Gamma radiation measuring instrument and gamma radiation measuring method

By employing a combination of an ionization chamber and a GM counter tube in the gamma radiation measuring instrument, along with differential signal transmission and dual power supply redundancy design, the problem of electromagnetic interference affecting gamma radiation measuring instruments in nuclear power plants has been solved, achieving a highly reliable and economical nuclear radiation measurement solution.

CN121522705APending Publication Date: 2026-02-13JIANGSU NUCLEAR POWER CORP
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Patent Information

Application Number
CN202511525462.X
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2025-10-24
Publication Date
2026-02-13

AI Technical Summary

Technical Problem

Existing gamma radiation measurement instruments in nuclear power plants are susceptible to electromagnetic interference, leading to false alarms and malfunctions, which affect the safety of nuclear power plants and are also costly.

Method used

An ionization chamber is used as the main measurement channel, and a GM counter tube is used as the auxiliary measurement channel. By combining differential signal transmission and dual power supply redundancy design, the influence of electromagnetic interference is reduced. The interference situation of the main channel is judged by the GM counter tube, and a judgment logic suitable for nuclear power plant sites is designed.

Benefits of technology

It improves the measurement reliability and stability of gamma radiation measuring instruments, reduces the risk of false alarms and malfunctions, ensures nuclear safety, and is economical.

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Abstract

The invention belongs to the technical field of gamma radioactive radiation measurement, and particularly relates to a gamma radiation measuring instrument and a gamma radiation measuring method. The gamma radiation measuring instrument comprises a primary instrument detection unit and a secondary instrument data processing unit. The primary instrument detection unit comprises an ionization chamber, a GM counting tube, a first high voltage, a second high voltage, a current amplification module, a pulse shaping module, a first differential conversion module, a second differential conversion module and a high voltage program control module. The secondary instrument data processing unit comprises a processor, a voltage frequency converter, a first differential reduction module, a power supply module, a second differential reduction module, a retort counting module and a relay output module. The ionization chamber is used as a main measurement channel, and the GM counting tube is used as an auxiliary measurement channel, so that the technical problem of how to improve the measurement reliability and stability of the radiation measurement instrument is solved.
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Description

TECHNICAL FIELD

[0001] The application belongs to the technical field of gamma radiation measurement, and particularly relates to a gamma radiation measuring instrument and a gamma radiation measuring method. BACKGROUND

[0002] The existing nuclear power plant main control room operation personnel habitability judgment is mainly based on the measurement results of the radioactivity level of the fresh air inlet of the main control room. When the radioactivity level of the fresh air is high and reaches the set radioactivity threshold, the safety-related system will be automatically started, mainly including switching to internal circulation ventilation or operating the ventilation filter or enabling the emergency ventilation system. Most of the domestic nuclear power plant main control room ventilation habitability judgment uses a single radioactivity measuring instrument for direct interlocking action, which requires that the stability of the fresh air radioactivity measuring instrument must be high. However, the gamma radiation measurement using an ionization chamber detector is a weak current signal, which is easily affected by environmental static electricity and electromagnetic interference, and it is generally difficult to avoid false alarms and malfunctions. In 2020-2021, only domestic nuclear power plants have sent multiple nuclear power plant operation events caused by safety system malfunctions due to false alarms of such instruments, which may cause public panic and have a negative impact on nuclear safety.

[0003] How to improve the measurement reliability and stability of radiation measuring instruments has always been the focus of research by technical personnel at home and abroad. The following difficulties exist: Using an ionization chamber type detector for measurement has a high range, is resistant to high temperature, and is easy to pass nuclear level identification, but is very susceptible to electromagnetic interference; Using a scintillator type detector for measurement has good light emission efficiency and high detection efficiency, but the scintillator detector is not resistant to high temperature and is difficult to pass nuclear level identification; Using a semiconductor type detector for measurement is limited by process technology, silicon detection crystals cannot be made large, high frequency vibration has interference, and germanium crystals must work at liquid nitrogen temperature; According to the fault safety principle of nuclear power plants, the alarm output relay of the radiation instrument is designed to be lost power flip, and when a loss of power failure occurs, the alarm relay should trigger the safety system action, which puts very high requirements on the power supply line and power module; Improving the interlocking logic of a single radiation instrument to 3 out of 2 or 4 out of 2 interlocking voting logic requires an additional two to three instruments for a single unit, with a cost of nearly one million yuan. SUMMARY

