CN112764086A - A miniaturized composite gamma spectrometer - Google Patents
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Abstract
本发明公开了一种小型化复合型γ(伽马)谱仪，具体包括半导体探测单元、闪烁晶体，以及光电转换器件和读出电路。创新点是在杯状的无机闪烁晶体的小尺寸空腔内紧凑安装一个高能量分辨的室温半导体伽马探测器，综合了无机闪烁晶体高探测效率及半导体探测器高能量分辨的优势，使谱仪兼具低本底伽马计数和高分辨反康普顿伽马能谱测量的功能，可以较好满足不同条件下的使用需求。本发明的技术方案能够实现宽剂量率范围的伽马辐射探测，无需制冷，易于设计成小型化、轻量化的便携式探头，可在部分应用领域替代传统的具有反康普顿功能的高纯锗探测器，在环境辐射监测、放射性核素识别等方面具有广阔的应用前景。
The invention discloses a miniaturized composite gamma (gamma) spectrometer, which specifically includes a semiconductor detection unit, a scintillation crystal, a photoelectric conversion device and a readout circuit. The innovation is to compactly install a high-energy-resolution room temperature semiconductor gamma detector in the small cavity of the cup-shaped inorganic scintillation crystal, which combines the advantages of the high detection efficiency of the inorganic scintillation crystal and the high energy resolution of the semiconductor detector, so that the spectral The instrument has the functions of low-background gamma counting and high-resolution inverse-Compton gamma spectroscopy, which can better meet the needs of use under different conditions. The technical scheme of the invention can realize gamma radiation detection in a wide dose rate range without refrigeration, and is easy to be designed as a miniaturized and lightweight portable probe, which can replace the traditional high-purity germanium with anti-Compton function in some application fields The detector has broad application prospects in environmental radiation monitoring and radionuclide identification.
Description
Technical Field
The invention belongs to the technical field of radiation detection, and particularly relates to a miniaturized composite gamma spectrometer.
Background
At present, domestic researches on a composite gamma spectrometer mainly comprise: qiu's distance method of Nanjing Kernel-Annu-Nuclear-energy science and technology Limited company, a wide-energy anti-Compton anti-cosmic ray high-purity germanium spectrometer (patent number: CN208110056U), a Rejunlin's anti-coincidence ultra-Low background HPGe gamma spectrometer (patent number: CN108287362A) of Kadino science and technology Limited company, a preliminary development of an efficient compact anti-Compton spectrometer (NUCLEAR TECHNCHIQUES) of Zeng national Strength et al of university of Country and northwest Nuclear technology research institute, and an axisymmetric BGO anti-Compton shielded detector development (Nuclear Electronics research institute) of Reinforcement State et al of China academy of sciences&Detection Technology), wherein an anti-compton spectrometer designed with a high-purity germanium detector as a core detector can realize very high energy resolution and is convenient for realizing nuclide identification and other functions, but because the volume and the weight of the anti-compton spectrometer are large, the high-purity germanium still needs to be used in a low-temperature environment, refrigeration equipment is needed in the using process, the anti-compton spectrometer is difficult to be used for field and field measurement, and the anti-compton spectrometer can only be used for a Detection method of field sampling-laboratory analysis with poor timeliness and high analysis cost; however, in the currently proposed patents of miniaturized portable composite gamma spectrometers, such as "a stacked scintillation type anti-Compton gamma spectrometer" (patent No. CN108535766A) of Cheng Li et al of the Chinese radiation protection research institute, "a portable anti-Compton detector" (patent No. CN206990810U) of Stadium Kogyo et al of the national institute of Nuclear-Industrial geology, Sichuan, the "a composite scintillator gamma spectrometer" (patent No. CN106547017A) of Zeng Zhi et al of the Qinghua university, and "preliminary research on a method for rapidly detecting a seawater in-situ gamma energy spectrum" (academic position of university of Chengdu university) of Cheng Dynasty university, all the patents adopt two scintillators for compounding, such as NaI crystal plus plastic scintillator, LaBr3The scheme needs to adopt a plurality of photoelectric conversion devices for reading or discriminate signal waveforms by utilizing the difference of the attenuation time of two crystals, thereby increasing the complexity of spectrometer reading electronics, and bringing certain difficulty to radionuclide identification due to relatively poor energy resolution of scintillation crystals. To is coming toThe design scheme of a miniaturized composite gamma spectrometer is provided by combining two detection units, namely a semiconductor detector and a scintillation crystal, and the design scheme is more portable and meets the requirements of general field tests.
