GM counting tube energy response optimization method, radiation dose detector, electronic equipment and storage medium

Abstract

The invention discloses an energy response optimization method of a GM counting tube, a radiation dose detector, electronic equipment and a storage medium. The energy response optimization method of the GM counting tube comprises the steps that energy response curves of the GM counting tube comprising different energy response compensation sleeves are determined respectively, and the different energy response compensation sleeves are obtained by combining different material types, different material thicknesses and different coverage areas; and the coverage area is the area of the sensitive area of the GM counting tube covered by the response compensation sleeve. And determining a target energy response compensation sleeve according to the energy response curves corresponding to the GM counting tubes of the different energy response compensation sleeves.

Description

Technical Field

[0001] The present invention relates to the technical field of image processing, and in particular to a method for optimizing the energy response of a GM counter tube, a radiation dose detector, an electronic device, and a storage medium. Background Art

[0002] A main problem with the energy response of a GM counter tube is over-response in the low-energy range. The over-response in the low-energy range is mainly caused by the photoelectric effect of the outer shell. The current method for improving the energy response is to add a heavy metal cladding layer as a shielding material to the outer shell of the GM counter tube to suppress the response in the low-energy range. This heavy metal cladding layer is called an energy response compensation sleeve.

[0003] However, if the sensitive area of the GM counter tube is completely covered by the heavy metal cladding layer, gamma rays below 65 keV are basically absorbed, resulting in a very low energy response below 65 keV. It can be seen that the nuclear radiation monitoring instrument using a GM counter as a detector in the related art has the problem that it is difficult to accurately and stably suppress and correct the over-response in the low-energy range. Summary of the Invention

[0004] In view of this, embodiments of the present invention provide a method for optimizing the energy response of a GM counter tube, a radiation dose detector, an electronic device, and a storage medium, aiming to improve the accuracy and reliability of the analysis process of isotope abundance information.

[0005] The technical solution of the embodiments of the present invention is realized as follows:

[0006] On the one hand, embodiments of the present invention provide a method for optimizing the energy response of a GM counter tube, the method comprising:

[0007] Determine the energy response curves of GM counter tubes including different energy response compensation sleeves respectively, where the different energy response compensation sleeves are obtained by combining different material types, different material thicknesses, and different coverage areas, and the coverage area is the area where the energy response compensation sleeve covers the sensitive area of the GM counter tube;

[0008] Determine the target energy response compensation sleeve according to the energy response curves corresponding to the GM counter tubes with different energy response compensation sleeves.

[0009] In the above solution, the determining the target energy response compensation sleeve according to the energy response curves corresponding to the GM counter tubes with different energy response compensation sleeves includes:

[0010] Determine the average value of the difference between the count rates corresponding to different energies in each energy response curve and the pre-designed count rate;

[0011] Determine the energy response compensation sleeve corresponding to the energy response curve with the minimum average value as the target energy response compensation sleeve.

[0012] On the other hand, an embodiment of the present application further provides a radiation dose detector, including: a GM counter tube, a main control circuit, a signal acquisition circuit, and a trigger circuit, where the GM counter tube includes a target energy response compensation sleeve as described in claim 1;

[0013] The GM counter tube is used to detect gamma rays in the environment and generate a current pulse signal;

[0014] The signal acquisition circuit is used to convert the current pulse signal generated by the GM counter tube into a voltage pulse signal;

[0015] The trigger circuit is used to convert the voltage pulse signal into a level signal and send it to the main control circuit;

[0016] The main control circuit is used to determine the radiation dose rate according to the received level signal.

[0017] In the above solution, the radiation dose detector further includes: a range switching circuit;

[0018] The GM counter tube includes: a high-range GM counter tube and a low-range GM counter tube;

[0019] The range switching circuit is used to control the on and off of the high-range GM counter tube and the low-range GM counter tube.

[0020] In the above solution, the range switching circuit includes at least two optoelectronic relays.

[0021] In the above solution, the radiation dose detector further includes: a high-voltage power supply;

[0022] The high-voltage power supply is used to provide a working voltage for the GM counter tube.

[0023] In the above solution, the radiation dose detector further includes: an alarm circuit;

[0024] The main control module is used to control the alarm circuit to give an alarm when the radiation dose rate exceeds a threshold.

[0025] On the other hand, an embodiment of the present application further provides a computer program product, including a computer program, where when the computer program is executed by a processor, the steps of the above method for optimizing the energy response of the GM counter tube are implemented.