[0004] Therefore, the application provides a gamma radiation measuring instrument and a gamma radiation measuring method, which use an ionization chamber as a main measurement channel and a GM counter tube as an auxiliary measurement channel to solve the technical problem of how to improve the measurement reliability and stability of radiation measuring instruments.

[0005] The first aspect of the application provides a gamma radiation measuring instrument, which comprises a primary instrument detection unit and a secondary instrument data processing unit. The primary instrument detection unit comprises an ionization chamber, a GM counter tube, a first high voltage, a second high voltage, a current amplification module, a pulse shaping module, a first differential conversion module, a second differential conversion module and a high voltage process control module. The secondary instrument data processing unit comprises a processor, a voltage frequency converter, a first differential restoration module, a power supply module, a second differential restoration module, a discrimination counting module and a relay output module. The power supply module is used to supply power to the high voltage process control module; the main measurement channel of the gamma ray is a channel in which the high voltage process control module, the first high voltage, the ionization chamber, the current amplification module, the first differential conversion module, the first differential restoration module and the voltage frequency converter are sequentially connected; the auxiliary measurement channel of the gamma ray is a channel in which the high voltage process control module, the second high voltage, the GM counter tube, the pulse shaping module, the second differential conversion module, the second differential restoration module and the discrimination counting module are sequentially connected; The processor is connected with the high voltage process control module, the voltage frequency converter, the discrimination counting module and the relay output module, is used to receive the pulse frequency signal transmitted by the voltage frequency converter, convert the pulse frequency signal into a corresponding radiation dose rate signal, receive the standard voltage pulse signal transmitted by the discrimination counting module and count, and drive the action of the relay output module according to the radiation dose rate signal and the standard voltage pulse signal.

[0006] In one specific embodiment of the application, the secondary instrument data processing unit further comprises a relay output module, an analog output module, a serial output module and an audible and visual display module. The processor is connected with the relay output module, the analog output module, the serial output module and the audible and visual display module, and is used to transmit the radiation dose rate signal to the analog output module, the serial output module and the audible and visual display module.

[0007] In one specific embodiment of the application, the power supply module comprises a first power supply module, a second power supply module, a battery module and a low-voltage power supply module. One side of the low-voltage power supply module is connected with the first power supply module, the second power supply module and the battery module, and the other side of the low-voltage power supply module is connected with the high voltage process control module. The first power supply module, the second power supply module and the battery module are used to supply power to the low-voltage power supply module. The low-voltage power supply module is used to supply power to the high voltage process control module.

[0008] The second aspect of the application provides a gamma radiation measuring method, which comprises: In step S10, in the continuous measurement mode, when the measurement value of the main channel ionization chamber exceeds the set alarm threshold value, the measurement value of the GM counter tube is checked; In step S20, if the measurement value of the GM counter tube exceeds the set multiple of the background value, it is judged that the data measured by the measuring device is real and reliable, and the action of the over-threshold alarm relay is triggered. Step S30, if the measured value of the GM counter tube does not exceed the background value by a set multiple, it is determined that the data measured by the measuring device is not reliable, it is considered that the instrument is disturbed or has a fault, the threshold value alarm relay does not act, the fault alarm is automatically triggered, and the maintenance mode is entered.

[0009] In one specific embodiment of the present application, before step S10, the gamma radiation measurement method further comprises: Step S1, when the gamma radiation measurement instrument of the present application has the operating conditions, the gamma radiation measurement instrument is powered on, and after being powered on, a self-checking program is automatically started, mainly to detect whether the GPIO pin state of the power module and the processor is correct and to initialize the measurement program; Step S2, if the self-checking fails, the gamma radiation measurement instrument triggers a fault alarm signal; Step S3, after the self-checking passes, the continuous measurement mode is entered.