In recent years, semiconductor-type gamma detectors have been developed rapidly, some types (such as cadmium zinc telluride, cadmium telluride, etc.) have good energy resolution at room temperature, and meanwhile, because refrigeration is not needed, the readout electronics is simple, and the miniaturization design of a spectrometer is easy to realize. However, due to the problems of process and cost, the room temperature semiconductor detector is difficult to be made large, so that the detection efficiency is often low, and the counting rate is too low under the condition of low radioactivity.
The scintillation crystal is developed well at present and is easy to process into a larger size, so that the scintillation crystal has high detection efficiency, has good measurement effect under the conditions of low radioactivity and short measurement time, and can just make up the defect of the detection efficiency of a common room-temperature semiconductor detector.
For high-energy gamma rays, the compton plateau of the measured spectrum is high due to the small volume of the room temperature semiconductor detector (often on the order of cubic centimeters). For the occasions with various radionuclides, the Compton case of high-energy gamma rays can interfere with the full-energy peak case of low-energy gamma rays, and great difficulty is brought to nuclide identification. Therefore, when the semiconductor detector is used for gamma detection, if the scintillation crystal is used for carrying out anti-coincidence to inhibit the counting of the Compton case, the interference of the Compton case of the high-energy-region gamma rays on the low-energy-region gamma case can be greatly reduced, and the radionuclide identification capability of the spectrometer is improved.
Disclosure of Invention
The invention aims to provide a design scheme of a miniaturized compound gamma spectrometer aiming at the problems in the prior art, and the spectrometer is convenient to carry and can measure gamma radiation in a wide dose rate range in the environment in real time.
The technical scheme adopted by the invention is as follows: a miniaturized composite gamma spectrometer comprises a semiconductor detection unit, a cup-shaped scintillation crystal, a photoelectric conversion device and a reading circuit,
the semiconductor detection unit is used for gamma energy spectrum measurement;
the cup-shaped scintillation crystal can be used for realizing gamma counting measurement or gamma energy spectrum measurement with relatively low resolution, namely 5% -10% resolution at FWHM under the condition of low radioactivity and short measurement time of only a few minutes to tens of minutes, and can also be used as an anti-coincidence detector of a semiconductor detection unit, and one semiconductor detection unit is compactly arranged in a cavity of the cup-shaped scintillation crystal;
the photoelectric conversion device is used for converting an optical signal output by the scintillation crystal into an electric signal;
the reading circuit is used for receiving signals output by the semiconductor detector and the photoelectric conversion device, and sampling and processing are carried out after amplification.
Furthermore, the semiconductor detection unit is a room temperature semiconductor gamma detector which does not need refrigeration, has the size of centimeter magnitude, namely the diameter of the outer contour of 0.5cm to 10cm, and has high energy resolution, namely the FWHM resolution is better than 2.5%.
Furthermore, the scintillation crystal is easy to process and store, low in self radioactivity and high in gamma detection efficiency, the shape of the scintillation crystal is processed into a cup shape, and the semiconductor detection unit is placed in a cavity of the cup-shaped scintillation crystal.
Furthermore, the semiconductor detection unit and the scintillation crystal are used in a combined mode, so that the spectrometer has two measurement modes at the same time, and the use requirements of different test durations and wide dose rate ranges can be met.
Further, the two measurement modes comprise that the scintillation crystal is used for gamma detection alone, or the semiconductor detection unit is used for gamma detection and the scintillation crystal realizes the anti-Compton function.
Further, the semiconductor detection unit is used for realizing gamma spectrum measurement with high resolution, namely FWHM resolution, better than 2.5% under the condition of higher radioactivity of more than 1 muSv/h or lower radioactivity of less than 1 muSv/h but longer measurement time, namely the hour order.
The principle of the invention is as follows: the miniaturized composite gamma spectrometer provided by the invention comprises a semiconductor detection unit, a scintillation crystal, a photoelectric conversion device and a reading circuit.
