CN111812700B - γ-β composite detection device - Google Patents
γ-β composite detection device Download PDFInfo
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- CN111812700B CN111812700B CN202010714761.9A CN202010714761A CN111812700B CN 111812700 B CN111812700 B CN 111812700B CN 202010714761 A CN202010714761 A CN 202010714761A CN 111812700 B CN111812700 B CN 111812700B
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- 238000001514 detection method Methods 0.000 title claims abstract description 44
- 239000002131 composite material Substances 0.000 title claims abstract description 30
- 239000013078 crystal Substances 0.000 claims abstract description 125
- 238000012545 processing Methods 0.000 claims abstract description 39
- FVAUCKIRQBBSSJ-UHFFFAOYSA-M sodium iodide Chemical compound [Na+].[I-] FVAUCKIRQBBSSJ-UHFFFAOYSA-M 0.000 claims description 12
- 238000005040 ion trap Methods 0.000 claims description 11
- 238000010521 absorption reaction Methods 0.000 claims description 9
- 238000001228 spectrum Methods 0.000 claims description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 7
- 229910052792 caesium Inorganic materials 0.000 claims description 6
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 claims description 6
- 239000002245 particle Substances 0.000 claims description 5
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 claims description 4
- 229910052740 iodine Inorganic materials 0.000 claims description 4
- 239000011630 iodine Substances 0.000 claims description 4
- 150000002500 ions Chemical class 0.000 claims description 4
- 235000009518 sodium iodide Nutrition 0.000 claims description 4
- 239000007787 solid Substances 0.000 claims description 4
- XKUYOJZZLGFZTC-UHFFFAOYSA-K lanthanum(iii) bromide Chemical compound Br[La](Br)Br XKUYOJZZLGFZTC-UHFFFAOYSA-K 0.000 claims description 3
- 239000000446 fuel Substances 0.000 abstract description 16
- 230000005855 radiation Effects 0.000 abstract description 9
- 238000012423 maintenance Methods 0.000 abstract description 2
- 239000007789 gas Substances 0.000 description 47
- 238000001914 filtration Methods 0.000 description 6
- 239000000463 material Substances 0.000 description 6
- 239000003758 nuclear fuel Substances 0.000 description 5
- 230000002285 radioactive effect Effects 0.000 description 5
- 238000002835 absorbance Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 238000000034 method Methods 0.000 description 4
- 238000004445 quantitative analysis Methods 0.000 description 4
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 238000004451 qualitative analysis Methods 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 230000005251 gamma ray Effects 0.000 description 2
- 230000005253 gamme decay Effects 0.000 description 2
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 230000035945 sensitivity Effects 0.000 description 2
- 238000004458 analytical method Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000005250 beta ray Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 239000003507 refrigerant Substances 0.000 description 1
- 238000010183 spectrum analysis Methods 0.000 description 1
Classifications
-
- 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
- G01T1/20—Measuring radiation intensity with scintillation detectors
- G01T1/203—Measuring radiation intensity with scintillation detectors the detector being made of plastics
-
- 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
- G01T1/20—Measuring radiation intensity with scintillation detectors
- G01T1/2008—Measuring radiation intensity with scintillation detectors using a combination of different types of scintillation detectors, e.g. phoswich
-
- 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
- G01T1/20—Measuring radiation intensity with scintillation detectors
- G01T1/202—Measuring radiation intensity with scintillation detectors the detector being a crystal
- G01T1/2023—Selection of materials
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/36—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
- G01T1/362—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry with scintillation detectors
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/36—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
- G01T1/38—Particle discrimination and measurement of relative mass, e.g. by measurement of loss of energy with distance (dE/dx)
Landscapes
- Physics & Mathematics (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Chemical & Material Sciences (AREA)
- Crystallography & Structural Chemistry (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention belongs to the technical field of nuclear power maintenance, and particularly relates to a gamma-beta composite detection device. The first scintillation crystal has higher absorptivity to beta rays than gamma rays, so that the first photomultiplier and the first signal processing unit can detect beta rays according to the light rays emitted by the first scintillation crystal, the second scintillation crystal has lower absorptivity to beta rays than gamma rays, and the second photomultiplier and the second signal processing unit can detect gamma rays according to the light rays emitted by the second scintillation crystal, thereby realizing the composite detection of gamma rays and beta rays, and further assisting in judging the damage condition of the fuel assembly at different stacking times. In addition, the first scintillation crystal is used as a detection chamber, so that the gas to be detected is effectively stored, and the first scintillation crystal can fully receive radiation of rays released by the gas to be detected from inside to outside, so that the gamma-beta composite detection device can sensitively detect beta rays released by the gas to be detected.