[0010] The third aspect of the present application provides a computer device, which comprises a processor and a memory. The processor is used to execute the gamma radiation measurement method of the second aspect of the present application. The memory is used to store the executable instructions of the processor.

[0011] The fourth aspect of the present application provides a computer readable storage medium, which stores the executable instructions of the computer. The executable instructions are executed by the processor to realize the gamma radiation measurement method of the second aspect of the present application.

[0012] The fifth aspect of the present application provides a computer program product, which comprises computer programs / instructions, and the computer programs / instructions are executed by the processor to realize the gamma radiation measurement method of the second aspect of the present application.

[0013] The beneficial effects of the technical solution of the present application are that the strong output signal of the GM counter tube is used as an auxiliary measurement channel to judge the interference condition of the ionization chamber in the low range and weak signal interval of the main channel, and a judgment logic suitable for the nuclear power site environment is designed, which effectively reduces the risk of misoperation of the interlocked equipment caused by false alarm of the instrument device. The gamma radiation measurement instrument is suitable for the use place of the nuclear radiation measurement instrument in the nuclear power station, nuclear chemical industry, and nuclear environmental protection industry, and is a safe, stable, economical, and reliable effective solution for site radioactive level measurement and automatic interlocking. BRIEF DESCRIPTION OF DRAWINGS

[0014] Figure 1 Fig. 1 shows a schematic diagram of the internal hardware connection of a gamma radiation measurement instrument provided by an embodiment of the present application.

[0015] Figure 2 Fig. 2 shows a flowchart of a gamma radiation measurement method provided by an embodiment of the present application.

[0016] Figure 3 Fig. 1 is a flow diagram of a method for measuring gamma radiation according to another embodiment of the present application.

[0017] In the figure, 1 is an ionization chamber, 2 is a GM counter tube, 3 is a first high voltage, 4 is a second high voltage, 5 is a current amplification module, 6 is a pulse shaping module, 7 is a first differential conversion module, 8 is a second differential conversion module, 9 is a high voltage program control module, 10 is a processor, 11 is a voltage frequency converter, 12 is a first differential reduction module, 13 is a second differential reduction module, 14 is a discrimination counting module, 15 is a first power supply module, 16 is a second power supply module, 17 is a battery module, 18 is a low voltage power supply module, 19 is a relay output module, 20 is an analog output module, 21 is a serial output module, and 22 is an audible and visual display module. DETAILED DESCRIPTION

[0018] In view of the actual needs, a gamma radiation measuring instrument is designed in accordance with the requirements of nuclear safety regulations and standards in China from the aspects of safety and economy, so as to improve the accuracy of radiation measurement, reduce the cost of measuring equipment, avoid the misoperation of the safety system, and further ensure nuclear safety.

[0019] The technical solutions in the embodiments of the present application will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only part of the embodiments of the present application, rather than all the embodiments. Based on the embodiments in the present application, all other embodiments obtained by those skilled in the art without creative work fall within the scope of the present application.

[0020] At least one embodiment of the present application provides a gamma radiation measuring instrument, which is suitable for high reliability places. Referring to Figure 1 The gamma radiation measuring instrument includes a primary instrument detection unit ( Figure 1 the device in the lower dashed box) and a secondary instrument data processing unit ( Figure 1The primary measurement channel of the gamma ray is a channel in which the high-voltage program control module 9, the first high voltage 3, the ionization chamber 1, the current amplification module 5, the first differential conversion module 7, the first differential restoration module 12 and the voltage frequency converter 11 are sequentially connected; and the auxiliary measurement channel of the gamma ray is a channel in which the high-voltage program control module 9, the second high voltage 4, the GM counter tube 2, the pulse shaping module 6, the second differential conversion module 7, the second differential restoration module 13 and the discrimination counting module 14 are sequentially connected. The processor 10 is connected with the high-voltage program control module 9, the voltage frequency converter 11, the discrimination counting module 14 and the relay output module 19, is used for receiving the pulse frequency signal transmitted by the voltage frequency converter 11, converting the pulse frequency signal into a corresponding radiation dose rate signal, receiving the standard voltage pulse signal transmitted by the discrimination counting module 14 and counting, and driving the action of the relay output module 19 according to the radiation dose rate signal and the standard voltage pulse signal.

