CN114839662A - Wide-range gamma dosimeter - Google Patents
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- CN114839662A CN114839662A CN202210530812.1A CN202210530812A CN114839662A CN 114839662 A CN114839662 A CN 114839662A CN 202210530812 A CN202210530812 A CN 202210530812A CN 114839662 A CN114839662 A CN 114839662A
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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
- G01T1/023—Scintillation dose-rate meters
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
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- G—PHYSICS
- G05—CONTROLLING; REGULATING
- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B19/00—Programme-control systems
- G05B19/02—Programme-control systems electric
- G05B19/04—Programme control other than numerical control, i.e. in sequence controllers or logic controllers
- G05B19/042—Programme control other than numerical control, i.e. in sequence controllers or logic controllers using digital processors
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention provides a wide-range gamma dosimeter which comprises a detection module, an acquisition and analysis module and a data distribution module, wherein the acquisition and analysis module is used for acquiring and analyzing electric pulse signals output by the detection module, and the data distribution module is used for man-machine interaction and data sharing. The detection module comprises a scintillator detector and a reading circuit, the acquisition and analysis module comprises a conditioning circuit, an AD converter and an FPGA (field programmable gate array), and the wide-range gamma dosimeter enables the scintillator detector to work in a single-pulse mode and a current mode by using the FPGA to match with the AD converter, so that the measurement range of gamma dose rate is expanded, and a gamma energy spectrum can be obtained in the single-pulse mode.
Description
Technical Field
The invention belongs to the technical field of ionizing radiation detection. In particular to a wide-range gamma dosimeter
Background
The gamma dose rate instrument has wide application in the fields of radiation monitoring, special workplaces in nuclear-related industries, nuclear medicine, nuclear security and the like, can provide real-time gamma dose rate or accumulated dose for related workers, can also provide warning when environmental radiation changes suddenly, and provides radiation safety guarantee for related workers.
The existing gamma-ray rate meters mainly use a counting rate conversion method, a G (E) function method and a current method. When the counting rate conversion method is applied to an inorganic scintillator, a large error occurs in the dose rate obtained by counting rate conversion due to high energy response at a low energy end, and the measurement deviation is increased due to accumulation of detector pulse signals in high environment dose rate; g (E) the function method uses full gamma energy spectrum information to carry out dose rate conversion, the conversion accuracy is the best, but pulse signals of a detector are seriously accumulated in high environment dose rate, and the accurate gamma energy spectrum cannot be obtained, so that the method is invalid; the working conditions of the two methods are that the detector is in a single-pulse mode; although the current method can work in a current mode in cooperation with a detector in a high dose rate environment, an error is increased in a low dose rate place due to insufficient detection sensitivity.
Under the condition that a single detector is used, the existing various gamma dose measuring instruments can only work in a single pulse mode or a current mode, so that the dose rate range coverage is narrow, particularly, an inorganic scintillator detector is usually used as an environmental gamma dose rate detection device, wrong judgment can be caused due to the fact that the dose rate range cannot be covered in an emergency, and under the background, the wide-range gamma dose instrument has important significance for the gamma dose rate instrument.
Applicants are unaware of prior art solutions in the above-mentioned field, providing a wide-range gamma dosimeter for enabling measurement of a wide range of gamma dose rates.
Disclosure of Invention
The invention aims to overcome the defects or shortcomings in the prior art and provide a wide-range gamma dosimeter, so that a scintillator detector can work in a single-pulse mode and a current mode under the control of a measuring instrument in a single probe mode, and the range of the gamma dosimeter is widened.
The purpose of the invention is realized as follows: the device consists of a detection module, an acquisition and analysis module and a data distribution module. The components and functions are realized as follows:
the detection module comprises a scintillator detector and a reading circuit; the scintillator detector is composed of a scintillator and a photoelectric conversion device, and the scintillator generates optical photons by causing a radiation-induced light effect through interaction with incident gamma rays; the light receiving surface of the photoelectric conversion device is coupled with the scintillator and used for converting optical photons into electric pulse signals; the reading circuit is connected with the photoelectric conversion device of the scintillator detector and is used for converting the current pulse signals output by the scintillator detector into voltage pulse signals.