The core part of the spectrometer is composed of a semiconductor detection unit with a block structure and a scintillation crystal with a cup shape. The semiconductor detector is placed in the cavity (close to the bottom) of the cup-shaped scintillation crystal, so that the effect that the semiconductor detector is enclosed in a large spatial solid angle range by the scintillation crystal is achieved, and the detection efficiency of the Compton scattered gamma rays is improved. The semiconductor detection unit adopts a room temperature type semiconductor gamma detector, and compared with a high-purity germanium detector, the room temperature semiconductor gamma detector does not need refrigeration and can be normally used at room temperature; compared with a scintillation crystal, the adopted room temperature semiconductor detector has high energy resolution, so that the radionuclide distinguishing capability is stronger, the detector is small in size, a photoelectric conversion device is not needed, and a current pulse signal can be directly output to a reading circuit, so that the miniaturization design is facilitated. The adopted inorganic scintillation crystal is easy to process, stable in chemical property, easy to store, low in radioactivity, high in density, strong in gamma ray stopping power and high in detection efficiency. The photoelectric conversion device is used for converting an optical signal output by the scintillation crystal into an electric signal and sending the electric signal to the reading circuit. The readout circuit amplifies the signals output by the semiconductor detector and the scintillation crystal detector respectively, and then carries out digital processing.
Compared with the prior art, the invention has the advantages that:
the gamma spectrometer provided by the invention has the advantages of two gamma detectors with different performances, can detect in a wide dose rate range, and can meet the use requirements under different conditions. Under the measuring conditions of low dose rate and short time, the semiconductor detector has small volume and relatively low detection efficiency, the selected scintillation crystal has relatively large volume and high detection efficiency on gamma rays, so that the radiation detection can be carried out only by using the scintillation crystal, and the gamma counting measurement or the gamma energy spectrum measurement with relatively low energy resolution ratio is realized; under the conditions of higher dose rate or longer measurement time, the semiconductor detector can be used for realizing high-resolution gamma energy spectrum measurement, and meanwhile, the scintillation crystal can be used as an anti-Compton detector, so that the counting of the Compton case of the energy spectrum measured by the semiconductor detector is inhibited, and the distinguishing capability of the radioactive nuclides is improved. The miniaturized composite gamma spectrometer disclosed by the invention can be used for measuring the counting rate and the energy spectrum of gamma rays in a larger dose rate range in real time, is beneficial to nuclide species identification, does not need refrigeration, is easy to design into a miniaturized and light portable probe, and can meet the radiation measurement requirements of various different application fields.
Drawings
Fig. 1 is a structural diagram of a miniaturized composite gamma spectrometer according to an embodiment of the present invention;
FIG. 2 is a schematic illustration of the BGO crystal and PMT package according to an embodiment of the present invention;
FIG. 3 is a diagram illustrating a simulated detector model according to an embodiment of the present invention;
FIG. 4 is a simulated CZT pair provided by an embodiment of the present invention137When the Cs is measured, the Cs reversely accords with the front and back energy spectrograms;
FIG. 5 is a simulated CZT pair provided by an embodiment of the present invention60Co doped with Cs137The measurement time is inversely in accordance with the front and back energy spectrograms;
FIG. 6 is a BGO simulation pair provided by an embodiment of the present invention60Energy spectrum when Co is measured.
Detailed Description
In order to make the technical contents of the present invention clearer, a specific embodiment will be described in detail below with reference to the accompanying drawings.
The structure of a design scheme of a gamma spectrometer specifically designed by the invention is shown in figure 1. In the embodiment, the semiconductor detection unit adopts a small-volume Cadmium Zinc Telluride (CZT) semiconductor detector which can achieve high-energy resolution at room temperature, and signals of an anode and a cathode of the semiconductor detection unit are respectively led out through a pin and directly connected to a reading circuit. The scintillation crystal selects BGO crystal with low radioactivity, high density, easy processing and other advantages, and uses photomultiplier tube (PMT) to make photoelectric conversion, the outer diameter of the cup-shaped BGO crystal is equal to the caliber of the PMT, the two are coupled together and sealed by aluminum shell, and the effect is shown in figure 2. And a corresponding voltage division circuit tube seat is arranged on the PMT, and a signal is led out to the reading circuit. The CZT detector is fixed on the front end circuit board through a support with a proper height, so that the CZT detector is located in the cavity of the cup-shaped BGO crystal and close to the bottom, and the efficiency of anti-Compton is improved. The reading circuit can be divided into a front end and a back end, wherein the front end circuit comprises a semiconductor detector front end circuit and a photoelectric conversion device front end circuit, signals output by the CZT detector and the PMT are amplified by the respective front end circuits respectively and then sent to a common back end circuit to be digitized and processed.
When the device is used, if the device is under the conditions of low radioactivity and short-time measurement, the spectrometer can only collect signals corresponding to the scintillation crystal through a configuration command, the signal amplitude threshold of the photoelectric conversion device is used as a trigger, and the energy measurement result of the scintillation crystal signal can be obtained according to waveform or amplitude information while the counting rate is calculated.