[0021] It should be noted that the first high voltage 3 is used to supply high voltage to the ionization chamber 1. The second high voltage 4 is used to supply high voltage to the GM counter tube 2. The processor 10 can be a single-chip microcomputer.

[0022] The current amplification module 5 is used for signal amplification and conversion of the current signal formed in the ionization chamber 1 when the gamma ray passes through the ionization chamber 1 into a single-ended voltage signal. The first differential conversion module 7 is used for converting the single-ended voltage signal into a differential voltage signal. The processor 10 is connected with the high-voltage program control module 9 and the voltage frequency converter 11, is used for controlling the high-voltage program control module 9 to drive the first high voltage 3 according to the program control logic; receiving the pulse frequency signal transmitted by the voltage frequency converter 11, converting the pulse frequency signal into a corresponding radiation dose rate signal, and generating a fault alarm signal according to the radiation dose rate signal.

[0023] The pulse shaping module 6 is used to receive the measured pulse voltage signal formed at both ends of the electrode of the GM counter tube 2 when the gamma rays pass through the GM counter tube 2 and convert the measured pulse voltage signal into a standard square wave voltage signal and transmit the standard square wave voltage signal to the second differential conversion module 8. The second differential conversion module 8 is used to convert the single-ended voltage signal into a differential voltage signal and transmit the differential voltage signal to the second differential restoration module 13 through a cable. The second differential restoration module 13 is used to convert the differential voltage signal into a single-ended voltage measurement signal and transmit the single-ended voltage measurement signal to the discrimination counting module 14. The discrimination counting module 14 is used to convert the single-ended voltage measurement signal into a standard voltage pulse signal proportional to the intensity of the gamma rays received by the GM counter tube and directly transmit the standard voltage pulse signal to the processor 10. The processor 10 is connected with the discrimination counting module 14 and is used to receive the standard voltage pulse signal and count and control the high-voltage program-controlled module 9 to drive the second high voltage 4 according to the program-controlled logic and drive the action of the relay output module 19 according to the measured value and the high or low of the threshold value and the fault state.

[0024] In the above embodiment, when the gamma rays pass through the ionization chamber 1, ion-electron pairs are generated by ionization inside the ionization chamber, and under the high-voltage electric field environment inside the ionization chamber, the ion-electron pairs drift to both ends of the electrode of the ionization chamber, respectively, to form a current signal. The size of the current represents the strength of the gamma radiation level. The current signal is amplified by the current amplification module 5 and converted into a single-ended voltage signal, and the single-ended voltage signal is converted into a differential voltage signal by the first differential conversion module 7. The primary instrument detection unit and the secondary instrument data processing unit are far away from each other, and a signal cable is needed for signal transmission. The long cable is equivalent to an antenna and is the main source of electromagnetic interference. Therefore, through differential signal transmission, the common-mode electromagnetic interference signal received on the line can be completely shielded, the long-distance interference-free transmission of the measurement voltage signal of the ionization chamber 1 is realized, and thus the primary instrument detection unit and the secondary data processing unit can be flexibly arranged and installed far away from each other. The used detector and electronic modules have high performance-price ratio and have promotional value. After the differential voltage signal of the primary instrument detection unit is transmitted to the secondary instrument data processing unit, it is converted into a single-ended voltage signal by the first differential restoration module 12, and the single-ended voltage signal is converted into a pulse frequency signal proportional to the voltage signal by the voltage frequency converter 11. At this time, the current signal reflecting the gamma radiation level has been converted into a pulse frequency signal proportional to the current signal. The pulse frequency signal is directly sent to the GPIO collection counting pin of the processor 10 to realize automatic data collection and counting. In the processor 10, the pulse frequency signal is converted into a corresponding radiation dose rate signal through a conversion coefficient, and whether a fault occurs is determined according to the radiation dose rate signal. If a fault occurs, a fault alarm signal is triggered.