[0026] On the other hand, an embodiment of the present invention provides an electronic device, including a processor and a memory, where the processor and the memory are connected to each other. Among them, the memory is used to store a computer program, the computer program includes program instructions, and the processor is configured to call the program instructions to execute the steps of the method for optimizing the energy response of the GM counter tube provided in the first aspect of the embodiment of the present invention.

[0027] On the other hand, an embodiment of the present invention provides a computer-readable storage medium, including: the computer-readable storage medium stores a computer program. When the computer program is executed by a processor, the steps of the energy response optimization method of the GM counter tube provided in the first aspect of the embodiment of the present invention are implemented.

[0028] In the embodiment of the present application, by respectively determining the energy response curves of GM counter tubes including different energy response compensation sleeves, different energy response compensation sleeves are obtained by combining different material types, different material thicknesses, and different coverage areas, and the coverage area is the area where the energy response compensation sleeve covers the sensitive area of the GM counter tube. According to the energy response curves corresponding to the GM counter tubes with different energy response compensation sleeves, the target energy response compensation sleeve is determined. Through the embodiment of the present application, the target energy response compensation sleeve with the best energy response compensation effect can be determined, and the over-response in the low energy segment can be accurately and stably suppressed and corrected. BRIEF DESCRIPTION OF THE DRAWINGS

[0029] Figure 1 is a schematic diagram of the energy response curve of a naked GM counter tube provided by an embodiment of the present invention;

[0030] Figure 2 is a schematic diagram of the implementation flow of an energy response optimization method of a GM counter tube provided by an embodiment of the present invention;

[0031] Figure 3 is a schematic diagram of the energy response compensation structure of a GM tube provided by an embodiment of the present invention;

[0032] Figure 4 is a schematic diagram of a plateau curve provided by an embodiment of the present invention;

[0033] Figure 5 is a comparison diagram of the energy response compensation effects of different materials provided by an embodiment of the present invention;

[0034] Figure 6 is a comparison diagram of the energy response compensation effects of different material thicknesses provided by an embodiment of the present invention;

[0035] Figure 7 is a comparison of the energy response compensation effects of different compensation areas provided by an embodiment of the present invention;

[0036] Figure 8 is a schematic diagram of the structure of a radiation dose detector provided by an embodiment of the present invention;

[0037] Figure 9 is a schematic diagram of the structure of a GM tube detector provided by an embodiment of the present invention;

[0038] Figure 10It is a schematic diagram of the electronic device provided by the embodiment of the present invention. Detailed implementation manners

[0039] The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention. Obviously, the described embodiments are some, but not all, of the embodiments of the present invention. All other embodiments obtained by those of ordinary skill in the art based on the embodiments of the present invention without creative efforts shall fall within the protection scope of the present invention.

[0040] Radiation dosimetry quantities are mainly divided into three categories: basic physical quantities, radiation protection evaluation quantities (hereinafter referred to as "protection quantities") and radiation protection practical quantities (hereinafter referred to as "practical quantities"). In the field of radiation protection, protection quantities are usually used to measure the harm of radiation to human organs and tissues and determine dose limits. However, the equivalent dose and effective dose in human tissues cannot be directly measured. Therefore, a set of measurable radiation protection operational practical quantities first defined by the ICRU in Report No. 39 are used to estimate these doses. However, with the continuous development of the industry and the continuous expansion of the types and energy ranges of ionizing radiation particles, the limitations of the current operational practical quantities are becoming more and more obvious in the process of estimating protection quantities. In 2020, the ICRU (International Commission on Radiation Units and Measurements) issued Report No. 95, proposing a new system of external exposure operational practical quantities. The new practical quantity system provides a more comprehensive and accurate evaluation method, uses a more scientific whole-body human reference phantom, and can better evaluate protection quantities within a wider range of radiation types and energy ranges through the new practical quantity system.

[0041] For the accurate estimation of protection quantities by operational practical quantities, reliable measuring instruments are essential conditions. Currently, the site dose monitoring detectors on the market are all designed based on the current practical quantity system and are used to measure the ambient dose equivalent H*. The new changes brought by the new practical quantity system may lead to the possibility of energy response differences and inaccurate dose values. Therefore, in order to adapt to the new practical quantity system and ensure the effective evaluation of site dose monitoring, a site dose monitoring detector for the new practical quantity system needs to be designed.