Under the condition of higher radioactivity or longer measuring time, the spectrometer can simultaneously acquire two paths of signals corresponding to the semiconductor detector and the scintillation crystal, the semiconductor detector serves as a main detector, and the scintillation crystal serves as an anti-Compton detector. The signal amplitude of the semiconductor detector is used as a trigger when the signal amplitude passes a threshold value. And when triggering is carried out each time, judging whether a threshold passing signal exists in a channel corresponding to the scintillation crystal in a fixed time window before and after the triggering time: if the gamma energy is not completely deposited in the semiconductor detector, the case is deleted; if the threshold signal is not exceeded, the instance is retained. The signal amplitudes corresponding to the semiconductor detectors in these retention cases are counted by back-end electronics, and the gamma energy spectrum after anti-compton can be obtained.
In order to verify the anti-compton function of the composite gamma spectrometer, a monte carlo physical simulation was performed using a computer program. The designed detector structure model is shown in fig. 3. In fig. 3, 1 is a cubic CZT semiconductor detector, which is provided with dimensions of 10mm, 2 is a cup-shaped BGO scintillation crystal, and is provided with a rulerThe front end of a cylinder with phi 51mm by 60mm is dug into a cylindrical cavity with phi 23mm by 30 mm. For a 662keV point source incidence gamma of 30cm from the detector (simulation)137Cs) is simulated, a certain random error is added to the energy measurement result obtained by each simulation to simulate the actual detector measurement error and the influence of electronic noise, etc., the anti-compton threshold of the BGO scintillation crystal is set to 80keV, and the energy spectrum results before and after anti-coincidence are obtained are shown in fig. 4. According to the energy spectrum comparison before and after the anti-coincidence, the full energy peak count of the energy spectrum after the anti-Compton basically has no loss, the Compton plateau is obviously inhibited, the peak Compton ratio is improved from 12 to 253, and the Compton inhibition coefficient is 21, which shows that the spectrometer adopting the scheme has a good anti-Compton effect theoretically.
Considering that in the field of radiation detection the environment to be measured tends to be complex and low energy gamma rays can be masked by the compton plateau of high energy gamma rays, to simulate this situation, a point source incident gamma case is simulated (simulation of a point source incident gamma case with a case ratio of 662keV 8%, 1.17MeV 46% and 1.33MeV 46%) (simulation of a point source incident gamma case)60Co and137cs mixed source) and the spectra before and after anti-compton are obtained as shown in fig. 5. It can be seen that in the spectrum after anti-compton, because the compton plateau is effectively inhibited, the proportion of the total energy peak count at 662keV to the total energy spectrum count is increased from 2.57% to 8.97%, so that the total energy peak becomes more prominent, which can greatly improve the capability of the spectrometer for identifying the radionuclide.
In order to show that the spectrometer can also independently use the BGO crystal to carry out gamma radiation detection so as to meet the application requirements of low dose rate and short time, contrast simulation is carried out on the independent use of the BGO crystal and the independent use of the CZT detector. FIG. 6 is a point source incidence γ (simulation) using 50% 1.17MeV and 50% 1.33MeV60Co) and CZT energy spectrum (certain measurement errors are added in the simulation program respectively, the ordinate is logarithmic coordinate), the cup-shaped BGO crystal can be seen to measure the normal gamma energy spectrum, and meanwhile, the BGO energy spectrum and the CZT energy spectrum are obtained through calculation: for a distance of 30cm from the detector60The total counting rate of the Co point source and the BGO crystal is about 18 times of the CZT. Furthermore, it can be seen that the peaks of the BGO crystal energy spectrumThe recovery ratio is obviously better than that of a CZT detector, the counting rate of the BGO crystal at the full energy peak is about 94 times that of the CZT detector, the BGO crystal with large volume and high detection efficiency has a good test effect under the conditions of low dose rate and short measurement time, and the defects of the CZT detector under the condition are just made up.
The above-mentioned embodiments further explain the objects, technical solutions and advantages of the present invention in detail. It should be understood that the above description is only exemplary of the present invention and is not intended to limit the present invention. Any modification, such as changing the type of semiconductor detector (CZT to another semiconductor detector with similar high resolution), changing the type of scintillation crystal (BGO to another type of scintillation crystal), and the type of photoelectric conversion device (PMT to SiPM or other types of photodetectors such as APD, PD), changing the packaging housing material, or changing the specific dimensions of the detector, as well as equivalent substitutions, modifications, etc., that are within the spirit and principles of the present invention, are intended to be included within the scope of the present invention.