The acquisition and analysis module comprises a conditioning circuit, an AD converter and an FPGA; the conditioning circuit is connected with the reading circuit of the detection module and is used for conditioning the voltage pulse signal output by the reading circuit to a voltage range adapted by the AD converter; the AD converter is used for converting an analog signal input into the AD converter by the conditioning circuit into a digital signal; the FPGA is used for monitoring the AD-converted nuclear pulse digital signal data stream in real time, setting a corresponding pulse integration time window according to the type of the scintillator detector, integrating the voltage signal in the time window and outputting an integral value.
The data collecting and distributing module is connected with the acquisition and analysis module and comprises a single chip microcomputer, a USB (universal serial bus), a wireless communication module and peripheral equipment; the single chip microcomputer is used for carrying out secondary processing on the nuclear pulse integral data output by the acquisition and analysis module to obtain gamma dose rate, gamma accumulated dose and gamma energy spectrum information of a radiation field and controlling other components of the data distribution module.
Preferably, wherein the scintillator is an inorganic scintillator.
Preferably, the photoelectric conversion device is one of a photomultiplier tube and a silicon photomultiplier tube, and the spectral response wavelength range of the photoelectric conversion device coincides with the scintillator light emission wavelength range.
Preferably, the readout circuit is composed of a current type front-end circuit in order to ensure the charge integration-energy correlation of the signal.
Preferably, the conditioning circuit is composed of an adjustable gain amplifying circuit and a single-end to differential circuit, and the adjustable gain amplifying circuit is composed of a high-speed operational amplifier in order to realize acquisition of a fast component of a nuclear pulse signal.
Preferably, wherein the AD converter is of a differential input type.
Preferably, the FPGA sets a signal threshold by determination of instrument electronics noise and signal baseline, the threshold being used to initiate the pulse integration time window.
Preferably, the single chip microcomputer determines whether the instrument works in a single pulse mode or a current mode by judging the number of integration values output by the FPGA in unit time, the single chip microcomputer performs dose rate conversion and gamma energy spectrum drawing simultaneously in the single pulse mode, and only performs dose rate conversion in the current mode.
Preferably, the single chip microcomputer can establish two-way communication with an upper computer through a USB and share gamma dose rate, gamma accumulated dose and gamma energy spectrum information.
Preferably, the single chip microcomputer can establish two-way communication with equipment with the same wireless communication function through the wireless communication module and share gamma dose rate, gamma accumulated dose and gamma energy spectrum information.
Preferably, the wireless communication module is any one of a bluetooth module, a ZigBee module, and a WiFi module.
Preferably, wherein the peripheral device comprises:
and the control key is connected with the singlechip and is used for controlling the working mode of the wide-range gamma dosimeter.
And the display screen is connected with the singlechip and is used for displaying the gamma dose rate, the gamma accumulated dose and the gamma energy spectrogram.
And the alarm is connected with the singlechip and used for giving an alarm when the gamma dose rate or the gamma accumulated dose exceeds a preset threshold value.
Preferably, the power module is connected with the detection module, the acquisition and analysis module and the data distribution module and used for supplying power to the detection module, the acquisition and analysis module and the data distribution module.
Compared with the prior art, the invention has the beneficial effects that: the wide-range gamma dosimeter disclosed by the invention has the advantages that the functions of the AD converter, the FPGA and the singlechip are integrated, and the modularized design of each part is matched, so that the scintillator detector can work in a single-pulse mode and a current mode, the gamma dose rate measuring range of the scintillator detector is expanded, meanwhile, the relative installation positions of each module can be adjusted according to the actual working environment, and the practicability is high.
Drawings
FIG. 1 is a block diagram of a wide range gamma dosimeter of the invention;
FIG. 2 is a schematic structural diagram of a detection module according to the present invention
FIG. 3 is a schematic diagram of a structure of the present invention
Reference numerals: the system comprises a detection module, a 2 acquisition and analysis module, a 3 data collection and distribution module, a 4 power supply module, a 5 scintillator detector, a 6 reading circuit, a 7 conditioning circuit, an 8 AD converter, a 9 FPGA, a 10 single chip microcomputer, an 11 USB, a 12 wireless communication module, a 13 peripheral device, a 14 scintillator, a 15 photoelectric converter, a 16 control key, a 17 display screen, an 18 alarm, a 19 optical adhesive, a 20 optical reflecting layer, a 21 row of needles, a 22 stainless steel hollow pipeline, a 23 mainframe box, a 24 aluminum cylindrical box and a 25 coaxial cable.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and specific embodiments.
