CN114167473A - Complex environment personal dose equivalent measuring system - Google Patents

Complex environment personal dose equivalent measuring system Download PDF

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CN114167473A
CN114167473A CN202111442064.3A CN202111442064A CN114167473A CN 114167473 A CN114167473 A CN 114167473A CN 202111442064 A CN202111442064 A CN 202111442064A CN 114167473 A CN114167473 A CN 114167473A
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dose
radiation monitor
data
radiation
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姚剑锋
李志刚
黎鹏
曹扬
李杉
张宪文
陈永祥
王倩
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Chengdu Tianhe Technology Co ltd
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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/02—Dosimeters
    • G01T1/026—Semiconductor dose-rate meters
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16—Measuring radiation intensity
    • G01T1/161—Applications in the field of nuclear medicine, e.g. in vivo counting
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16—Measuring radiation intensity
    • G01T1/24—Measuring radiation intensity with semiconductor detectors
    • G01T1/248—Silicon photomultipliers [SiPM], e.g. an avalanche photodiode [APD] array on a common Si substrate
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00—Measuring neutron radiation
    • G01T3/08—Measuring neutron radiation with semiconductor detectors
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T7/00—Details of radiation-measuring instruments
    • G01T7/12—Provision for actuation of an alarm

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Abstract

The invention discloses a complex environment personal dose equivalent measuring system, which comprises a radiation monitor, a data reading device and a data management system, wherein the data reading device is connected with the radiation monitor and is used for acquiring dose data of the radiation monitor and uploading the dose data to the data management system; the radiation monitor comprises a gamma radiation monitor and an n-gamma radiation monitor; the data management system is used for providing user registration, equipment management, dose analysis, energy spectrum presentation and alarm records, and further comprises a network transmission module, the radiation monitor is connected with the data management system through the network transmission module, and the network transmission module adopts 4G/5G and Beidou transmission. The invention can carry out comprehensive safety monitoring on various aspects of personal irradiated radiation quantity, radionuclide species, real-time dose, dose equivalent rate and the like; and when the irradiated quantity exceeds a threshold value, giving an alarm for prompting.

Description

Complex environment personal dose equivalent measuring system
Technical Field
The invention relates to the technical field of nuclear radiation detection, in particular to a personal dose equivalent measuring system in a complex environment.
Background
With the continuous development of nuclear technology, a large number of nuclear facilities with neutron activity, such as nuclear reactors, nuclear power plants, hash neutron sources, post-processing plants, military nuclear power plants and the like, are put into use, and these nuclear facilities simultaneously release (ionizing) radiation particles, such as alpha particles, beta particles, neutrons, gamma rays and the like, to the surrounding environment to form a complex nuclear radiation environment. Since the first reactor in the world was built up, many nuclear accidents have occurred around the world, and the consequences of these events are that the leaking radionuclide continues to produce (cause) ionizing radiation particles, causing irreversible radiation damage to personnel exposed to the surrounding environment. Therefore, in the operation process of nuclear facilities and possibly other radiation environments, the dose equivalent rate of the positions of workers needs to be monitored in real time, and the workers are reminded to evacuate in time when the radiation dose exceeds the standard.
The dosage instruments mainly used by the personal dosage monitoring system comprise a thermoluminescent dosemeter, a personal radiation alarm instrument, a direct-reading dosemeter and a matched data management system. The thermoluminescent dosimeter is the most basic measuring device, but cannot reflect the dosage rate, and needs matched equipment to read the accumulated dosage, while the personal radiation alarm instrument can only give an alarm at a rated threshold value; the dosage error of the direct-reading personal dosage product exceeds 30%, and the direct-reading personal dosage product only can provide data reference and alarm functions and cannot give accurate radiation dosage.
The neutron absorption dose versus photon fluence at any point in space is given by:
Figure BDA0003383708900000011
wherein
Figure BDA0003383708900000012
Is the photon number rate at the test point,
Figure BDA0003383708900000013
is the absorption coefficient of mass energy of air, EγIs the photon energy. As can be seen from the above formula, the absorbed dose D is related to only three quantities.
Currently, two types of detectors are mainly applied to a commonly used personal dosimeter: G-M tube, ion implantation type Si semiconductor detector. Both detectors have no energy resolving property and can only count rays, theoretically, dose measurement cannot be performed.
It has been found in dosimetry studies that many detectors tend to flatten the energy response to gamma radiation over a range of energies. If the requirement on the measurement precision is not high, the product of the air quality energy absorption coefficient and the photon energy in the formula can be regarded as a constant, then the absorbed dose is in direct proportion to the fluence rate, and further the dose monitoring is realized through counting.