[0042] The GM counter tube, also known as the Geiger-Müller counter tube, is widely used in various nuclear radiation measurements such as reactor radiation monitoring and environmental radiation monitoring. The GM counter tube has the advantages of high sensitivity, large output charge pulse amplitude, good stability, suitability for harsh environments, convenient use, and low manufacturing cost. Currently, GM counter tubes are widely used as detectors in military and civilian nuclear radiation monitors at home and abroad.

[0043] Due to the structure of the GM counter tube itself, for a naked counter tube, whether it is used to measure exposure or air kerma, or to measure new practical radiation quantities, there is a large deviation in the energy response of the instrument in the low-energy range due to over-response, which affects the accuracy of the measurement results.

[0044] As Figure 1 shown, Figure 1 is a schematic diagram of the energy response curve of a naked GM counter tube. It can be found that for a GM tube (naked tube) that is usually not compensated for energy response, there is a deviation in the response value for different ray energies. Generally, there is an obvious "over-response" in the low-energy range below 100 keV, that is, the measured value is greater than the actual value. Therefore, heavy metals are needed to shield low-energy rays.

[0045] The current method to improve the energy response is to add a layer of heavy metal cladding (energy response compensation sleeve) to the outer shell of the GM counter tube as a shielding material to suppress the response in the low-energy range. Generally, lead-tin is selected as the cladding. After adding the cladding, the GM counter tube will have the problem of over-suppression in the low-energy range. To overcome the problem of over-suppression, it is necessary to moderately expose the sensitive area of the GM counter tube. However, different exposed areas of the sensitive area will also affect the measurement results. Moreover, different cladding materials and thicknesses will also affect the measurement results.

[0046] In view of the shortcomings of the above background technology, the embodiment of the present invention provides a method for optimizing the energy response of a GM counter tube, which can determine the most reasonable energy response compensation sleeve and accurately and stably suppress and correct the over-response in the low-energy range. To illustrate the technical solution described in the present invention, the following will be described through specific embodiments.

[0047] Figure 2 is a schematic diagram of the implementation process of a method for optimizing the energy response of a GM counter tube provided by an embodiment of the present invention. The execution subject of the method for optimizing the energy response of the GM counter tube is an electronic device, and the electronic device includes a desktop computer, a laptop computer, a server, etc. Referring to Figure 2 , the method for optimizing the energy response of the GM counter tube includes:

[0048] S201, respectively determine the energy response curves of GM counter tubes including different energy response compensation sleeves, where the different energy response compensation sleeves are obtained by combining different material types, different material thicknesses, and different coverage areas, and the coverage area is the area where the energy response compensation sleeve covers the sensitive area of the GM counter tube.

[0049] The energy response refers to the relationship between the radiation sensitivity of the counter tube and the ray energy. By changing the energy, the radiation sensitivity of the technical tube at this energy is determined, and here the counting rate is used to represent the radiation sensitivity.

[0050] Design energy response compensation sleeves with different material types, different material thicknesses, and different coverage areas, and design a large number of energy response compensation sleeve models. Then, customize the energy response compensation sleeves for GM counters according to these models, and apply different energy response compensation sleeves to GM counters. Here, different energy response compensation sleeves should all be used with GM counters having the same rule parameters.

[0051] As Figure 3 shown, Figure 3 Figure shows the schematic diagram of the energy response compensation structure of the GM tube. The compensation layer of the GM counter corresponds to the energy response compensation sleeve, and the compensation layer partially covers the GM counter, making the sensitive area of the GM counter moderately exposed.

[0052] GM counters exhibit significantly different counting rate characteristics at different operating voltages. Before optimizing the design of the detector, measure its operating voltage through tests on the detector. Based on the low-energy X-ray reference radiation field, select the same measurement point, adjust the operating voltage of the GM tube separately, and record the actual counting rate data at different voltages. The obtained plateau curve is as Figure 4 shown. The growth of the counting rate in the range of 350V to 500V tends to be stable, which is the plateau region. Therefore, the operating voltage of the counter can be selected at 450V.

[0053] Then, obtain the energy response curve of the GM counter with the energy response compensation sleeve at the operating voltage. Each GM counter with an energy response compensation sleeve can obtain an energy response curve.

[0054] S202. Determine the target energy response compensation sleeve according to the energy response curves corresponding to the GM counters with different energy response compensation sleeves.

[0055] The energy response curves of the energy response compensation sleeves obtained by combining different material types, different material thicknesses, and different coverage areas are all different.

