure the ambient dose rate and cannot obtain energy spectrum information, making it impossible to distinguish between natural background radiation and artificial radionuclides, thus failing to meet the needs of precise monitoring. Traditional energy spectrometers also have significant drawbacks: high-purity germanium detectors, while highly accurate, require liquid nitrogen cooling and are bulky and expensive; while spectrometers using NaI(Tl) scintillators are slightly cheaper, their photomultiplier tubes require high-voltage power supply and are sensitive to magnetic fields, and the crystals are prone to deliquescence and have poor reliability. In addition, the systems rely on high-speed ADCs and FPGAs, resulting in high complexity and cost, making it difficult to meet the requirements of low-cost, low-power large-scale deployment. Summary of the Invention

[0003] This invention aims to at least partially solve one of the technical problems in related technologies. Therefore, the first objective of this invention is to provide a nuclear radiation monitoring system that significantly improves the accuracy and reliability of nuclear radiation monitoring, reduces hardware complexity and cost, and enhances the system's environmental adaptability.

[0004] The second objective of this invention is to provide a nuclear radiation monitoring device.

[0005] To achieve the above objectives, a first aspect of the present invention provides a nuclear radiation monitoring system, wherein the system comprises: a scintillator detector unit for converting incident gamma rays and / or X-rays into electrical pulse signals; a signal processing unit, signal-connected to the scintillator detector unit, for processing the electrical pulse signals to output a trigger signal and a peak voltage; and a data processing unit, signal-connected to the signal processing unit, for counting the trigger signals to obtain a dose rate and accumulating the peak voltage to obtain energy spectrum data, and uploading the dose rate and the energy spectrum data to a cloud platform so that the cloud platform determines the nuclear radiation monitoring results based on the dose rate and the energy spectrum data.

[0006] The nuclear radiation monitoring system according to embodiments of the present invention significantly improves the accuracy and reliability of nuclear radiation monitoring, reduces hardware complexity and cost, and enhances the system's environmental adaptability.

[0007] In addition, the nuclear radiation monitoring system according to the above embodiments of the present invention may further include the following additional technical features: According to one embodiment of the present invention, the scintillator detector unit includes an inorganic scintillator and a silicon photomultiplier tube connected to each other. The inorganic scintillator is used to convert the γ-rays and / or the X-rays into optical signals, and the silicon photomultiplier tube is used to convert the optical signals into electrical pulse signals.

[0008] According to one embodiment of the present invention, the inorganic scintillator is a GAGG:Ce scintillator.

[0009] According to an embodiment of the present invention, the signal processing unit includes: a bias power supply connected to the silicon photomultiplier tube (SMT) for providing a working bias voltage to the SMT; an amplifier circuit for receiving and amplifying an electrical pulse signal output by the SMT; a filter and shaping circuit connected to the amplifier circuit for filtering and shaping the amplified electrical pulse signal; a comparator circuit connected to the filter and shaping circuit for comparing the filtered and shaped electrical pulse signal with a preset voltage to identify the preset pulse signal; a peak extraction circuit connected to the filter and shaping circuit for extracting the peak voltage of the electrical pulse signal; and an analog-to-digital conversion circuit connected to the peak extraction circuit for converting the peak voltage into a digital signal.

[0010] According to one embodiment of the present invention, the analog-to-digital conversion circuit is a low-speed analog-to-digital conversion circuit.

[0011] According to one embodiment of the present invention, the bias power supply is further used to: automatically adjust the bias voltage output to the silicon photomultiplier tube according to the ambient temperature.

[0012] According to one embodiment of the present invention, the data processing unit includes a sampling control module, which is signal-connected to the comparator circuit, the peak extraction circuit, and the analog-to-digital conversion circuit, respectively. The sampling control module is configured to: acquire a preset pulse signal output by the comparator circuit; drive the analog-to-digital conversion circuit to operate based on the preset pulse signal; acquire the digital signal output by the analog-to-digital conversion circuit after it operates to generate energy spectrum data based on the digital signal; acquire the number of pulses of the trigger signal; and determine the dose rate based on the number of pulses.

[0013] The sampling control module of the low-speed analog-to-digital conversion circuit is further configured to correct the dose rate based on the energy spectrum data.