The count-based dosimetry methods, even after energy compensation, still have large errors. Meanwhile, the existing n and gamma mixed radiation monitoring equipment on the market generally uses two detectors to respectively respond to neutrons and gamma rays, and the influence of a gamma background on neutron detection cannot be effectively avoided. The existing gamma personal dosimeter is a counting type dosimeter, can only provide an alarm function, and cannot accurately measure personal dose rate.
Disclosure of Invention
In order to solve the problems, the invention provides a complex environment personal dose equivalent measuring system which is used for evaluating the radiation dose level of personnel and realizing the functions of personnel data management, alarm prompt and the like, and the measuring system comprises a radiation monitor, a data reading device and a data management system, wherein the data reading device is connected with the radiation monitor and is used for acquiring the dose data of the radiation monitor and uploading the dose data to the data management system; the radiation monitor comprises a gamma radiation monitor and an n-gamma radiation monitor; the data management system is used for providing user registration, equipment management, dose analysis, energy spectrum presentation and alarm recording.
Specifically, the complex environment personal dose equivalent measurement system further comprises a network transmission module, the radiation monitor is connected with the data management system through the network transmission module, and the network transmission module adopts 4G/5G and Beidou transmission.
Specifically, the radiation monitor is connected with the data reading device through a wireless infrared module.
Specifically, the data reading device uploads data to the data management system in a USB communication manner.
Specifically, the gamma radiation monitor adopts a CLYC crystal, the CLYC crystal is coupled with SiPM through silicon oil, detected nuclear signals are converted into photoelectric signals, the photoelectric signals are converted into digital signals through a signal reading system at the rear end, pulse voltage amplitude values are obtained, an energy spectrum corresponding to a radioactive source is obtained according to mathematical statistics of the pulse amplitude values, and radiation dose equivalent data are obtained through G (E) weighting function operation, so that real-time monitoring is realized.
Specifically, the n-gamma radiation monitor adopts a GAGG crystal, the GAGG crystal is coupled with SiPM through silicone oil, detected nuclear signals are converted into photoelectric signals, the photoelectric signals are converted into digital signals through a signal reading system at the rear end, pulse voltage amplitude values are obtained, an energy spectrum corresponding to a radioactive source is obtained according to mathematical statistics of the pulse amplitude values, and radiation dose equivalent data are obtained through G (E) weighting function operation, so that real-time monitoring is realized.
Specifically, the gamma radiation monitor and the n-gamma radiation monitor both have an accumulated dose function: according to the real-time monitoring data, calculating and recording a deep personal dose equivalent HP (10) and a superficial personal dose equivalent HP (0.07) within the using time of a user, and meanwhile, screening and recording the irradiated radionuclide species through an n/gamma screening algorithm and calculating the cumulative dose amount and the dose equivalent rate of the personal radiation dose.
Specifically, the gamma radiation monitor and the n-gamma radiation monitor both have a dose alarm function: the dose threshold is set through real-time monitoring of radiation dose and monitoring of accumulated radiation dose, and when the dose data exceeds the dose threshold, the gamma radiation monitor and the n-gamma radiation monitor give an alarm in a sound or vibration mode.
The invention has the beneficial effects that: the comprehensive safety monitoring can be carried out on various aspects of personal irradiated radiation quantity, radionuclide species, real-time dose, dose equivalent rate and the like; and when the irradiated quantity exceeds a threshold value, giving an alarm for prompting.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the structures shown in the drawings without creative efforts.
FIG. 1 is a block diagram of the system of the present invention;
FIG. 2 is a schematic view of a gamma radiation monitor;
FIG. 3 is a schematic view of the n-gamma radiation monitor;
FIG. 4 is the shape of neutron and gamma-generated current pulses;
in the figure, 1-CLYC crystal, 2-BaSO43-aluminum shell, 4-silicon oil, 5-PN junction cathode, 6-PN junction anode and 7-GAGG crystal.
Detailed Description
In order to make the objects, technical solutions and advantages of the embodiments of the present invention clearer, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, but not all, embodiments of the present invention. The components of embodiments of the present invention generally described and illustrated in the figures herein may be arranged and designed in a wide variety of different configurations.
Thus, the following detailed description of the embodiments of the present invention, presented in the figures, is not intended to limit the scope of the invention, as claimed, but is merely representative of selected embodiments of the invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Some embodiments of the invention are described in detail below with reference to the accompanying drawings. The embodiments described below and the features of the embodiments can be combined with each other without conflict.