[0025] When the gamma rays pass through the GM counter tube 2, ionization generates ion-electron pairs in the GM counter tube 2. Due to the high voltage of the GM counter tube, one ion-electron pair in the GM counter tube 2 is accelerated by the high-voltage electric field to obtain a high kinetic energy, and then impacts the surrounding working gas to continue to generate the next generation of ion-electron pairs. The cycle continues to form an ionization avalanche of the gas in the GM counter tube 2, and a number of ion-electron pairs much higher than that of the ionization chamber is generated. Therefore, a strong amplitude measurement voltage signal is formed at the two electrodes of the GM counter tube 2, which can drive the electronic circuit without amplification. The measurement voltage signal of the GM counter tube 2 in the primary instrument detection unit is a single-ended voltage signal, which is converted into a differential measurement signal by the second differential conversion module 8 and transmitted to the secondary instrument data processing unit through a cable, so as to realize the long-distance and non-interference transmission of the measurement voltage signal of the GM counter tube 2. After the differential voltage signal of the primary instrument detection unit of the GM counter tube 2 on the site is transmitted to the secondary instrument data processing unit, it is converted into a single-ended voltage measurement signal by the second differential restoration module 13. The single-ended voltage measurement signal is filtered by the discrimination counting module 14 to remove the low-amplitude background noise signal and the high-amplitude environmental interference signal, so as to form a standard voltage pulse signal proportional to the intensity of the gamma rays received by the GM counter tube, and directly sent to the GPIO acquisition pin of the processor 10 to realize the automatic acquisition and counting of the measurement data of the GM counter tube 2.

[0026] In addition, in the above embodiment, the strong output signal of the GM counter tube 2 is used as an auxiliary measurement channel to judge the interference of the ionization chamber 1 in the low range and weak signal interval, and a judgment logic suitable for the nuclear power site environment is designed, which effectively reduces the risk of misoperation of the interlocked equipment caused by false alarm of the instrument device. The gamma radiation measuring instrument is suitable for the use place of the nuclear radiation measuring instrument in the nuclear power station, nuclear chemical industry and nuclear environmental protection industry, and is a safe, stable, economical and reliable effective solution for the measurement of the site radioactivity level and the automatic interlocking.

[0027] In at least one embodiment of the present application, the secondary instrument data processing unit further comprises an analog output module 20, a serial output module 21 and an audible and light display module 22. The processor 10 is connected with the analog output module 20, the serial output module 21 and the audible and light display module 22, and is used for transmitting the radiation dose rate signal to the analog output module 20, the serial output module 21 and the audible and light display module 22.

[0028] In at least one embodiment of the present application, the power supply module includes a first power supply module 15, a second power supply module 16, a battery module 17 and a low-voltage power supply module 18. One side of the low-voltage power supply module 18 is connected with the first power supply module 15, the second power supply module 16 and the battery module 17, and the other side of the low-voltage power supply module 18 is connected with the high-voltage program control module 9. The first power supply module 15, the second power supply module 16 and the battery module 17 are used to supply power to the low-voltage power supply module 18. The low-voltage power supply module 18 is used to supply power to the high-voltage program control module 9.

[0029] Specifically, the first power supply module 15, the second power supply module 16 and the battery module 17 are simultaneously connected with the commercial alternating current 220V power supply line. When the commercial power is normal, the first power supply module 15 and the second power supply module 16 simultaneously supply power to the instrument device and realize hot standby with each other. When one of the first power supply module 15 and the second power supply module 16 fails, the instrument automatically triggers a fault alarm. When the first power supply module 15 and the second power supply module 16 fail at the same time, the battery module 17 will automatically supply power to the low-voltage power supply module 18 without disturbance, ensuring that the instrument can continue to work for 0.5 hours, and at the same time, the instrument automatically triggers a fault alarm.