[0014] The sampling control module of the low-speed analog-to-digital conversion circuit is further configured to reset the peak extraction circuit after completing the acquisition of the digital signal.

[0015] To achieve the above objectives, a second aspect of the present invention provides a nuclear radiation monitoring device, including the nuclear radiation monitoring system described in the aforementioned embodiments of the present invention.

[0016] The nuclear radiation monitoring equipment according to embodiments of the present invention significantly improves the accuracy and reliability of nuclear radiation monitoring, reduces hardware complexity and cost, and enhances the system's environmental adaptability.

[0017] Additional aspects and advantages of the invention will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the invention. Attached Figure Description

[0018] Figure 1 This is a block diagram of a nuclear radiation monitoring system according to an embodiment of the present invention; Figure 2 This is a block diagram of a nuclear radiation monitoring system according to a specific embodiment of the present invention; Figure 3 This is a block diagram of a nuclear radiation monitoring device according to an embodiment of the present invention.

[0019] Figure label: Nuclear radiation monitoring system 100, scintillator detector unit 10, signal processing unit 20, data processing unit 30, inorganic scintillator 11, silicon photomultiplier tube 12, bias power supply 21, amplifier circuit 22, filter shaping circuit 23, comparator circuit 24, peak extraction circuit 25, analog-to-digital conversion circuit 26, sampling control module 31, storage module 32, nuclear radiation monitoring equipment 1000. Detailed Implementation

[0020] Embodiments of the present invention are described in detail below, examples of which are illustrated in the accompanying drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and intended to explain the present invention, and should not be construed as limiting the present invention.

[0021] The nuclear radiation monitoring system and nuclear radiation monitoring equipment of the present invention are described below with reference to the accompanying drawings.

[0022] Figure 1 This is a block diagram of a nuclear radiation monitoring system according to an embodiment of the present invention.

[0023] Specifically, such as Figure 1As shown, the nuclear radiation monitoring system 100 includes a scintillator detector unit 10, a signal processing unit 20, and a data processing unit 30.

[0024] The scintillator detector unit 10 is used to convert incident gamma rays and / or X-rays into electrical pulse signals; the signal processing unit 20 is signal-connected to the scintillator detector unit and is used to process the electrical pulse signals to output trigger signals and peak voltages; the data processing unit 30 is signal-connected to the signal processing unit and is used to count the trigger signals to obtain the dose rate and to accumulate the peak voltages to obtain energy spectrum data, and to upload the dose rate and energy spectrum data to the cloud platform so that the cloud platform can determine the nuclear radiation monitoring results based on the dose rate and energy spectrum data.

[0025] Specifically, in this embodiment, such as Figure 2 As shown, the system workflow is as follows: When gamma rays and / or X-rays are incident on the scintillator detector unit 10, the scintillator detector unit 10 includes an inorganic scintillator 11 and a silicon photomultiplier tube 12 connected to each other. The inorganic scintillator 11 first deposits and converts the energy of the gamma rays and / or X-rays into fluorescent photons, the number of which is proportional to the energy of the rays. Then, the silicon photomultiplier tube 12 converts the fluorescent photon signal into a weak current pulse signal and outputs it to the signal processing unit 20. In the signal processing unit 20, the current pulse signal is amplified by the amplifier circuit 22 and conditioned by the filter and shaping circuit 23, and then divided into two independent signals: one is sent to the comparator circuit 24 for comparison with a preset threshold voltage. When the pulse amplitude exceeds the threshold, a trigger signal is output to the data processing unit 30; the other is sent to the peak extraction circuit 25, which accurately captures and holds the peak voltage of the pulse through a holding network composed of diodes and capacitors, and then the analog-to-digital converter circuit 26 quantizes it into a digital signal. Upon receiving a trigger signal, the sampling control module 31 in the data processing unit 30 immediately begins acquiring the peak digital signal and accumulates the data into the corresponding energy spectrum, while simultaneously recording the pulse count. After sampling is completed, the peak holding capacitor is reset to prepare for receiving the next pulse. The system calculates the initial dose rate statistically from the pulse count and uses the accumulated energy spectrum data to perform energy response compensation on the initial dose rate. Finally, the corrected accurate dose rate and energy spectrum data are uploaded to the cloud platform via the IoT communication module.