Example 1:
referring to fig. 1-3, in order to solve the problem that the traditional counting type personal dosimeter cannot accurately measure the dose, the invention designs a personal dose equivalent measuring system in a complex environment, which comprises a radiation monitor, a data reading device and a data management system, wherein the data reading device is connected with the radiation monitor and used for acquiring dose data of the radiation monitor and uploading the dose data to the data management system; the radiation monitor comprises a gamma radiation monitor and an n-gamma radiation monitor; the data management system is used for providing user registration, equipment management, dose analysis, energy spectrum presentation and alarm recording. The invention is used for evaluating the radiation dose level of personnel and realizing the functions of personnel data management, alarm prompt and the like.
Further, in this embodiment, the complex environment personal dose equivalent measurement system further includes a network transmission module, the radiation monitor is connected with the data management system through the network transmission module, and the network transmission module adopts 4G/5G and Beidou transmission. The 4G/5G and Beidou transmission are data transmission systems which are closed by default, the data transmission system can be actively started by using a network, and when the data transmission system is used for network data transmission, only the current monitored real-time dose and the accumulated dose record of the service time are uploaded; compared with infrared transmission, the 4G/5G and Beidou transmission more directly transmit data to a data management system, but have the defects of data leakage danger and power consumption increase, so that network data transmission is only used as a standby data transmission mode and is closed by default when not used.
Further, in this embodiment, the radiation monitor is connected to the data reading device through an infrared transmission device; the data reading device adopts an infrared data reader, infrared transmission is always in a standby state, and the infrared transmission device of the portable personal dose radiation monitor is activated when the portable personal dose radiation monitor (comprising a gamma radiation monitor and an n-gamma radiation monitor) approaches the infrared data reader. The using time, the dose equivalent rate, the irradiated radionuclide species, the radiation dose recorded in real time and the dose accumulated record in the using process are transmitted to an infrared data reader through an infrared transmitting and receiving tube on the portable personal dose radiation monitor, and the infrared data reader is transmitted to a data management system through a USB data interface.
Specifically, the theoretical principle of the gamma spectrometer is as follows: the secondary electrons generated by the gamma rays in the scintillator cause ionization and excitation of the scintillator. The energy E lost in the scintillator by the incident gamma ray causes the scintillator to emit photons. The total number of emitted photons produced in the scintillator is then:
Figure BDA0003383708900000041
Figure BDA0003383708900000042
as photon energy averaged over the emission spectrum, CnpThe differential luminous efficiency. The photoelectric conversion device is an electronic device that converts a weak signal into an electric signal. After receiving the emitted photons of the scintillator, its output current pulse is approximately:
Figure BDA0003383708900000051
q is the total charge collected at the anode, τ0Is the pulse decay time constant. After passing through the RC circuit, the output voltage is calculated as follows:
Figure BDA0003383708900000052
the maximum pulse amplitude is:
Figure BDA0003383708900000053
the maximum output pulse amplitude of the above equation is proportional to Q and proportional to the incident particle energy. By measuring the maximum pulse amplitude, energy information of the incident radiation can be obtained.
Further, in this embodiment, the gamma radiation monitor employs a CLYC crystal 1, the CLYC crystal 1 is coupled with SiPM through silicone oil 4, converts a detected nuclear signal into a photoelectric signal, converts the photoelectric signal into a digital signal through a signal readout system at the rear end, obtains a pulse voltage amplitude, obtains an energy spectrum corresponding to a radiation source according to mathematical statistics of the pulse amplitude, and obtains radiation dose equivalent data through g (e) weighting function operation, thereby implementing real-time monitoring.
Specifically, the gamma radiation monitor adopts a CLYC crystal 1, an aluminum shell 3 is arranged outside the CLYC crystal 1, and BaSO is arranged in the aluminum shell 34The CLYC crystal 1 is coupled with SiPM through silicone oil 4, the silicone oil 4 is connected with a PN junction cathode 5, the SiPM photoelectric converter is connected with a PN junction anode 6, a detected nuclear signal can be converted into a photoelectric signal, the photoelectric signal is expanded into a trapezoid-like pulse signal by a voltage type peak holding circuit after being amplified by an operational amplifier, the trapezoid-like pulse signal immediately enters an ARM chip ADC (analog-to-digital converter), a pulse analog signal is converted into a digital signal, and when the ARM chip detects a pulse rising edge, a DMA (direct memory access) chip starts to acquire the digital signal converted by the ADC and obtains a pulse voltage amplitude. Obtaining energy spectrum of corresponding radioactive source according to mathematical statistics of pulse amplitude, and obtaining radiation dose equivalent through G (E) weighting function operationData and dosage data are uploaded to a dosage data management system through a data reading device or 4G/5G and Beidou, and personal dosage alarm, analysis and recording can be achieved.