[0030] During normal operation of the instrument device, the first power supply module 15, the second power supply module 16 and the battery module 17 are first put into operation. After the power supply is normal, the processor 10 starts the GPIO pin self-check and program initialization. After confirming that there is no fault, the low-voltage power supply module 18 supplies power to the high-voltage program control module 9. After the high-voltage program control module 9 is powered on, it drives the first high-voltage 3 and the second high-voltage 4 according to the program control logic. The first high-voltage 3 supplies high voltage to the ionization chamber 1, and the second high-voltage 4 supplies high voltage to the GM counter tube 2, ensuring that the ionization chamber 1 and the GM counter tube 2 work independently at high voltage, avoiding common cause failure.

[0031] In the above embodiment, double power supply modules are used as hot standby, and an emergency fault battery module is configured, that is, the instrument device is configured with triple redundant power supply, so that common cause failure of the instrument power supply can be effectively prevented, and false operation in the fault safety mode caused by power failure of the instrument can be avoided, and false operation of the interlocking equipment caused by the fault relay output module 19 due to power failure can be avoided, thereby improving the stability of the instrument. At the same time, the interference noise decoupling principle of the differential circuit is ingeniously used to eliminate the interference introduced by the transmission line.

[0032] It should be noted that the gamma radiation measuring instrument strictly follows the relevant standards of nuclear power plants, and the technical specifications followed are as follows: HAF003 Nuclear Power Plant Quality Assurance Safety Regulations HAF102 Safety Regulations for Nuclear Power Plant Design GB-T15475-1995 Quality Assurance Classification of Nuclear Power Plant Instruments and Control Systems and Their Power Supply Equipment GB 4793.1-2007 Safety requirements for electrical measurements, controlgear and laboratory equipment - Part 1: General requirements.

[0033] The gamma radiation measuring method is executed by the processor in the gamma radiation measuring instrument in the above embodiment. Referring to Figure 2 , the gamma radiation measuring method comprises the following steps.

[0034] In step S10, in the continuous measurement mode, the measurement value of the main channel ionization chamber 1 is checked when the measurement value exceeds the set alarm threshold value.

[0035] It should be noted that the measurement value of the main channel ionization chamber 1 is the radiation dose rate signal. The measurement value of the GM counter tube 2 is the standard voltage pulse signal count and its equivalent dose rate value.

[0036] In step S20, if the measurement value of the GM counter tube 2 exceeds the set multiple of the background value, it is determined that the data measured by the measuring device is reliable, and the over-threshold alarm relay is triggered to act.

[0037] It should be noted that the set multiple of the background value of the GM counter tube 2 can be slightly lower than the setting value of the instrument device, and can be reasonably adjusted according to the environmental background. The relay output module 19 can be referred to as a relay.

[0038] In step S30, if the measurement value of the GM counter tube 2 does not exceed the set multiple of the background value, it is determined that the data measured by the measuring device is not reliable, and it is considered that the instrument is disturbed or has a fault, the over-threshold alarm relay does not act, and the fault alarm is automatically triggered, and the maintenance mode is entered.

[0039] It should be noted that the maintenance mode can notify the maintenance personnel to check and maintain on site. The GM counter tube 2 can be referred to as a GM tube.

[0040] In at least one embodiment of the present application, before step S10, the gamma radiation measuring method further comprises steps S1 to S3.

[0041] In step S1, when the gamma radiation measuring instrument of the present application has the operating conditions, the gamma radiation measuring instrument is powered on, and after power-on, the self-checking program is automatically started, mainly to detect whether the GPIO pin state of the power module and the processor 10 is correct and initialize the measurement program.

[0042] In step S2, if the self-checking fails, the gamma radiation measuring instrument will trigger a fault alarm signal.

[0043] In step S3, after the self-checking passes, the continuous measurement mode is entered.

[0044] It should be noted that the remote transmission of the fault signal can be further realized by a fault state relay or a serial port as needed.