Description
Technical Field
The invention belongs to the technical field of nuclear power maintenance, and particularly relates to a gamma-beta composite detection device.
Background
The most efficient detection means for detecting breakage of a nuclear fuel assembly is to detect radioactive fission gases released to the outside, and fissile materials in the fuel assembly are mainly Xe-133, kr-85, I-131, cs-136, cs-134, CS-137 and isotopes of these elements, wherein gaseous fission products which are not easily dissolved in water are mainly Xe-133 and Kr-85 and isotopes thereof. The branch ratio of the gamma ray decay of Xe-133 is large, and obvious energy characteristic peaks can be found by detecting the gamma rays, so that the Xe-133 and the radioactivity of the Xe-133 are judged, but the damage condition of the fuel assembly with long stacking time is difficult to judge by measuring Xe-133 nuclide due to the short half-life. The half-life period of the Kr-85 is long, and the Kr-85 can be used as a judging basis for the damage condition of the fuel assembly with long stack-out time, but the gamma decay branch ratio of the Kr-85 is small, the obvious energy characteristic peak is difficult to detect through gamma rays, the beta rays are continuous spectrums, and quantitative and qualitative analysis of radioactive substances is difficult to carry out when various radioactive substances exist. Therefore, there is a need for efficient detection of radioactivity in nuclear fuel assemblies that have long unstacking times.
Disclosure of Invention
In order to overcome the problems in the related art, a gamma-beta composite detection device is provided.
According to an aspect of the disclosed embodiments, there is provided a γ - β composite detection apparatus including a first photomultiplier tube, a second photomultiplier tube, a first scintillation crystal, a second scintillation crystal, a first signal processing unit, a second signal processing unit;
The first scintillation crystal is internally provided with a cavity, the cavity is used for storing gas to be detected, and one side surface of the second scintillation crystal is tightly attached to the surface of the first scintillation crystal;
The incident window of the first photomultiplier tube is closely attached to the surface of the first scintillation crystal;
The incident window of the second photomultiplier is closely attached to the surface of the other side of the second scintillation crystal;
The first scintillation crystal emits light under the irradiation of beta rays and/or gamma rays, the absorption rate of the first scintillation crystal to the beta rays is higher than that to the gamma rays, the first photomultiplier generates an electric signal according to the light rays emitted by the first scintillation crystal, and the first signal processing unit is connected with the first photomultiplier and is used for generating a map for identifying the beta rays according to the electric signal generated by the first photomultiplier;
The second scintillation crystal emits light under the condition of being irradiated by beta rays and/or gamma rays, the absorptivity of the second scintillation crystal to the beta rays is lower than that to the gamma rays, the second photomultiplier generates an electric signal according to the light rays emitted by the second scintillation crystal, and the second signal processing unit is connected with the second photomultiplier and is used for generating a map for identifying the gamma rays according to the electric signals generated by the second photomultiplier.
In one possible implementation, the outer wall of the first scintillation crystal is shaped as a sphere and the inner wall of the chamber of the first scintillation crystal is shaped as a sphere.
In one possible implementation, the spheres formed by the outer walls of the first scintillation crystal are concentric with the spheres formed by the inner walls of the chamber of the first scintillation crystal.