Furthermore, the invention adopts a method which can directly convert the measured energy spectrum into dose, namely a weight factor method, namely a G (E) function method, wherein the G (E) function method is also called a full spectrum method, and each channel of a gamma-ray pulse amplitude spectrum measured by a spectrometer is added with a coefficient related to energy, namely a dose weight value. This value can be calculated from a g (e) function, which can be obtained by a least squares fit based on the principle of least squares of relative error. It is a function related to the size, structure, etc. of the detector, independent of the radiation field, so it can be used to calculate the absorbed dose of any gamma radiation field by calculating the G (E) function of the specific detector spectrometer. The method for calculating the gamma radiation absorption dose rate by using the G (E) function method does not need to perform spectrum resolution on a pulse amplitude spectrum, and can directly perform energy spectrum-dose conversion.
For an incident gamma photon of energy E0, with a probability n of depositing energy E in the scintillator (E, E0), it grants the scintillator an average energy of:
Figure BDA0003383708900000061
if the scintillator is replaced with an equivalent air medium, the average energy granted to the air by the photons is:
Figure BDA0003383708900000062
wherein k is a constant, mua(E0) The energy absorption coefficient of gamma photons in air with energy E0.
Since the scintillator medium composition is different from air,
Figure BDA0003383708900000063
and
Figure BDA0003383708900000064
the magnitude of the ratio of (a) is related to E0, i.e. integrating the dose by height using the pulse amplitude spectrum does not result in a flat energy response. To obtain a flat energy response, a G (E) function is introduced such that:
Figure BDA0003383708900000065
where k1 is a constant, and because of the absorbed dose of gamma photons in air,
Figure BDA0003383708900000066
therefore, the following steps are obtained:
Figure BDA0003383708900000067
specifically, the theoretical principle of n- γ is as follows: the scintillator has a luminescence curve similar to a step response after being excited by incident particles, and the luminescence intensity reaches a peak value in about 10-12s and then exponentially decays due to the de-excitation effect. With decay time constant divided into a fast component τf(fluorescence decay, tens of ns) and a slow component τs(phosphorescence setback, several hundred ns), the current pulse formed on the photoelectric conversion device can be approximated as:
Figure BDA0003383708900000068
where If and IS can be considered as fractions corresponding to different decay times, i.e. If IS the starting value for the fast component and IS the starting value for the slow component.
As shown in fig. 4, the fraction of fast components is larger for gamma rays; for neutrons, the density of electrons generated by charged ions generated by nuclear reaction in the scintillator is larger, the range is shorter, so that the de-excitation time of a plurality of excited atoms is longer, namely the attenuation time of current pulse signals after photoelectric conversion is longer, and the discrimination of neutrons and gamma is realized by extracting the difference of the attenuation time of the current pulse.
Further, in this embodiment, the n- γ radiation monitor employs a GAGG crystal 7, the GAGG crystal 7 is coupled with SiPM through silicon oil 4, an aluminum shell 3 is disposed outside the CLYC crystal 1, and BaSO is disposed inside the aluminum shell 34The CLYC crystal 1 is coupled with SiPM through silicone oil 4, the silicone oil 4 is connected with a PN junction cathode 5, the SiPM photoelectric converter is connected with a PN junction anode 6, detected nuclear signals are converted into photoelectric signals, the photoelectric signals are converted into digital signals through a signal reading system at the rear end, pulse voltage amplitude values are obtained, an energy spectrum corresponding to a radioactive source is obtained according to mathematical statistics of the pulse amplitude values, and radiation dose equivalent data are obtained through G (E) weighting function operation, so that real-time monitoring is realized.
Specifically, the n-gamma radiation monitor adopts a GAGG crystal 7, and the GAGG crystal 7 is coupled with SiPM through silicon oil 4, so that a detected nuclear signal can be converted into a photoelectric signal. The signal enters an ADC (analog-to-digital converter) of an ARM chip immediately after being amplified by an operational amplifier, a pulse analog signal is converted into a digital signal, when the ARM chip detects a pulse rising edge, a DMA (direct memory access) chip starts to acquire the digital signal converted by the ADC, n-gamma discrimination is carried out by adopting a pulse gradient method, and a pulse voltage amplitude is obtained. According to the mathematical statistics of the pulse amplitude, the energy spectrum of the corresponding radioactive source is obtained, then radiation dose equivalent data is obtained through G (E) weighting function operation (the same as above), and the dose data is uploaded to a dose data management system through a data reading device or 4G/5G and Beidou, so that personal dose alarm, analysis and recording can be realized.