Fig. 1 shows a block diagram of a system structure of a wide-range gamma dosimeter according to a preferred embodiment of the present invention, which includes a detection module 1, an acquisition and analysis module 2, a wireless communication module 3, and a power module 4.
Referring to fig. 2, the detection module 1 includes a scintillator detector 5 and a readout circuit 6, the scintillator detector 5 is a closed whole, and includes a scintillator 14 and a photoelectric conversion device 15 inside, and end faces of the two are connected by an optical cement 19; an optical reflection layer 20 is arranged in the gap inside the detection module; the reading circuit 6 is a current type front circuit, is packaged on a PCB and is connected with the signal output end of the scintillator detector 5 through a pin header 21;
the acquisition and analysis module 2 is connected to the detection module 1, and the acquisition and analysis module 2 is packaged on a PCB and comprises a conditioning circuit 7, an AD converter 8 and an FPGA 9;
the data distribution module 3 comprises a singlechip 10, a USB 11, a wireless communication module 12 and a peripheral 13; the single chip microcomputer 10 is connected to the FPGA 9 of the acquisition and analysis module 2; the peripheral comprises a control key 16, a display screen 17 and an alarm 18;
the power module 4 is connected to the detection module 1, the acquisition and analysis module 2 and the data distribution module, and is used for supplying power to each module.
In this embodiment, the optical photons generated after the scintillator 14 is irradiated by the gamma rays enter the photoelectric conversion device 15 under the guidance of the optical reflection layer and the optical cement to generate a current pulse signal, the current pulse signal is converted into a voltage pulse signal through the current type front-end circuit of the readout circuit 6, and the magnitude of the voltage pulse signal is equal to the energy E of the incident gamma rays γ And the energy E of the deposition of the incident gamma ray in the scintillator 14 dep Positively correlated, also E dep Absorbed dose D with scintillator 14 s Positively correlated, and the absorbed dose D of the scintillator 14 s With air absorbed dose D a Can be expressed by the dose conversion equation:
D s /D a ＝(μ en /ρ) s /(μ en /ρ) a
wherein (μ) en /ρ) s Is the mass energy absorption coefficient of the scintillator (μ) en /ρ) a Is the mass energy absorption coefficient of air. According to the above formula, the air absorbs the dose D a Absorbed dose D with scintillator 14 s And (4) positively correlating. Therefore, the energy-related information of the incident gamma ray related to the voltage pulse signal can be obtained by integrating a single voltage pulse signal, the air absorption dose-related information in unit time can be obtained by integrating all the voltage pulse signals in unit time, and the information can be calibrated to obtain the energy and the air absorption dose of the incident gamma ray. The voltage pulse signal enters a conditioning circuit 7, is adjusted to a voltage range adapted by an AD converter 8 by an adjustable gain amplifying circuit in the conditioning circuit 7 and is conditioned by a conditioning circuitThe single-end-to-differential circuit in the circuit 7 converts differential signals into differential signals to adapt to an input mode of the AD converter 8, the AD converter 8 digitalizes differential voltage pulse signals and transmits the differential voltage pulse signals to the FPGA 9, the FPGA 9 compares the input data stream with a preset threshold value one by one, when the signals are found to be larger than the threshold value, a time window is recorded backwards, the signals in the time window are accumulated to obtain an integral value, the recorded integral value is transmitted to the single chip microcomputer 10 one by one, the single chip microcomputer 10 immediately records the signal integral value and judges the accumulation degree according to the number of the signal integral value in unit time, when the accumulation degree is lower than the preset value of the single chip microcomputer 10, the scintillator detector 5 works in a single-pulse mode, the single chip microcomputer 10 continuously counts the signal integral value to form a gamma energy spectrum and stores the gamma energy spectrum, and simultaneously the single chip microcomputer 10 accumulates all the signal integral values in unit time to obtain a total signal integral value, when the accumulation degree is higher than the preset value of the single chip microcomputer 10, the scintillator detector 5 works in a current mode, the single chip microcomputer 10 stops counting the integral value and the gamma energy spectrum but continues to accumulate all signal integral values in unit time to obtain a total signal integral value, and the single chip microcomputer 10 further brings the total signal integral value into a calibration fitting formula to calculate the gamma dose rate.