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113133775A (en) * | 2021-04-06 | 2021-07-20 | 北京格物时代科技发展有限公司 | Gamma probe and gamma detection system comprising same |
| CN113835114A (en) * | 2021-08-25 | 2021-12-24 | 吉林大学 | A compact high-energy gamma-ray anti-coincidence stack detector |
| RU209993U1 (en) * | 2021-09-27 | 2022-03-24 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | GAMMA SPECTROMETER |
| CN117214942A (en) * | 2023-11-07 | 2023-12-12 | 清华大学 | High-purity germanium detector and preparation method thereof |
| CN117250651A (en) * | 2023-11-07 | 2023-12-19 | 中国科学技术大学 | Planet element detection device based on pixel type tellurium-zinc-cadmium detector |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20080251728A1 (en) * | 2007-04-10 | 2008-10-16 | The Regents Of The University Of Ca | Isotopic response with small scintillator based gamma-ray spectrometers |
| CN105510956A (en) * | 2015-07-19 | 2016-04-20 | 成都理工大学 | Anti-Compton scattering detector |
| US20160266260A1 (en) * | 2013-11-26 | 2016-09-15 | Flir Detection, Inc. | SiPM-BASED RADIATION DETECTION SYSTEMS AND METHODS |
| CN208110056U (en) * | 2018-04-12 | 2018-11-16 | 南京核安核能科技有限公司 | A kind of wide energy antiuniverse ray pured germanium crystal spectrometer of anti-Compton |
| CN209373136U (en) * | 2018-12-29 | 2019-09-10 | 西安中核核仪器有限公司 | Integrate the γ radiation detector assembly of tellurium-zincium-cadmium crystal and plastic scintillant |
| CN110687583A (en) * | 2019-11-05 | 2020-01-14 | 中国计量科学研究院 | Position energy time testing system and device based on CZT detector |
| CN111158040A (en) * | 2019-12-27 | 2020-05-15 | 中国原子能科学研究院 | A Layout Structure to Improve Compton Suppression Factor of Anti-Concentration Spectrometer |
| CN112083471A (en) * | 2020-09-15 | 2020-12-15 | 成都理工大学 | Anti-Compton Aerospace Gamma Spectroscopy Measurement System and Measurement Method |
-
2020
- 2020-12-28 CN CN202011594971.5A patent/CN112764086B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20080251728A1 (en) * | 2007-04-10 | 2008-10-16 | The Regents Of The University Of Ca | Isotopic response with small scintillator based gamma-ray spectrometers |
| US20160266260A1 (en) * | 2013-11-26 | 2016-09-15 | Flir Detection, Inc. | SiPM-BASED RADIATION DETECTION SYSTEMS AND METHODS |
| CN105510956A (en) * | 2015-07-19 | 2016-04-20 | 成都理工大学 | Anti-Compton scattering detector |
| CN208110056U (en) * | 2018-04-12 | 2018-11-16 | 南京核安核能科技有限公司 | A kind of wide energy antiuniverse ray pured germanium crystal spectrometer of anti-Compton |
| CN209373136U (en) * | 2018-12-29 | 2019-09-10 | 西安中核核仪器有限公司 | Integrate the γ radiation detector assembly of tellurium-zincium-cadmium crystal and plastic scintillant |
| CN110687583A (en) * | 2019-11-05 | 2020-01-14 | 中国计量科学研究院 | Position energy time testing system and device based on CZT detector |
| CN111158040A (en) * | 2019-12-27 | 2020-05-15 | 中国原子能科学研究院 | A Layout Structure to Improve Compton Suppression Factor of Anti-Concentration Spectrometer |
| CN112083471A (en) * | 2020-09-15 | 2020-12-15 | 成都理工大学 | Anti-Compton Aerospace Gamma Spectroscopy Measurement System and Measurement Method |
Non-Patent Citations (2)
| Title |
|---|
| 邹全，等: "面向辐射环境监测的反康普顿γ能谱仪蒙特卡罗模拟研究", 《四川大学学报（自然科学版》 * |
| 邹全，等: "面向辐射环境监测的反康普顿γ能谱仪蒙特卡罗模拟研究", 《四川大学学报（自然科学版》, vol. 55, no. 5, 30 September 2018 (2018-09-30), pages 1025 - 1030 * |
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