Specifically, the n-gamma discrimination algorithm: defining the pulse gradient m of the signal by adopting a pulse gradient method:
Figure BDA0003383708900000071
in the formula, ypIs the amplitude of the pulse peak; y isdThe amplitude at a fixed time after the selected peak; t is tp、tdAre each ypAnd ydThe corresponding time. All pulses normalized ypWith a value of 1, selecting a suitable tdThen the pulse gradient consists of y onlydDetermine, therefore, according to ydAnd carrying out n-gamma screening.
Further, in the present embodiment, the gamma radiation monitor and the n-gamma radiation monitor each have an accumulated dose function: according to the real-time monitoring data, calculating and recording a deep personal dose equivalent HP (10) and a superficial personal dose equivalent HP (0.07) within the using time of a user, and meanwhile, screening and recording the irradiated radionuclide species through an n/gamma screening algorithm and calculating the cumulative dose amount and the dose equivalent rate of the personal radiation dose.
Further, in this embodiment, the gamma radiation monitor and the n-gamma radiation monitor both have a dose alarm function: the dose threshold is set through real-time monitoring of radiation dose and monitoring of accumulated radiation dose, and when the dose data exceeds the dose threshold, the gamma radiation monitor and the n-gamma radiation monitor give an alarm in a sound or vibration mode. Specifically, the user is prompted to be overdimensioned when the annual dose within one year exceeds 20mSV, and the user is prompted to be overdimensioned when the annual dose within 1 year exceeds 50mVs within 5 years. When the dosage data exceeds the set threshold value, the portable radiation monitor gives an alarm by sound or vibration. In addition, when the data management system receives the data that the portable personal dose radiation monitor records exceeds the threshold value, the data management system also carries out sound or light prompting.
Further, in this embodiment, the data management system is developed based on a Windows system, and provides functions such as user registration, device management, dose analysis, energy spectrum presentation, and alarm recording.
Specifically, the user registration: the method is used for establishing a user database, providing an operation basis for equipment management, opening up a dosage management space of at least 2000 users and storing personal equipment information of the users.
Specifically, the device management: the portable personal dosage monitor is used for managing the information of the equipment, managing the time and the service time of the registered equipment, configuring and storing the specified equipment, configuring the portable personal dosage monitor during the next data transmission, and performing targeted equipment management according to the service condition of each equipment.
Specifically, the dose analysis: through the recorded data uploaded by each device recorded in the system, the annual integral radiation dose analysis is carried out on the data of the whole system, the change situation of the annual total radiation dose in time can be visually displayed, the standby absorbed dose in 5 years can be calculated according to the dose equivalent of each use of the registered device, the annual total effective dose of a user is calculated for comparison in the same year, the use time, the single dose equivalent, the accumulated dose equivalent, the dose equivalent rate and the irradiated radionuclide type of the device can be analyzed, and the irradiated situation and the annual irradiated trend of each user can be visually and clearly analyzed.
Specifically, the alarm recording: according to the effective standby absorbed dose of the dose analysis, when the annual dose within 1 year exceeds 20mSv, the user is prompted to be overdimensioned, or when the annual dose within 5 years exceeds 50mSv, the user is prompted to be overdimensioned; the real time, dose equivalent, irradiated radionuclide species of each alarm in the portable nuclear radiation personal dose monitor are recorded for dose analysis by the user.
The invention uses a portable gamma radiation personal dose radiation monitor, a portable n-gamma radiation personal dose radiation monitor and a matched personal dose equivalent measuring system to comprehensively and safely monitor various aspects of personal irradiated radiation quantity, radionuclide species, real-time dose, dose equivalent rate and the like, and when the irradiated quantity exceeds a threshold value, sound alarm and vibration prompt are carried out; the detection crystal of the GAGG, the CLYC detection crystal, the SiPM photoelectric conversion device and the energy spectrum are combined with the G (E) algorithm to realize the reliability of dose equivalent monitoring and the accuracy of dose equivalent measurement.