In this embodiment, the control key 16 is arranged to control the display content of the display screen 17, where the display content includes the gamma dose rate, the gamma accumulated dose, and the gamma energy spectrum, and further, the user can clear the gamma accumulated dose and set the alarm value by the key, and when the gamma dose rate or the gamma accumulated dose exceeds the set alarm value, the alarm 18 will give an alarm.
In the embodiment, by arranging the USB 11, the wide-range gamma dosimeter can establish two-way communication with an upper computer in a wired mode and share gamma dose rate, gamma accumulated dose and gamma energy spectrum information; through setting up wireless communication module 12, wide range gamma dosimeter can establish two-way communication and share gamma dose rate, gamma accumulative total dose and gamma energy spectrum information with the equipment that possesses the same wireless communication function.
In some preferred modes, the scintillator 14-bit BGO scintillation crystal is a cylinder with the size of 25.4mm in diameter and 25.4mm in length, and the photoelectric conversion device is a photomultiplier with the diameter of 25.4mm and the length of 50 mm.
In some preferred modes, the AD converter is a 12-bit high-speed ADC with a sampling rate of 250 Msps.
In some preferred modes, the structure of the wide-range gamma dosimeter is as shown in fig. 3, the acquisition and analysis module 2 and the data distribution module 3 are installed in a main case 23, the detection module 1 is installed in an aluminum cylindrical box 24, the aluminum cylindrical box 24 is connected with the main case 23 through a stainless steel hollow pipe 22 with the length of 1m, and the readout circuit of the detection module 1 is connected with the conditioning circuit 7 of the acquisition and analysis module 2 through a coaxial cable 25 penetrating through the stainless steel hollow pipe 22.
In some preferred forms, the power module 4 contains an AC-DC circuit and a rechargeable lithium battery.
In summary, the invention relates to a wide-range gamma dosimeter, which comprises a detection module, an acquisition and analysis module for acquiring and analyzing electric pulse signals output by the detection module, and a data distribution module for human-computer interaction and data sharing. The detection module comprises a scintillator detector and a reading circuit, the acquisition and analysis module comprises a conditioning circuit, an AD converter and an FPGA (field programmable gate array), and the wide-range gamma dosimeter enables the scintillator detector to work in a single-pulse mode and a current mode by using the FPGA to match with the AD converter, so that the measurement range of gamma dose rate is expanded, and a gamma energy spectrum can be obtained in the single-pulse mode.
Claims (10)
1. A wide range gamma dosimeter characterized in that: the power supply module is connected with the detection module, the acquisition and analysis module and the data distribution module and supplies power to the detection module, the acquisition and analysis module and the data distribution module; the detection module comprises a scintillator detector and a reading circuit, wherein the reading circuit is connected with the scintillator detector and is used for converting a current pulse signal output by the scintillator detector into a voltage pulse signal; the acquisition and analysis module comprises a conditioning circuit, an AD converter and an FPGA, wherein the conditioning circuit is connected with a reading circuit of the detection module and is used for conditioning a voltage pulse signal output by the reading circuit to a voltage range adapted to the AD converter; the AD converter is used for converting the analog signal output by the conditioning circuit into a digital signal; the FPGA is used for monitoring digital signals of the AD converter, setting an integration time window, integrating voltage signals in the integration time window and outputting an integration value; the data collecting and distributing module is connected with the collecting and analyzing module and comprises a single chip microcomputer, a USB (universal serial bus), a wireless communication module and a peripheral, the single chip microcomputer determines whether the measuring instrument works in a single-pulse mode or a current mode by judging the number of the integrated values output by the FPGA in unit time, the single chip microcomputer performs dose rate conversion and simultaneously performs gamma energy spectrum drawing in the single-pulse mode, and only performs dose rate conversion in the current mode.