[0026] Furthermore, in some embodiments of the present invention, such as Figure 2 As shown, the scintillator detector unit 10 includes an inorganic scintillator 11 and a silicon photomultiplier tube 12 connected to each other. The inorganic scintillator 11 is used to convert γ-rays and / or X-rays into optical signals, and the silicon photomultiplier tube 12 is used to convert optical signals into electrical pulse signals.

[0027] Specifically, in this embodiment, the inorganic scintillator 11 and the silicon photomultiplier tube 12 (SiPM) achieve optical contact through an optical coupling agent, forming an integrated detection structure. When the inorganic scintillator 11 is irradiated by gamma rays and / or X-rays, it deposits ray energy through interactions such as the photoelectric effect and Compton scattering. The number of scintillating photons generated is proportional to the incident ray energy. These scintillating photons are transmitted to the photosensitive area of ​​the silicon photomultiplier tube 12 via the optical interface. The silicon photomultiplier tube 12 uses its densely packed micropixel units to convert the photon signal into corresponding current pulses. This combined structure has significant advantages over the traditional photomultiplier tube (PMT) scheme. The operating voltage of the SiPM is typically below 50V, far lower than the kilovolt-level high voltage required by the PMT, greatly reducing the complexity and safety risks of power supply design. At the same time, the SiPM uses solid-state semiconductor technology, which has the characteristics of compact size, resistance to mechanical vibration, and insensitivity to magnetic fields, greatly improving the environmental adaptability of the detector.

[0028] Furthermore, in some embodiments of the present invention, the inorganic scintillator 11 is a GAGG:Ce scintillator.

[0029] Specifically, in this embodiment, the inorganic scintillator 11 is a GAGG:Ce scintillator. The GAGG:Ce scintillator has a strong blocking ability against gamma rays and X-rays, ensuring high detection efficiency. Secondly, the GAGG:Ce crystal does not contain spontaneously radioactive nuclides and has extremely low background noise. At the same time, its physical and chemical properties are stable, and it does not have the deliquescence problem of NaI(Tl) crystal. It can work stably in a humid environment for a long time without special packaging. Furthermore, in some embodiments of the present invention, such as Figure 2 As shown, the signal processing unit 20 includes: a bias power supply 21 connected to the silicon photomultiplier tube 12, used to provide a working bias voltage for the silicon photomultiplier tube 12; an amplifier circuit 22 used to receive and amplify the electrical pulse signal output by the silicon photomultiplier tube 12; a filter and shaping circuit 23 connected to the amplifier circuit 22, used to filter and shape the amplified electrical pulse signal; a comparator circuit 24 connected to the filter and shaping circuit 23, used to compare the filtered and shaped electrical pulse signal with a preset voltage to identify the preset pulse signal; a peak extraction circuit 25 connected to the filter and shaping circuit 23, used to extract the peak voltage of the electrical pulse signal; and an analog-to-digital conversion circuit 26 connected to the peak extraction circuit 25, used to convert the peak voltage into a digital signal.

[0030] Specifically, in this embodiment, the signal processing unit 20 adopts a modular cascaded architecture, with each circuit module connected sequentially according to the signal flow direction to form a complete processing link. The system workflow is as follows: The bias power supply 21 first provides a stable operating bias voltage to the silicon photomultiplier tube 12, ensuring that it operates in the linear region. When radiating particles deposit energy in the inorganic scintillator 11, the silicon photomultiplier tube 12 outputs a weak current pulse signal. This signal first enters the amplifier circuit 22 for amplitude amplification, boosting it to a level suitable for subsequent processing.

[0031] The amplified pulse signal is fed into the filtering and shaping circuit 23, which performs noise filtering and waveform shaping to optimize the rise time and pulse width characteristics, improving signal quality while preserving the original information. The shaped signal is then processed in parallel in two paths: one path is fed into the comparator circuit 24, which compares it with a preset threshold voltage to identify valid radiated pulses and outputs a corresponding trigger signal; the other path is input to the peak extraction circuit 25, which accurately captures and maintains the peak voltage of the pulse, providing a stable input signal for subsequent analog-to-digital conversion.