[0056] When designing the energy response compensation sleeve, the material thickness and coverage area can be controlled to be unchanged first, and different heavy metal materials are used for comparative analysis of the energy response curves to determine the best material type. Then, under this material type, the coverage area is controlled to be unchanged, and different material thicknesses are used for comparative analysis of the energy response curves to determine the best material thickness. Finally, under the above best material type and best material thickness, different coverage areas are used for comparative analysis of the energy response curves to determine the best coverage area.

[0057] The best material type, best material type, and best material thickness form the target energy response compensation sleeve.

[0058] For example, first control the material thickness and coverage area to be unchanged, and use different heavy metal materials for comparative analysis of the shielding effect. Figure 5The figure shows the comparison of the energy response compensation effects of energy response compensation sleeves made of 0.6 mm lead and 0.6 mm tin. By controlling other variables, it can be clearly found that the compensation ability of the lead material is significantly better than that of tin (the flatter the curve, the better), and at the same thickness, lead is more likely to meet the energy response requirements than tin.

[0059] Then, while controlling the material type and coverage area unchanged, a comparative analysis of the shielding effects with different lead thicknesses was carried out. Figure 6 The figure shows the comparison of the energy response compensation effects of energy response compensation sleeves made of lead with different thicknesses. It can be found that the lead with a thickness of 0.9 mm has a relatively better energy response (the flatter the curve, the closer the relative energy response is to 1, and the more linear the detector is, the better). However, over-compensation occurs in the low-energy range below 80 keV, and the low-energy response can be increased by reducing the compensation area.

[0060] Finally, while controlling the material type and material thickness unchanged, a comparative analysis with different compensation areas was carried out for the over-compensation of 0.9 mm lead. Figure 7 The figure shows the comparison of the energy response compensation effects of energy response compensation sleeves made of 0.9 mm lead with different compensation areas. It can be found that when the compensation area of the 0.9 mm lead is 85%, the relative energy response is the best (the closer the relative energy response is to 1 at each ray energy, the better). The compensation area refers to the area of the sensitive region of the GM tube covered by the energy response compensation sleeve, which can be simply understood as Figure 3 the compensation layer accounts for 85% of the total tube area in

[0061] It can be seen that the material of the target energy response compensation sleeve in one embodiment is lead, the thickness is 0.9 mm, and the coverage area is 85%.

[0062] Alternatively, a large number of energy response compensation sleeves can be designed according to experience, and the corresponding energy response curves can be obtained respectively. Determine the maximum count rate, minimum count rate, and average count rate in each energy response curve. The target energy response compensation sleeve can be determined based on the maximum count rate, minimum count rate, and average count rate.

[0063] For example, those with a maximum count rate greater than the threshold are excluded, and those with a minimum count rate less than the threshold are also excluded. Then, the one with the average count rate closest to the threshold is determined as the target energy response compensation sleeve.

[0064] In the embodiments of the present application, by respectively determining the energy response curves of GM counting tubes including different energy response compensation sleeves, different energy response compensation sleeves are obtained by combining different material types, different material thicknesses, and different coverage areas. The coverage area is the area of the sensitive region of the GM counting tube covered by the energy response compensation sleeve. Based on the energy response curves corresponding to the GM counting tubes with different energy response compensation sleeves, the target energy response compensation sleeve is determined. Through the embodiments of the present application, the target energy response compensation sleeve with the best energy response compensation effect can be determined, and the over-response in the low-energy range can be accurately and stably suppressed and corrected.

[0065] The embodiments of the present application are carried out based on new practical quantities for radiation protection, and the obtained target energy response compensation sleeve is under the new practical quantity system.

[0066] In one embodiment, determining the target energy response compensation sleeve according to the energy response curves corresponding to the GM counter tubes of different energy response compensation sleeves includes:

[0067] Determining the average value of the differences between the counting rates corresponding to different energies in each energy response curve and the pre-designed counting rate;

[0068] Determining the energy response compensation sleeve corresponding to the energy response curve with the smallest average value as the target energy response compensation sleeve.

[0069] For each energy response curve, determine the counting rates corresponding to different energies, calculate the differences between the counting rates corresponding to different energies and the pre-designed counting rate (for example, the pre-designed counting rate is 1) respectively, then calculate the average value of all differences, and determine the energy response compensation sleeve corresponding to the energy response curve with the smallest average value as the target energy response compensation sleeve.

[0070] The smallest average value indicates that the curve is more flat, the relative energy response is closer to 1, and the detector is more linear, which is better.

[0071] Figure 8 It is a schematic structural diagram of a radiation dose detector, including: a GM counter tube 11, a main control circuit 12, a signal acquisition circuit 13, and a trigger circuit 14. The GM counter tube uses the target energy response compensation sleeve in the above embodiment.