[0045] Since the GM counter tube 2 has a small volume and cannot be made large, the detection efficiency is low, and the range is limited, and it cannot completely cover the measurement range of the ionization chamber, so the GM counter tube 2 is used as an auxiliary measurement channel, and the ionization chamber 1 is used as a main measurement channel. When there is strong electromagnetic interference in the operating environment of the instrument, the first differential conversion module, the second differential conversion module 8, the first differential restoration module 12, the second differential restoration module 13 and other modules can completely shield the electromagnetic interference signals received through the cable, but cannot shield the electromagnetic interference received from the detector segment. The avalanche effect of the GM counter tube 2 caused by ionizing radiation will generate a higher amplitude measurement voltage signal, which is several orders of magnitude stronger than the measurement signal amplitude of the ionization chamber 1, and has much stronger resistance to environmental electromagnetic interference, so it can be used as a reference criterion for the ionization chamber 2 to measure whether it is disturbed in the low range and weak signal stage. The judgment process is shown in Figure 3 .

[0046] In the above embodiment, a judgment logic suitable for the nuclear power site environment is designed, and only through self-checking and confirmation can a real alarm be output, thereby effectively reducing the risk of misoperation of interlocked equipment caused by false alarms of the instrument device.

[0047] At least one embodiment of the present application also provides a computer device, which comprises a processor and a memory. The processor is used to execute the gamma radiation measurement method provided by any one of the above embodiments of the present application. The memory is used to store executable instructions of the processor, such as an application program. The number of processors can be one or more. The application program stored in the memory can include one or more than one module corresponding to a set of instructions. In addition, the processor is configured to execute the instructions to execute the above gamma radiation measurement method.

[0048] The computer device can also include a power supply component configured to manage the power supply of the computer device, a wired or wireless network interface configured to connect the computer device to a network, and an input / output (I / O) interface. The computer device can operate based on an operating system stored in the memory, such as Windows Server TM , Mac OSX TM , Unix TM , Linux TM , FreeBSD TM or the like.

[0049] The computer readable storage medium stores computer executable instructions. The computer executable instructions are executed by the processor to implement the gamma radiation measurement method provided by any of the embodiments of the present application.

[0050] The non-transitory computer readable storage medium stores instructions. The instructions are executed by the processor of the computer device to enable the computer device to perform the gamma radiation measurement method. The gamma radiation measurement method is performed by an agent program.

[0051] Those skilled in the art can appreciate that the algorithm steps of each example described in combination with the embodiments disclosed in the present application can be implemented in electronic hardware or a combination of computer software and electronic hardware. Whether the functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. The skilled person can use different methods to implement the described functions for each specific application, but such implementation should not be considered beyond the scope of the present application.

[0052] The computer program product includes computer program / instructions. The computer program / instructions are executed by the processor to implement the gamma radiation measurement method provided by any of the embodiments of the present application.

[0053] The above functions, if implemented in the form of software function units and sold or used as independent products, can be stored in a computer readable storage medium. Based on this understanding, the technical solutions of the present application or the part of the technical solutions that essentially contribute to the prior art can be embodied in the form of a computer program product stored in a storage medium, including a plurality of instructions for causing a computer device (which can be a personal computer, a server, or a network device, etc.) to execute all or part of the steps of the gamma radiation measurement method of the embodiments of the present application. The aforementioned storage medium includes: a U disk, a mobile hard disk, a read-only memory (ROM), a random access memory (RAM), a magnetic disk or an optical disk, and various program code storage media.

[0054] It should be noted that the combination of the technical features in the embodiments of the present application is not limited to the combination described in the embodiments of the present application or the combination described in the specific embodiments. All the technical features described in the present application can be freely combined or combined, unless contradictory.

[0055] As used in this application and the appended claims, the singular forms "a," "an," and "the" include plural referents unless the context clearly dictates otherwise. Thus, for example, reference to "a" or "the" element or steps includes one or more of them, and reference to "the" method includes the methods described herein and equivalents thereof. Similarly, the words "comprise," "comprises," and "comprising," and the like, when used in this application and the appended claims, can have the meaning ascribed to them in U.S. patent law, i.e., they are used in the sense of "include" and not in the sense of "consist of." The use of any and all examples, or exemplary language (e.g., "for instance," "for example," "e.g.,") provided herein, is intended merely to better illuminate the application and does not pose a limitation on the scope of the application unless otherwise indicated. No language is intended to indicate that the application will not also encompass only those systems recited in the claims.