2. The wide-range gamma dosimeter of claim 1, wherein: the scintillator is an inorganic scintillator.
3. The wide-range gamma dosimeter of claim 1, wherein: the photoelectric conversion device is one of a photomultiplier tube and a silicon photomultiplier tube, and the spectral response wavelength range of the photoelectric conversion device coincides with the emission wavelength range of the scintillator.
4. The wide-range gamma dosimeter of claim 1, wherein: the reading circuit is composed of a current type front-end circuit.
5. The wide-range gamma dosimeter of claim 1, wherein: the conditioning circuit consists of an adjustable gain amplifying circuit and a single-end to differential circuit, and the adjustable gain amplifying circuit consists of a high-speed operational amplifier in order to realize the acquisition of the fast component of the nuclear pulse signal.
6. The wide-range gamma dosimeter of claim 1, wherein: the AD converter is of a differential input type.
7. The wide-range gamma dosimeter of claim 1, wherein: and the FPGA sets a signal threshold value through judging electronic noise and a signal baseline, and the threshold value is used for starting the pulse integration time window.
8. The wide-range gamma dosimeter of claim 1, wherein: the single chip microcomputer determines whether the instrument works in a single pulse mode or a current mode by judging the number of the integrated values output by the FPGA in unit time, the single chip microcomputer performs dose rate conversion and simultaneously performs gamma energy spectrum drawing in the single pulse mode, and only performs dose rate conversion in the current mode; the single chip microcomputer establishes two-way communication with an upper computer through a USB and shares gamma dose rate, gamma accumulated dose and gamma energy spectrum information; the single chip microcomputer can establish two-way communication with equipment with the same wireless communication function through the wireless communication module and share gamma dose rate, gamma accumulated dose and gamma energy spectrum information.
9. The wide-range gamma dosimeter of claim 1, wherein: the wireless communication module is any one of a Bluetooth module, a ZigBee module and a WiFi module.
10. The wide-range gamma dosimeter of claim 1, wherein: the peripheral comprises a control key, a display screen and an alarm; the control key is connected with the single chip microcomputer and used for controlling the working mode of the wide-range gamma dosimeter; the display screen is connected with the singlechip and is used for displaying the gamma dose rate, the gamma accumulated dose and the gamma energy spectrogram; the alarm is connected with the single chip microcomputer and used for giving an alarm when the gamma dose rate or the gamma accumulated dose exceeds a preset threshold value.
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Citations (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1098790A (en) * | 1994-06-10 | 1995-02-15 | 清华大学 | Miniature r-ray dosage instrument |
| CN101258421A (en) * | 2005-08-25 | 2008-09-03 | Rae系统股份有限公司 | Combined radiation dosimeter and rate meter |
| JP2014211380A (en) * | 2013-04-19 | 2014-11-13 | 三菱電機株式会社 | Dose rate measurement device |
| CN105953847A (en) * | 2015-12-24 | 2016-09-21 | 天津市迅尔电子信息技术有限公司 | Ultra-wide range vortex street signal measuring method |
| CN106707009A (en) * | 2016-12-30 | 2017-05-24 | 南京理工大学 | Wide-range high-precision current statistics circuit |
| CN109471154A (en) * | 2018-11-09 | 2019-03-15 | 中国核动力研究设计院 | A kind of small-sized GM counting tube wide-range measuring instrument |