[0072] The GM counter tube 11 is used to detect gamma rays in the environment and generate current pulse signals;

[0073] The signal acquisition circuit 13 is used to convert the current pulse signal generated by the GM counter tube into a voltage pulse signal;

[0074] The trigger circuit 14 is used to convert the voltage pulse signal into a level signal and send it to the main control circuit;

[0075] The main control circuit 12 is used to determine the radiation dose rate according to the received level signal.

[0076] Among them, a GM counter tube is used as a radiation detector. Its basic structure is in a glass tube filled with an inert gas (such as argon or neon), with a tungsten wire in the center as the anode and a metal layer close to the surface of the glass tube as the cathode. When it starts working, the high voltage module in the power module circuit outputs the working high voltage to the anode wire. At this time, an electric field is formed inside the counter tube, and the radiation rays enter the detector and interact with the gas in the tube to produce ionization. Under the action of the electric field, the ions quickly avalanche discharge between the anode wire and the tube wall, and the primary particle incident event is quickly multiplied and amplified, thereby outputting a pulse signal with a large signal amplitude. The output frequency of the signal is proportional to the radiation dose, so the radiation dose rate can be obtained by converting the pulse signal count rate.

[0077] A target energy response compensation sleeve is arranged outside the GM counter tube of this embodiment, which can accurately and stably suppress and correct the over-response in the low energy range.

[0078] The main control circuit 12 can use an N32 chip as an MCU main control chip, and can obtain a radiation dose rate by converting a pulse signal count rate.

[0079] The signal acquisition circuit 13 can convert the current signal output by the GM counter tube into a pulse voltage signal through an RC circuit, and then the comparator of the trigger circuit 14 converts the voltage signal into a TTL level signal output. Among them, the comparator can adopt the LMV393TP-SR dual-channel voltage comparator, and its output end adopts an open collector structure. The uniqueness of this structure is that when the output of the comparator is at a high level, the output transistor is cut off, so that the output end is not directly driven to the power supply voltage level, but remains in an open circuit state. Therefore, the voltage level of the output end has strong flexibility and is determined by the voltage connected to the external pull-up resistor. This configuration provides higher flexibility and adaptability, allowing the system to perform accurate signal processing and counting according to specific application requirements.

[0080] In one embodiment, the radiation dose detector further comprises: a range switching circuit;

[0081] The GM counter tubes include: a high-range GM counter tube and a low-range GM counter tube;

[0082] The range switching circuit is used to control the opening and closing of the high-range GM counter tube and the low-range GM counter tube.

[0083] For example, it may include one high-range GM counter tube and two low-range GM counter tubes, and the range switching circuit may control the opening and closing of the GM counter tubes.

[0084] In one embodiment, the range switching circuit includes at least two photoelectric relays.

[0085] The range switching circuit can use two PhotoMOS to control the high-range GM counter tube and the low-range GM counter tube respectively. When the control pin is at a high level, the triode conducts, and the LED tube inside the optoelectronic relay emits light. The emitted light passes through the transparent silicon plate and irradiates the optoelectronic element on the opposite side. The optoelectronic element converts the light into a corresponding voltage according to the intensity of the light, and this voltage is output through the control circuit to charge the MOS-FET. When the gate voltage of the MOSFET reaches a predetermined voltage value, the MOSFET starts to conduct and connects the load. When the input signal current is turned off, the LED tube stops emitting light, the MOSFET is cut off, and the load is quickly disconnected.

[0086] In one embodiment, the radiation dose detector further includes: a high-voltage power supply;

[0087] The high-voltage power supply is used to provide the operating voltage for the GM counter tube.

[0088] Among them, the radiation dose detector includes a power supply module, and the high-voltage power supply can be a part of the power supply module. The power supply module includes two parts: a low-voltage power supply and a high-voltage power supply.