[0032] The analog-to-digital converter circuit 26 quantizes the analog voltage held by the peak extraction circuit 25 into a digital signal, and the conversion result is transmitted to the data processing unit 30 for further analysis. Throughout the processing chain, the timing of each module is precisely coordinated: the trigger signal output by the comparator initiates the analog-to-digital conversion process; after conversion, the control system generates a reset signal to clear the peak holding state, preparing for the next measurement. This ensures that each effective radiation pulse can be accurately acquired and analyzed, while maintaining the system's fast response characteristics.

[0033] Furthermore, in some embodiments of the present invention, the analog-to-digital conversion circuit 26 is a low-speed analog-to-digital conversion circuit.

[0034] Specifically, in this embodiment, the analog-to-digital conversion circuit 26 employs a low-speed analog-to-digital converter (ADC), whose operating speed is significantly lower than that of the high-speed ADCs used in traditional radiation spectroscopy measurement systems. This design choice is based on the system's unique signal processing architecture: the rapid electrical pulse signal generated by the silicon photomultiplier tube 12 is converted into a steady-state peak voltage signal with a longer hold time through the pre-stage peak extraction circuit 25. This significantly reduces system complexity and cost.

[0035] Furthermore, in some embodiments of the present invention, the bias power supply 21 is also used to automatically adjust the bias voltage output to the silicon photomultiplier tube 12 according to the ambient temperature.

[0036] Specifically, in this embodiment, the bias power supply 21 integrates a temperature sensor and voltage compensation circuit, forming a complete closed-loop control system. The temperature sensor monitors changes in ambient temperature in real time and converts the temperature signal into corresponding changes in electrical parameters. The compensation circuit dynamically adjusts the feedback network of the power output stage based on these changes, ensuring that the final output bias voltage has a specific compensation relationship with the temperature. When the ambient temperature rises, the bias voltage increases accordingly; when the ambient temperature decreases, the bias voltage decreases accordingly, thereby achieving temperature compensation for the gain of the silicon photomultiplier tube 12. This significantly improves the data consistency and reliability of the system during long-term monitoring in the field environment, avoiding measurement deviations caused by diurnal temperature differences or seasonal changes.

[0037] Furthermore, in some embodiments of the present invention, such as Figure 2 As shown, the data processing unit 30 includes a sampling control module 31, which is connected to the comparator circuit 24, the peak extraction circuit 25, and the analog-to-digital converter circuit 26. The sampling control module 31 is configured to: acquire the preset pulse signal output by the comparator circuit 24; drive the analog-to-digital converter circuit 26 to work based on the preset pulse signal; acquire the digital signal output by the analog-to-digital converter circuit 26 after it works to generate energy spectrum data based on the digital signal; acquire the number of pulses of the trigger signal; and determine the dose rate based on the number of pulses.

[0038] Specifically, in this embodiment, when the comparator circuit 24 identifies a valid pulse and generates a trigger signal, this signal immediately triggers an external interrupt to the sampling control module 31. In the interrupt service routine, the module responds quickly, performing three key operations: First, it starts the analog-to-digital conversion circuit 26, reads and saves the digital value corresponding to the pulse peak value held by the peak extraction circuit 25; second, it uses this digital value as an address to accumulate and count the corresponding channel address in the energy spectrum data area of ​​the internal memory, thereby dynamically generating and updating the energy spectrum histogram; finally, it increments an independent pulse counter, the accumulated value of which is used to calculate the initial dose rate. This ensures that each identified radiation event is recorded promptly and accurately, while simultaneously completing the accumulation of raw data for energy spectrum construction and dose rate calculation.

[0039] Furthermore, in some embodiments of the present invention, the sampling control module 31 is also configured to correct the dose rate based on the energy spectrum data.

[0040] Specifically, in this embodiment, the sampling control module 31 internally stores a pre-calibrated detector energy response curve. After a fixed measurement cycle, the sampling control module 31 calls a processing program to analyze the currently accumulated energy spectrum data. This processing program calculates the actual contribution weight of each energy range count to the total dose rate, i.e., the weighting factor, based on the energy spectrum distribution. Subsequently, the system no longer simply multiplies the total count rate by a single coefficient, but instead uses a weighted summation method: corrected dose rate = Σ(count rate of each energy range × corresponding weighting factor). This effectively compensates for potential differences in detector efficiency in low-energy or high-energy regions, making the final output dose rate value closer to the actual ambient radiation level, significantly improving the accuracy and reliability of the measurement.