In one possible implementation, a side surface of the second scintillator is a spherical surface concentric with a sphere formed by an outer wall of the first scintillator;
The other side surface of the second scintillation crystal is a plane parallel to the tangential plane of one side surface of the two scintillation crystals.
In one possible implementation, the axial section of the second scintillation crystal is a trapezoidal section, a base of the longer trapezoidal section is located on one side surface of the second scintillation crystal, and a base of the shorter trapezoidal section is located on the other side surface of the second scintillation crystal.
In one possible implementation, the first scintillation crystal includes a plastic scintillator.
In one possible implementation, the second scintillation crystal includes sodium iodide or lanthanum bromide.
In one possible implementation, the gamma-beta composite detection device comprises a gas treatment unit;
the gas processing unit communicates with the chamber of the first scintillation crystal for processing gas input to the chamber of the first scintillation crystal.
In one possible implementation, the gas treatment unit includes a gas inlet, a filter, a dryer, a refrigerator, an ion trap, and a gas outlet;
the filter is communicated with the air inlet and is used for filtering solid particles, gaseous iodine and gaseous cesium of the air input from the air inlet;
The dryer is connected with the filter and is used for filtering the water vapor of the gas output by the filter;
The refrigerator is connected with the dryer and used for cooling the gas output by the overdrying device;
the ion trap is connected with the refrigerator and is used for filtering charged ions of gas output by the refrigerator;
One end of the air outlet is connected with the ion trap, the other end of the air outlet is connected with the cavity, and the gas output by the ion trap is input into the cavity through the air outlet.
In one possible implementation, the gamma-beta composite detection device is surrounded by a lead compartment.
The invention has the beneficial effects that in the embodiment of the disclosure, the absorptivity of the first scintillation crystal to the beta rays is higher than that of the gamma rays, so that the first photomultiplier and the first signal processing unit can detect the beta rays according to the rays emitted by the first scintillation crystal, the absorptivity of the second scintillation crystal to the beta rays is lower than that of the gamma rays, and the second photomultiplier and the second signal processing unit can detect the gamma rays according to the rays emitted by the second scintillation crystal, thereby realizing the composite detection of the gamma rays and the beta rays, realizing quantitative and qualitative analysis of radioactive gases such as Xe-133, kr-85 and the like, and further being capable of assisting in judging the damage condition of the fuel assembly at different stacking times. In addition, the first scintillation crystal is used as a detection chamber, so that the gas to be detected is effectively stored, and the first scintillation crystal can fully receive radiation of rays released by the gas to be detected from inside to outside, so that the gamma-beta composite detection device can sensitively detect beta rays released by the gas to be detected.
Drawings
Fig. 1 is a schematic diagram of a gamma-beta composite detection device, according to an exemplary embodiment.
Fig. 2 is a block diagram illustrating a gamma-beta composite detection device according to an exemplary embodiment.
Detailed Description
The invention will be described in further detail with reference to the accompanying drawings and specific examples.
In general, for fuel assemblies with short off-stack times, the Xe-133 gas content is high and the radioactivity can be analyzed by detecting the energy characteristic peak of Xe-133 by gamma rays.
As the released nuclides in the damaged fuel component mainly comprise Xe-133, kr-85, I-131, cs-136, cs-134, cs-137 and isotopes of Xe and Kr, most of the other nuclides are medium and short-lived, most of the nuclides decay in about one week after the nuclear fuel component is discharged, the isotope half-lives of Xe and Kr nuclides are generally too short, the nuclear fuel component is basically not in the component after the nuclear fuel component is discharged for two months, the I-131 half-life is 8.02d, the Cs-134 half-life 752.63d and the Cs-137 half-life is 11013d, but the nuclides are isotopes which are easy to dissolve in water, and once the fuel component is damaged, most of the leaked I-131, cs-134 and Cs-137 can be detained in a coolant. The most predominant gaseous species in the gas to be tested is Kr-85 for long-term storage of the fuel assembly. Therefore, for the fuel assembly with long pile-out time, the Kr-85 nuclide can be detected, the gamma decay branch ratio of the Kr-85 is only 0.43%, the obvious characteristic peak is difficult to detect, and the detection of beta rays can be adopted to analyze the Kr-85.