| CN109669206A (en) * | 2019-03-03 | 2019-04-23 | 南昌华亮光电有限责任公司 | Circulating type liquid scintillator intelligence energy disperse spectroscopy system and its signal processing method |
| CN109975855A (en) * | 2019-04-02 | 2019-07-05 | 东华理工大学 | A kind of wide-range intelligence X- gamma dose rate instrument device based on Bluetooth technology |
| CN212160097U (en) * | 2019-11-12 | 2020-12-15 | 中核控制系统工程有限公司 | Wide-range gamma dose rate monitor |
| CN112882082A (en) * | 2021-01-12 | 2021-06-01 | 中国人民解放军海军工程大学 | Neutron-gamma ambient dose equivalent rate instrument based on pulse shape discrimination |
| CN112987070A (en) * | 2019-12-18 | 2021-06-18 | 广州兰泰胜辐射防护科技有限公司 | Detection signal processing method, device and circuit |
| CN113009542A (en) * | 2019-12-18 | 2021-06-22 | 广州兰泰胜辐射防护科技有限公司 | Radiation detection device and chip |
| CN214097799U (en) * | 2020-10-30 | 2021-08-31 | 江西省核工业地质调查院(江西省核工业地质局二六六大队) | Unmanned aerial vehicle radiation environment monitoring system |
| CN113848580A (en) * | 2021-09-26 | 2021-12-28 | 中国科学院高能物理研究所 | X/gamma ray radiation quantity detection system and detection method |
| CN114488251A (en) * | 2021-12-28 | 2022-05-13 | 中国原子能科学研究院 | Wide-range gamma radiation dose measuring system and method |
| CN114859393A (en) * | 2022-04-26 | 2022-08-05 | 中国科学院近代物理研究所 | Radiotherapy dose monitoring device with self-recovery function |
-
2022
- 2022-05-16 CN CN202210530812.1A patent/CN114839662A/en active Pending
Patent Citations (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1098790A (en) * | 1994-06-10 | 1995-02-15 | 清华大学 | Miniature r-ray dosage instrument |
| CN101258421A (en) * | 2005-08-25 | 2008-09-03 | Rae系统股份有限公司 | Combined radiation dosimeter and rate meter |
| JP2014211380A (en) * | 2013-04-19 | 2014-11-13 | 三菱電機株式会社 | Dose rate measurement device |
| CN105953847A (en) * | 2015-12-24 | 2016-09-21 | 天津市迅尔电子信息技术有限公司 | Ultra-wide range vortex street signal measuring method |
| CN106707009A (en) * | 2016-12-30 | 2017-05-24 | 南京理工大学 | Wide-range high-precision current statistics circuit |
| CN109471154A (en) * | 2018-11-09 | 2019-03-15 | 中国核动力研究设计院 | A kind of small-sized GM counting tube wide-range measuring instrument |
| CN109669206A (en) * | 2019-03-03 | 2019-04-23 | 南昌华亮光电有限责任公司 | Circulating type liquid scintillator intelligence energy disperse spectroscopy system and its signal processing method |
| CN109975855A (en) * | 2019-04-02 | 2019-07-05 | 东华理工大学 | A kind of wide-range intelligence X- gamma dose rate instrument device based on Bluetooth technology |
| CN212160097U (en) * | 2019-11-12 | 2020-12-15 | 中核控制系统工程有限公司 | Wide-range gamma dose rate monitor |
| CN112987070A (en) * | 2019-12-18 | 2021-06-18 | 广州兰泰胜辐射防护科技有限公司 | Detection signal processing method, device and circuit |
| CN113009542A (en) * | 2019-12-18 | 2021-06-22 | 广州兰泰胜辐射防护科技有限公司 | Radiation detection device and chip |
| CN214097799U (en) * | 2020-10-30 | 2021-08-31 | 江西省核工业地质调查院(江西省核工业地质局二六六大队) | Unmanned aerial vehicle radiation environment monitoring system |
| CN112882082A (en) * | 2021-01-12 | 2021-06-01 | 中国人民解放军海军工程大学 | Neutron-gamma ambient dose equivalent rate instrument based on pulse shape discrimination |
| CN113848580A (en) * | 2021-09-26 | 2021-12-28 | 中国科学院高能物理研究所 | X/gamma ray radiation quantity detection system and detection method |
| CN114488251A (en) * | 2021-12-28 | 2022-05-13 | 中国原子能科学研究院 | Wide-range gamma radiation dose measuring system and method |
| CN114859393A (en) * | 2022-04-26 | 2022-08-05 | 中国科学院近代物理研究所 | Radiotherapy dose monitoring device with self-recovery function |
Non-Patent Citations (1)
| Title |
|---|
| 杨立涛;李东仓;杨磊;孟祥厅;杨洋;: "基于FPGA与MC8051 IP核的χ-γ剂量仪设计", 核技术, no. 08, 10 August 2010 (2010-08-10) * |
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