It should be noted that, for simplicity of description, the foregoing embodiments are described as a series of acts or combination of acts, but those skilled in the art will recognize that the present application is not limited by the order of acts, as some steps may occur in other orders or concurrently depending on the application. Further, those skilled in the art will appreciate that the embodiments described in the specification are presently preferred and that no particular act is required to implement the invention.
Furthermore, the terms "connected" and "disposed" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "connected" or "provided" may explicitly or implicitly include one or more of that feature. Furthermore, the terms "connected," "disposed," and the like are used for distinguishing between similar elements and not necessarily for describing a particular sequential or chronological order. It is to be understood that the data so used is interchangeable under appropriate circumstances such that the embodiments of the invention described herein are capable of operation in sequences other than those illustrated or described herein.
In the above embodiments, the basic principle and the main features of the present invention and the advantages of the present invention are described. It will be understood by those skilled in the art that the present invention is not limited to the embodiments described above, which are merely illustrative of the principles of the invention, and that modifications and variations can be made by one skilled in the art without departing from the spirit and scope of the invention as defined by the appended claims.

Claims (8)

1. A personal dose equivalent measuring system in a complex environment is characterized by comprising a radiation monitor, a data reading device and a data management system, wherein the data reading device is connected with the radiation monitor and used for acquiring dose data of the radiation monitor and uploading the dose data to the data management system; the radiation monitor comprises a gamma radiation monitor and an n-gamma radiation monitor; the data management system is used for providing user registration, equipment management, dose analysis, energy spectrum presentation and alarm recording.
2. The complex environment personal dose equivalent measurement system of claim 1, further comprising a network transmission module, wherein the radiation monitor is connected to the data management system through the network transmission module, and the network transmission module employs 4G/5G and beidou transmission.
3. A complex environment personal dose equivalent measurement system as claimed in claim 1 wherein said radiation monitor is connected to a data reading device via a wireless infrared module.
4. A complex environment personal dose equivalent measurement system as claimed in claim 1, wherein said data reading means uploads data to the data management system via USB communication.
5. The complex environment personal dose equivalent measurement system as claimed in claim 1, wherein the gamma radiation monitor employs a CLYC crystal (1), the CLYC crystal (1) is coupled with SiPM through silicone oil (4), the detected nuclear signal is converted into a photoelectric signal, the photoelectric signal is converted into a digital signal through a signal readout system at the rear end, a pulse voltage amplitude is obtained, an energy spectrum of a corresponding radioactive source is obtained according to mathematical statistics of the pulse amplitude, and radiation dose equivalent data is obtained through g (e) weighting function operation, so as to realize real-time monitoring.
6. The complex environment personal dose equivalent measurement system as claimed in claim 1, wherein the n- γ radiation monitor employs a GAGG crystal (7), the GAGG crystal (7) is coupled with SiPM through silicone oil (4), the detected nuclear signal is converted into a photoelectric signal, the photoelectric signal is converted into a digital signal through a signal readout system at the rear end, a pulse voltage amplitude is obtained, an energy spectrum of a corresponding radiation source is obtained according to mathematical statistics of the pulse amplitude, and radiation dose equivalent data is obtained through g (e) weighting function operation, so as to implement real-time monitoring.
7. A complex environment personal dose equivalent measurement system as claimed in any one of claims 1, 5 or 6, wherein said gamma radiation monitor and n-gamma radiation monitor each have cumulative dose functionality: according to the real-time monitoring data, calculating and recording a deep personal dose equivalent HP (10) and a superficial personal dose equivalent HP (0.07) within the using time of a user, and meanwhile, screening and recording the irradiated radionuclide species through an n/gamma screening algorithm and calculating the cumulative dose amount and the dose equivalent rate of the personal radiation dose.
8. A complex environment personal dose equivalent measurement system as claimed in any one of claims 1, 5 or 6, wherein said gamma radiation monitor and n-gamma radiation monitor each have a dose alarm function: the dose threshold is set through real-time monitoring of radiation dose and monitoring of accumulated radiation dose, and when the dose data exceeds the dose threshold, the gamma radiation monitor and the n-gamma radiation monitor give an alarm in a sound or vibration mode.
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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115826027A (en) * 2022-12-01 2023-03-21 成都理工大学 In-vehicle radiation environment monitoring system and radiation dose calculation method

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115826027A (en) * 2022-12-01 2023-03-21 成都理工大学 In-vehicle radiation environment monitoring system and radiation dose calculation method
CN115826027B (en) * 2022-12-01 2024-04-05 成都理工大学 In-vehicle radiation environment monitoring system and radiation dose calculating method

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