Fig. 1 is a schematic diagram of a gamma-beta composite detection device, according to an exemplary embodiment. As shown in fig. 1, the γ - β composite detection apparatus may include a first photomultiplier tube 2, a second photomultiplier tube 3, a first scintillation crystal 5, a second scintillation crystal 4, a first signal processing unit (not shown), and a second signal processing unit (not shown);
The first scintillation crystal 5 is internally provided with a cavity 6, the cavity 6 is used for storing gas to be detected, one side surface of the second scintillation crystal 4 is tightly attached to the surface of the first scintillation crystal 5, the first scintillation crystal 5 and the second scintillation crystal 4 can be in any shape such as cuboid, cylinder or polyhedron, the cavity of the first scintillation crystal 5 can also be in any shape such as cuboid, cylinder or polyhedron, and the shapes of the first scintillation crystal 5 and the second scintillation crystal 4 can be the same or different.
The first scintillation crystal 5 can emit light when irradiated by beta and/or gamma rays, and the first scintillation crystal 5 can have a higher absorption rate for beta rays than gamma rays, e.g., the material of the first scintillation crystal can be a plastic scintillator having an absorption efficiency for beta rays that is about 100 times higher than an absorption efficiency for gamma rays. (the embodiment of the disclosure does not limit the material of the first scintillation crystal, as long as the material has higher absorptivity to beta rays than to gamma rays), the incident window of the first photomultiplier tube 2 is closely attached to the surface of the first scintillation crystal 5, the first photomultiplier tube 2 generates an electric signal according to the light emitted by the first scintillation crystal 5, the first signal processing unit is connected with the first photomultiplier tube 2, and the Kr-85 is considered to be substantially only containing Kr-85 with long period due to the internal cracked gas in the fuel assembly with longer stacking time, and the Kr-85 mainly releases beta rays, and in addition, the absorptivity to beta rays of the first scintillation crystal is higher than the absorptivity to gamma rays, so that the first signal processing unit can generate an electric signal for identifying beta rays according to the electric signal generated by the first photomultiplier tube. Thus, the first scintillation crystal, the first photomultiplier tube, and the first signal processing unit may be primarily used for beta-ray detection of long-lived fuel assemblies.
The second scintillation crystal 4 may emit light when irradiated with β and/or γ rays, and the second scintillation crystal 4 has an absorbance for β rays lower than an absorbance for γ rays, for example, the material of the second scintillation crystal may be NaI (sodium iodide), laBr3 (lanthanum bromide), or the like (the material of the second scintillation crystal is not limited in this embodiment as long as the absorbance for β rays is lower than the absorbance for γ rays). The incident window of the second photomultiplier tube 3 is closely attached to the other side surface of the second scintillation crystal 4, the second photomultiplier tube 3 generates an electric signal according to light rays emitted by the second scintillation crystal 4, and the second signal processing unit is connected with the second photomultiplier tube 3. The gamma rays of specific nuclides have specific energy values, obvious peaks can be shown on the spectrum of the second signal processing unit to confirm which nuclide is the nuclide, the beta rays can only form continuous patterns without peaks, and the second scintillation crystal has low absorption efficiency on the beta rays and high absorption efficiency on the gamma rays, and the measuring signal of the second photomultiplier on the beta rays can be used as a radioactive background to exist in the measuring signal of the second photomultiplier on the gamma rays, so that the second signal processing unit can generate the spectrum for identifying the gamma rays according to the electric signals generated by the second photomultiplier. Therefore, the second scintillation crystal, the second photomultiplier tube and the second signal processing unit can be mainly used for gamma ray detection of the fuel assembly with shorter stack-out time.