[0089] The low-voltage power supply part is divided into two voltage specifications of 5V and 3.3V. 5V is responsible for supplying power to the LMV393TP-SR comparator of 3PEAK, the reset circuit, the optoelectronic relay (PhotoMOS) for controlling on / off, and the field effect transistor for controlling voltage switching; the 3.3V voltage is dedicated to meeting the power supply requirements of the single-chip microcomputer and other logic chips. The power input of the host part is 12V, so a 12V-to-5V power supply module is used to complete the first step of power voltage conversion. The K7805T-1000R3 DC-DC power supply module of Jin Shengyang can be used. This module has characteristics such as high efficiency, low no-load power consumption, and short-circuit protection, and the maximum output current can reach 1000mA, which can meet the requirements for the 5V power supply in the detection unit. In order to meet the requirements of other logic chips, the AMS1117-3.3 chip of Huaxuanyang Electronics can be used to complete the conversion from 5V to 3.3V. The high-voltage power supply part can use the L1 series high-voltage power supply module DW-P501-1.5AL1 of Dongwen High-Voltage. The input 5V DC power supply can output a positive high voltage of 500V, and the output voltage can be linearly adjusted using a potentiometer, flexibly determining the tube voltage used, providing convenient conditions for testing the plateau curve of the detector. And if other detectors need to be replaced later, the tube voltage can be changed according to the requirements of the detector.

[0090] In one embodiment, the radiation dose detector further includes: an alarm circuit;

[0091] The main control module is used to control the alarm circuit to issue an alarm when the radiation dose rate exceeds the threshold.

[0092] An over - limit alarm function is installed on the periphery of the detector, which enables the monitoring system to issue an alarm in a timely manner when the radiation exceeds the safe range, ensuring the safety of personnel and the environment.

[0093] In one embodiment, an Electrically Erasable Programmable Read - Only Memory (EEPROM) can also be used to store various parameters to ensure that the stored relevant parameters can be retained after power failure or restart.

[0094] As Figure 9 shown, Figure 9 is a schematic structural diagram of a GM tube detector provided by an embodiment of the present invention, including:

[0095] a main control chip, a signal acquisition circuit, a high - voltage module, a power supply module, an EEPROM, GM counter tube 1 - 1, GM counter tube 2, GM counter tube 1 - 2, a range switching circuit, an over - limit alarm module, a display unit, and a trigger circuit.

[0096] Among them, the main control module is a control center for data acquisition, processing, signal control, communication, etc. The high - voltage power supply provides the working voltage for the GM counter tube. The signal acquisition circuit is used to convert the output current signal of the GM counter tube into a pulse voltage signal. The trigger circuit is used to convert the pulse voltage signal into a TTL digital signal output. The over - limit alarm module is used to control the alarm circuit to issue an alarm when the radiation dose rate exceeds the threshold. The display unit is used to display the current radiation dose rate.

[0097] It should be understood that the magnitudes of the sequence numbers of the steps in the above - mentioned embodiments do not mean the order of execution. The execution order of each process should be determined by its function and internal logic, and should not constitute any limitation to the implementation process of the embodiments of the present invention.

[0098] It should be understood that when used in this specification and the appended claims, the terms "comprising" and "including" indicate the presence of the described features, wholes, steps, operations, elements, and / or components, but do not exclude the presence or addition of one or more other features, wholes, steps, operations, elements, components, and / or their combinations.

[0099] It should be noted that the technical solutions described in the embodiments of the present invention can be combined arbitrarily without conflict.

[0100] In addition, in the embodiments of the present invention, "first", "second", etc. are used to distinguish similar objects and do not necessarily describe a specific order or sequence.

[0101] Based on the hardware implementation of the above program modules and to implement the method of the embodiments of the present application, the embodiments of the present application further provide an electronic device. Figure 10 It is a schematic diagram of the hardware composition structure of the electronic device according to the embodiments of the present application. As Figure 10 shown, the electronic device includes:

[0102] A communication interface capable of interacting with other devices such as network devices for information.

[0103] A processor, connected to the communication interface to enable information interaction with other devices, and when running a computer program, to execute the methods provided by one or more of the above technical solutions on the electronic device side. And the computer program is stored on the memory.

[0104] Of course, in actual application, each component in the electronic device is coupled together through a bus system. It can be understood that the bus system is used to realize the connection and communication between these components. In addition to the data bus, the bus system also includes a power bus, a control bus, and a status signal bus. However, for the sake of clear illustration, in Figure 10 all kinds of buses are labeled as the bus system.

[0105] The above electronic device can be in the form of a cluster, such as in the form of a cloud computing platform. The so-called cloud computing platform is a business form that uses computing virtualization, network virtualization, and storage virtualization technologies to organize multiple independent server physical hardware resources into pooled resources. It is a software-defined resource structure based on the development of virtualization technology and can provide resource capabilities in the form of virtual machines, containers, etc. By eliminating the fixed relationship between the hardware and the operating system, relying on the network connectivity for unified resource scheduling, and then providing the required virtual resources and services, it is a new type of IT and software delivery model, with characteristics such as flexibility, elasticity, distribution, multi-tenancy, and on-demand.