[0056] The terms "first," "second," and the like, do not imply any relative importance, but can be used merely to number various elements. Thus, a feature defined with "first," "second," etc., can include one or more of the features implicitly or explicitly.

[0057] The foregoing is considered as illustrative only of the principles of the application. Further, since numerous modifications and changes will readily occur to those skilled in the art, it is not desired to limit the application to the exact construction and practice described. Accordingly, all such variations are intended to be included within the scope of the present application as defined in the following claims.

Claims

1. A gamma radiation survey meter, characterized in that, The primary instrument detection unit comprises an ionization chamber, a GM counter tube, a first high voltage, a second high voltage, a current amplification module, a pulse shaping module, a first differential conversion module, a second differential conversion module, and a high voltage process control module. The secondary instrument data processing unit comprises a processor, a voltage frequency converter, a first differential reduction module, a power supply module, a second differential reduction module, a discrimination counting module, and a relay output module. The power supply module is configured to supply power to the high voltage process control module.

2. A gamma radiation survey meter according to claim 1, characterised in that The processor is connected to the high voltage process control module, the voltage frequency converter, the discrimination counting module, and the relay output module.

3. A gamma radiation measuring instrument according to claim 1 or 2, characterised in that, The processor is configured to receive a pulse frequency signal transmitted by the voltage frequency converter, convert the pulse frequency signal into a corresponding radiation dose rate signal, receive a standard voltage pulse signal transmitted by the discrimination counting module, count the standard voltage pulse signal, and drive the relay output module to act according to the radiation dose rate signal and the standard voltage pulse signal.

4. A method of measuring gamma radiation, characterized by, The secondary instrument data processing unit further comprises an analog output module, a serial output module, and an audible and visual display module. The processor is connected to the analog output module, the serial output module, and the audible and visual display module. The power supply module comprises a first power supply module, a second power supply module, a battery module, and a low-voltage power supply module. The low-voltage power supply module is connected to the first power supply module, the second power supply module, and the battery module on one side, and is connected to the high voltage process control module on the other side.

5. A method of measuring gamma radiation according to claim 4, characterised in that, The first power supply module, the second power supply module, and the battery module are configured to supply power to the low-voltage power supply module. The low-voltage power supply module is configured to supply power to the high voltage process control module. The processor is configured to execute the following steps: In step S10, in the continuous measurement mode, when the measurement value of the ionization chamber of the main channel exceeds the set alarm threshold, the measurement value of the GM counter tube is checked. In step S20, if the measurement value of the GM counter tube exceeds the set multiple of the background value, it is determined that the data measured by the measurement device is reliable, and the threshold alarm relay output module is triggered to act. In step S30, if the measurement value of the GM counter tube does not exceed the set multiple of the background value, it is determined that the data measured by the measurement device is not reliable, and it is considered that the instrument is disturbed or has a fault, the threshold alarm relay output module does not act, the fault alarm is automatically triggered, and the maintenance mode is entered. Before step S10, the following steps are further included: Step S1, when the gamma radiation measuring instrument of the embodiment of the present application has the operating condition, the gamma radiation measuring instrument is powered on, and after the power-on, a self-checking program is automatically started, mainly to detect whether the GPIO pin state of the power module and the processor is correct and to initialize the measurement program; Step S2, if the self-checking does not pass, the gamma radiation measuring instrument will trigger a fault alarm signal; Step S3, after the self-checking passes, the continuous measurement mode is entered.

6. A computer apparatus, comprising: Comprise: A processor for executing a gamma radiation measurement method according to claim 4 or 5; And A memory for storing executable instructions of the processor.

7. A computer readable storage medium having stored thereon executable instructions of a computer, characterized in that, The executable instructions are executed by the processor to realize the gamma radiation measurement method according to claim 4 or 5.

8. A computer program product comprising computer programs / instructions, characterized in that, The computer program / instructions are executed by the processor to realize the gamma radiation measurement method according to claim 4 or 5.