In the embodiment of the disclosure, the absorptivity of the first scintillation crystal to the beta rays is higher than the absorptivity to the gamma rays, so that the first photomultiplier and the first signal processing unit can detect the beta rays according to the light rays emitted by the first scintillation crystal, the absorptivity of the second scintillation crystal to the beta rays is lower than the absorptivity to the gamma rays, and the second photomultiplier and the second signal processing unit can detect the gamma rays according to the light rays emitted by the second scintillation crystal, thereby realizing the composite detection of the gamma rays and the beta rays, realizing quantitative and qualitative analysis of radioactive gases such as Xe-133 and Kr-85, and further being capable of assisting in judging the damage condition of the fuel assembly at different stacking times. In addition, the first scintillation crystal is used as a detection chamber, so that the gas to be detected is effectively stored, and the first scintillation crystal can fully receive radiation of rays released by the gas to be detected from inside to outside, so that the gamma-beta composite detection device can sensitively detect beta rays released by the gas to be detected.
In one possible implementation, the outer wall of the first scintillation crystal may be spherical in shape, and the inner wall of the chamber of the first scintillation crystal may also be spherical in shape. For example, a sphere formed by an outer wall of the first scintillation crystal is concentric with a sphere formed by an inner wall of a chamber of the first scintillation crystal, which can effectively increase an area of the first scintillation crystal irradiated by radiation, increase sensitivity of the first scintillation crystal to detect radiation, and increase a volume of gas stored in the chamber, and in one example, can increase a detection efficiency of the first scintillation crystal to beta radiation by more than 50%.
In one possible implementation, where the first scintillation crystal is spherical in shape, one side surface of the second scintillation crystal may be machined to be spherical, which may be concentric with the first scintillation crystal shape, and the other side surface of the second scintillation crystal is a plane parallel to the one side surface tangent plane of the two scintillation crystals. Therefore, the radiation irradiation area of the second scintillation crystal can be effectively increased, one surface of the second scintillation crystal, which is clung to the first scintillation crystal, can be clung to the outer surface of the first crystal, and the sensitivity of the second scintillation crystal for detecting radiation is increased.
In one possible implementation, the axial cross section of the second scintillation crystal may be a trapezoidal cross section, with the longer base of the trapezoidal cross section being located on one side surface of the second scintillation crystal and the shorter base of the trapezoidal cross section being located on the other side surface of the second scintillation crystal.
In one possible implementation, the lead chamber 1 may be wrapped outside the first photomultiplier tube 2, the second photomultiplier tube 3, the first scintillation crystal 5, and the second scintillation crystal 4, and the lead chamber may shield external radiation rays, so as to further improve detection accuracy.
Fig. 2 is a block diagram illustrating a gamma-beta composite detection device according to an exemplary embodiment. As shown in fig. 2, the gamma-beta composite detecting device may further include a gas processing unit.
The gas processing unit is communicated with the cavity of the first scintillation crystal and is used for processing gas which is introduced into the cavity of the first scintillation crystal;
As shown in fig. 2, the gas treatment unit may include a gas inlet, a filter, a dryer, a refrigerator, an ion trap, and a gas outlet;
the filter is communicated with the air inlet and is used for filtering solid particles, gaseous iodine and gaseous cesium of the air input from the air inlet;
the dryer is connected with the filter and is used for filtering the vapor of the gas output by the filter;
the refrigerator is connected with the dryer and used for cooling the gas discharged from the overdrying device;
The ion trap is connected with the refrigerator and is used for filtering charged ions in the refrigerator.
For example, the gas to be measured enters the detection device from the gas inlet, and reaches the gas treatment unit first;
The gas to be measured firstly passes through a filter in a gas treatment unit, and solid particles, active gases such as iodine, cesium and the like are filtered;
the gas to be detected passes through a dryer, water vapor and iodine and cesium dissolved in the water vapor are filtered, and interference of active gases such as iodine, cesium and the like on detection results can be effectively avoided;
The gas to be detected passes through the refrigerant, the gas is cooled, preparation is carried out for entering the detection unit, and water vapor in the gas is further filtered;
the gas to be tested passes through an ion trap, and charged ions in the gas are filtered;
The gas to be measured enters a detection air cavity (an example of a cavity of a first scintillation crystal), a gamma detector (an example of a first scintillation crystal and a first photomultiplier) and a beta detector (an example of a first scintillation crystal and a first photomultiplier) respectively detect gamma rays and beta particles in the air cavity, detection signals of the gamma detector enter a gamma spectrometer (an example of a second signal processing unit) to form a spectrum for identifying gamma rays, and detection signals of the beta detector enter a beta signal processing unit to form a spectrum for identifying beta rays.