[0106] The memory in the embodiments of the present application is used to store various types of data to support the operation of the electronic device. Examples of these data include: any computer program for operating on the electronic device.

[0107] It can be understood that the memory can be a volatile memory or a non-volatile memory, or can include both volatile and non-volatile memories. Among them, the non-volatile memory can be a read-only memory (ROM, Read Only Memory), a programmable read-only memory (PROM, Programmable Read-Only Memory), an erasable programmable read-only memory (EPROM, Erasable Programmable Read-Only Memory), an electrically erasable programmable read-only memory (EEPROM, Electrically Erasable Programmable Read-Only Memory), a ferromagnetic random access memory (FRAM, ferromagnetic random access memory), a flash memory (Flash Memory), a magnetic surface memory, an optical disc, or a compact disc read-only memory (CD-ROM, Compact Disc Read-Only Memory); the magnetic surface memory can be a disk memory or a tape memory. The volatile memory can be a random access memory (RAM, Random Access Memory), which is used as an external cache. By way of example but not limitation, many forms of RAM are available, such as a static random access memory (SRAM, Static Random Access Memory), a synchronous static random access memory (SSRAM, Synchronous Static Random Access Memory), a dynamic random access memory (DRAM, Dynamic Random Access Memory), a synchronous dynamic random access memory (SDRAM, Synchronous Dynamic Random Access Memory), a double data rate synchronous dynamic random access memory (DDR SDRAM, Double Data Rate Synchronous Dynamic Random Access Memory), an enhanced synchronous dynamic random access memory (ESDRAM, Enhanced Synchronous Dynamic Random Access Memory), a synchronous link dynamic random access memory (SLDRAM, SyncLink Dynamic Random Access Memory), a direct rambus random access memory (DRRAM, Direct Rambus Random Access Memory). The memory described in the embodiments of the present application is intended to include but not limited to these and any other suitable types of memory.

[0108] The method disclosed in the embodiments of the present application can be applied to a processor or implemented by a processor. The processor may be an integrated circuit chip with signal processing capabilities. During implementation, the steps of the above method can be completed by the integrated logic circuit in the hardware of the processor or instructions in software form. The above-mentioned processor may be a general-purpose processor, a DSP, or other programmable logic devices, discrete gate or transistor logic devices, discrete hardware components, etc. The processor can implement or execute the various methods, steps, and logic block diagrams disclosed in the embodiments of the present application. The general-purpose processor may be a microprocessor or any conventional processor, etc. Combining the steps of the method disclosed in the embodiments of the present application can be directly embodied as being executed and completed by a hardware decoding processor, or executed and completed by a combination of hardware and software modules in the decoding processor. The software module may be located in a storage medium, and this storage medium is located in the memory. The processor reads the program in the memory and combines its hardware to complete the steps of the foregoing method.

[0109] Optionally, when the processor executes the program, it implements the corresponding processes implemented by the electronic device in the various methods of the embodiments of the present application. For the sake of brevity, they will not be elaborated here.

[0110] In an exemplary embodiment, the embodiments of the present application further provide a storage medium, that is, a computer storage medium, specifically a computer-readable storage medium, such as a first memory storing a computer program. The above computer program can be executed by the processor of the electronic device to complete the steps of the foregoing method. The computer-readable storage medium may be a FRAM, ROM, PROM, EPROM, EEPROM, Flash Memory, magnetic surface memory, optical disc, or CD-ROM, etc.

[0111] In several embodiments provided by the present application, it should be understood that the disclosed devices, electronic devices, and methods can be implemented in other ways. The device embodiments described above are only illustrative. For example, the division of the units is only a logical function division. In actual implementation, there may be other division methods, such as: multiple units or components can be combined, or can be integrated into another system, or some features can be ignored, or not executed. In addition, the coupling, direct coupling, or communication connection between the various components shown or discussed with each other may be through some interfaces, and the indirect coupling or communication connection of devices or units may be electrical, mechanical, or other forms.

[0112] The units described above as separate components may or may not be physically separated. The components shown as units may or may not be physical units, that is, they may be located in one place or distributed over multiple network units. Some or all of the units can be selected according to actual needs to achieve the purpose of the solution of this embodiment.

[0113] In addition, in each embodiment of the present application, all the functional units may be integrated in one processing unit, or each unit may be separately regarded as a unit, or two or more units may be integrated in one unit. The above integrated units may be implemented in the form of hardware, or in the form of a combination of hardware and software functional units.