[0041] Furthermore, in some embodiments of the present invention, the sampling control module 31 is also configured to reset the peak extraction circuit 25 after completing the acquisition of the digital signal.

[0042] Specifically, in this embodiment, after the analog-to-digital conversion circuit 26 successfully acquires the peak voltage digital signal, the sampling control module 31 generates a brief digital pulse signal with controllable pulse width through a general-purpose input / output port. This reset signal is applied to the reset switch (usually composed of a MOSFET) in the peak extraction circuit 25, causing it to turn on instantaneously, thereby rapidly releasing the charge stored in the holding capacitor to ground. This effectively prevents the "pulse accumulation" distortion caused by the superposition of two consecutive pulse signals and minimizes the system's dead time (i.e., the time during which the system cannot process new pulses), ensuring accurate energy spectrum and count data can still be obtained under high count rate conditions.

[0043] Furthermore, in some embodiments of the present invention, such as Figure 2 As shown, the data processing unit 30 includes a storage module 32 for storing dose rate and energy spectrum data.

[0044] Specifically, in this embodiment, the storage module 32 uses a Flash memory (such as W25Q128) with an SPI (Serial Peripheral Interface) interface. Its storage space is divided into three logical areas: energy spectrum data area, dose rate history record area, and device calibration parameter area. The energy spectrum data area adopts a circular cache structure to continuously store complete energy spectrum data for multiple time periods, supporting energy spectrum change trend analysis. The dose rate history record area stores dose rate values ​​with timestamps in a time sequence to form a long-term monitoring database. The calibration parameter area stores key calibration data such as the detector's energy response curve and temperature compensation coefficient.

[0045] In summary, the nuclear radiation monitoring system according to embodiments of the present invention significantly improves the accuracy and reliability of nuclear radiation monitoring, reduces hardware complexity and cost, and enhances the system's environmental adaptability.

[0046] Figure 3 This is a block diagram of a nuclear radiation monitoring device according to an embodiment of the present invention.

[0047] Specifically, such as Figure 3 As shown, the nuclear radiation monitoring device 1000 includes the nuclear radiation monitoring system 100 described in the above embodiment of the present invention.

[0048] The nuclear radiation monitoring equipment according to embodiments of the present invention significantly improves the accuracy and reliability of nuclear radiation monitoring, reduces hardware complexity and cost, and enhances the system's environmental adaptability.

[0049] It should be noted that 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 specifically implemented 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). For the purposes of this specification, "computer-readable medium" can be any means that can contain, store, communicate, propagate, or transmit programs for use by, or in conjunction with, an instruction execution system, apparatus, or device. More specific examples (a non-exhaustive list) of computer-readable media include: an electrical connection having one or more wires (electronic device), a portable computer disk drive (magnetic device), random access memory (RAM), read-only memory (ROM), erasable and editable read-only memory (EPROM or flash memory), fiber optic devices, and portable optical disc read-only memory (CDROM). Alternatively, the computer-readable medium may be paper or other suitable media on which the program can be printed, since the program can be obtained electronically, for example, by optically scanning the paper or other medium, followed by editing, interpreting, or otherwise processing as necessary, and then stored in a computer memory.

[0050] It should be understood that various parts of the present invention can be implemented in hardware, software, firmware, or a combination thereof. In the above embodiments, multiple steps or methods can be implemented in software or firmware stored in memory and executed by a suitable instruction execution system. For example, if implemented in hardware, as in another embodiment, it can be implemented using any one or a combination of the following techniques known in the art: discrete logic circuits having logic gates for implementing logical functions on data signals, application-specific integrated circuits (ASICs) having suitable combinational logic gates, programmable gate arrays (PGAs), field-programmable gate arrays (FPGAs), etc.

[0051] In the description of this specification, 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 the invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples.

[0052] In the description of this invention, it should be understood that the terms "center," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," and "circumferential" indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are used only for the convenience of describing this invention and simplifying the description, and are not intended to indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this invention.