If the method aims at the fuel assembly with shorter stack-out time, the energy characteristic peak is analyzed on the gamma spectrum, so that the analysis of Xe-133 nuclide is realized;
If the method aims at the fuel assembly with longer stack-out time, the method can eliminate the activity influence of interfering nuclides by detecting the beta total count and assisting the gamma detector to perform energy spectrum analysis, thereby realizing quantitative analysis of Kr-85
The beta signal processing module can adopt an independent functional module design method and is mainly divided into a power module, a data processing module, a V-F (voltage-frequency) conversion module, a zeroing potentiometer and the like, and the radioactive signal processing units formed by the two parts jointly perform analog signal processing, digital-to-analog conversion and digital signal processing on beta and gamma pulse electric signals transmitted by the detector to form an analyzable energy map.
The foregoing description of the embodiments of the present disclosure has been presented for purposes of illustration and description, and is not intended to be exhaustive or limited to the embodiments disclosed. Many modifications and variations will be apparent to those of ordinary skill in the art without departing from the scope and spirit of the various embodiments described. The terminology used herein was chosen in order to best explain the principles of the embodiments, the practical application, or the technical improvement of the technology in the marketplace, or to enable others of ordinary skill in the art to understand the embodiments disclosed herein.
Claims (7)
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| CN103941275A (en) * | 2014-05-15 | 2014-07-23 | 长沙市宇驰检测技术有限公司 | Method for detecting radon in soil through scintillation chamber method |
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| CN212965440U (en) * | 2020-07-23 | 2021-04-13 | 中核武汉核电运行技术股份有限公司 | Gamma-beta composite detecting device |
Family Cites Families (8)
| Publication number | Priority date | Publication date | Assignee | Title |
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| US3882309A (en) * | 1973-07-30 | 1975-05-06 | Texaco Inc | Dual scintillation detector, single photomultiplier density logging system |
| JPH06214035A (en) * | 1993-01-18 | 1994-08-05 | Hamamatsu Photonics Kk | Scintillation detecting device |
| CN101539630B (en) * | 2009-05-08 | 2012-01-25 | 上海生物医学工程研究中心 | Method for detecting and positioning compound high-energy rays |
| CN202362462U (en) * | 2011-11-14 | 2012-08-01 | 石家庄经济学院 | Exhaust type continuous radon gas detector |
| CN203617003U (en) * | 2013-12-02 | 2014-05-28 | 浙江大学 | Gamma ray detection interlocking device |
| CN104820232A (en) * | 2015-04-24 | 2015-08-05 | 中国船舶重工集团公司第七一九研究所 | On-line type energy spectrum analysis anti-coincidence measurement detector |
| CN109490939B (en) * | 2018-11-23 | 2022-10-21 | 南京航空航天大学 | Radioactive source positioning method applied to small unmanned aerial vehicle |
| CN109407139B (en) * | 2018-12-21 | 2024-03-22 | 苏州瑞派宁科技有限公司 | Combined scintillation crystal and radiation detection device and system comprising same |
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Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103941275A (en) * | 2014-05-15 | 2014-07-23 | 长沙市宇驰检测技术有限公司 | Method for detecting radon in soil through scintillation chamber method |
| CN208060728U (en) * | 2018-04-24 | 2018-11-06 | 中广核研究院有限公司 | Radioactive activity continuously monitors and nuclide identification device |
| CN212965440U (en) * | 2020-07-23 | 2021-04-13 | 中核武汉核电运行技术股份有限公司 | Gamma-beta composite detecting device |
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