[0114] Those of ordinary skill in the art can understand that all or part of the steps of implementing the above method embodiments can be completed by hardware related to program instructions. The foregoing program can be stored in a computer-readable storage medium. When the program is executed, it performs the steps including the above method embodiments. The foregoing storage medium includes various media that can store program codes, such as removable storage devices, ROM, RAM, magnetic disks, or optical discs.

[0115] Alternatively, if the above integrated units of the present application are implemented in the form of software functional modules and sold or used as independent products, they can also be stored in a computer-readable storage medium. Based on this understanding, the technical solution of the embodiments of the present application, in essence or the part that contributes to the related art, can be embodied in the form of a software product. The computer software product is stored in a storage medium and includes several instructions to enable a computer device (which can be a personal computer, a server, or a network device, etc.) to execute all or part of the methods described in the various embodiments of the present application. The foregoing storage medium includes various media that can store program codes, such as removable storage devices, ROM, RAM, magnetic disks, or optical discs.

[0116] In an exemplary embodiment, the embodiments of the present application also provide a computer program product, including a computer program, which can be executed by a processor of an electronic device to complete the steps of the method for optimizing the energy response of a GM counter tube in the embodiments of the present application.

[0117] It should be noted that the technical solutions described in the embodiments of the present application can be combined arbitrarily without conflict.

[0118] In addition, in the examples of the present application, "first", "second", etc. are used to distinguish similar objects and do not necessarily need to describe a specific order or sequence.

[0119] As described above, it is only the specific implementation manner of this application, but the protection scope of this application is not limited thereto. Any person skilled in the art within the technical scope disclosed by this application can easily think of changes or substitutions, which should all be covered within the protection scope of this application. Therefore, the protection scope of this application shall be subject to the protection scope of the claimed rights.

Claims

1. A method for optimizing the energy response of a GM counter tube, characterized in that, Including: Respectively determine the energy response curves of GM counters including different energy response compensation sleeves, where the different energy response compensation sleeves are obtained by combining different material types, different material thicknesses, and different coverage areas, and the coverage area is the area where the energy response compensation sleeve covers the sensitive area of the GM counter; Determine the target energy response compensation sleeve according to the energy response curves corresponding to the GM counters with different energy response compensation sleeves.

2. The method according to claim 1, wherein The step of determining the target energy response compensation sleeve according to the energy response curves corresponding to the GM counters with different energy response compensation sleeves includes: Determine the average value of the differences between the counting rates corresponding to different energies in each energy response curve and the preset counting rate; Determine the energy response compensation sleeve corresponding to the energy response curve with the smallest average value as the target energy response compensation sleeve.

3. A radiation dose detector, characterized in that, Including: A GM counter, a main control circuit, a signal acquisition circuit, and a trigger circuit, where the GM counter includes the target energy response compensation sleeve as described in claim 1; The GM counter is used to detect gamma rays in the environment and generate a current pulse signal; The signal acquisition circuit is used to convert the current pulse signal generated by the GM counter into a voltage pulse signal; The trigger circuit is used to convert the voltage pulse signal into a level signal and send it to the main control circuit; The main control circuit is used to determine the radiation dose rate according to the received level signal.

4. The radiation dose detector according to claim 3, characterized in that, The radiation dose detector further includes: a range switching circuit; The GM counter includes: a high-range GM counter and a low-range GM counter; The range switching circuit is used to control the on and off of the high-range GM counter and the low-range GM counter.

5. The radiation dose detector according to claim 4, characterized in that, The range switching circuit includes at least two optoelectronic relays.

6. The radiation dose detector according to claim 3, wherein, The radiation dose detector further includes: a high-voltage power supply; The high-voltage power supply is used to provide a working voltage for the GM counter.

7. The radiation dose detector according to claim 3, characterized in that, The radiation dose detector further includes: an alarm circuit; The main control module is used to control the alarm circuit to give an alarm when the radiation dose rate exceeds the threshold.

8. A computer program product, comprising a computer program, characterized in that, When the computer program is executed by a processor, it implements the steps of the energy response optimization method of the GM counter described in any one of claims 1-2.

9. An electronic device, comprising a memory, a processor, and a computer program stored in the memory and executable on the processor, characterized in that, When the processor executes the computer program, it implements the energy response optimization method of the GM counter described in any one of claims 1 to 2.

10. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores a computer program, and the computer program includes program instructions, and when the program instructions are executed by a processor, the processor executes the energy response optimization method of the GM counter described in any one of claims 1 to 2.

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