[0053] 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 invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0054] In this invention, unless otherwise explicitly specified and limited, the terms "installation," "connection," "linking," and "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components, unless otherwise explicitly limited. Those skilled in the art can understand the specific meaning of the above terms in this invention according to the specific circumstances.

[0055] In this invention, unless otherwise explicitly specified and limited, "above" or "below" the second feature can mean that the first feature is in direct contact with the second feature, or that the first feature is in indirect contact with the second feature through an intermediate medium. Furthermore, "above," "over," and "on top" of the second feature can mean that the first feature is directly above or diagonally above the second feature, or simply that the first feature is at a higher horizontal level than the second feature. "Below," "below," and "under" the second feature can mean that the first feature is directly below or diagonally below the second feature, or simply that the first feature is at a lower horizontal level than the second feature.

[0056] Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention. Those skilled in the art can make changes, modifications, substitutions and variations to the above embodiments within the scope of the present invention.

Claims

1. A nuclear radiation monitoring system, characterized in that, The system includes: A scintillator detector unit is used to convert incident gamma rays and / or X-rays into electrical pulse signals; The signal processing unit, which is signal-connected to the scintillator detector unit, is used to process the electrical pulse signal to output a trigger signal and a peak voltage; A data processing unit, connected to the signal processing unit, is used to count the trigger signal to obtain the dose rate and to accumulate the peak voltage to obtain energy spectrum data. The dose rate and the energy spectrum data are then uploaded to a cloud platform so that the cloud platform can determine the nuclear radiation monitoring results based on the dose rate and the energy spectrum data.

2. The nuclear radiation monitoring system according to claim 1, characterized in that, The scintillator detector unit includes an inorganic scintillator and a silicon photomultiplier tube connected to each other. The inorganic scintillator is used to convert the γ-rays and / or the X-rays into optical signals, and the silicon photomultiplier tube is used to convert the optical signals into electrical pulse signals.

3. The nuclear radiation monitoring system according to claim 2, characterized in that, The inorganic scintillator is a GAGG:Ce scintillator.

4. The nuclear radiation monitoring system according to claim 2, characterized in that, The signal processing unit includes: A bias power supply, connected to the silicon photomultiplier tube, is used to provide a working bias voltage for the silicon photomultiplier tube; An amplifier circuit is used to receive and amplify the electrical pulse signal output by the silicon photomultiplier tube; A filtering and shaping circuit, connected to the amplification circuit, is used to filter and shape the amplified electrical pulse signal; A comparator circuit, connected to the filter and shaping circuit, is used to compare the filtered and shaped electrical pulse signal with a preset voltage to identify the preset pulse signal. A peak extraction circuit, connected to the filtering and shaping circuit, is used to extract the peak voltage of the electrical pulse signal; An analog-to-digital converter circuit, connected to the peak extraction circuit, is used to convert the peak voltage into a digital signal.

5. The nuclear radiation monitoring system according to claim 4, characterized in that, The analog-to-digital converter circuit is a low-speed analog-to-digital converter circuit.

6. The nuclear radiation monitoring system according to claim 4, characterized in that, The bias power supply is also used to automatically adjust the bias voltage output to the silicon photomultiplier tube according to the ambient temperature.

7. The nuclear radiation monitoring system according to claim 4, characterized in that, The data processing unit includes a sampling control module, which is signal-connected to the comparator circuit, the peak extraction circuit, and the analog-to-digital conversion circuit, respectively. The sampling control module is configured to: The preset pulse signal output by the comparator circuit is acquired, the analog-to-digital converter circuit is driven to work based on the preset pulse signal, and the digital signal output by the analog-to-digital converter circuit after it works is acquired, so as to generate energy spectrum data based on the digital signal. The number of pulses of the trigger signal is collected, and the dose rate is determined based on the number of pulses.

8. The nuclear radiation monitoring system according to claim 7, characterized in that, The sampling control module is also configured to: The dose rate is corrected based on the energy spectrum data.

9. The nuclear radiation monitoring system according to claim 7, characterized in that, The sampling control module is also configured to: After the digital signal acquisition is completed, the peak extraction circuit is reset.

10. A nuclear radiation monitoring device, characterized in that, The nuclear radiation monitoring system includes any one of claims 1-9.

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