CN114545485A - Copper slag component content detection device based on neutron activation gamma energy spectrum analysis - Google Patents
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- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 title claims abstract description 79
- 239000010949 copper Substances 0.000 title claims abstract description 79
- 229910052802 copper Inorganic materials 0.000 title claims abstract description 79
- 239000002893 slag Substances 0.000 title claims abstract description 79
- 238000001514 detection method Methods 0.000 title claims abstract description 34
- 230000004913 activation Effects 0.000 title claims abstract description 31
- 238000010183 spectrum analysis Methods 0.000 title claims abstract description 18
- 238000001228 spectrum Methods 0.000 claims abstract description 45
- 230000005251 gamma ray Effects 0.000 claims abstract description 34
- 230000004907 flux Effects 0.000 claims abstract description 24
- 239000006096 absorbing agent Substances 0.000 claims abstract description 20
- 230000005855 radiation Effects 0.000 claims abstract description 19
- 238000005259 measurement Methods 0.000 claims abstract description 15
- 238000012545 processing Methods 0.000 claims abstract description 9
- XKUYOJZZLGFZTC-UHFFFAOYSA-K lanthanum(iii) bromide Chemical compound Br[La](Br)Br XKUYOJZZLGFZTC-UHFFFAOYSA-K 0.000 claims abstract description 8
- 239000000463 material Substances 0.000 claims description 25
- 238000006243 chemical reaction Methods 0.000 claims description 13
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 7
- 239000010439 graphite Substances 0.000 claims description 7
- 229910002804 graphite Inorganic materials 0.000 claims description 7
- 239000004698 Polyethylene Substances 0.000 claims description 6
- 229920000573 polyethylene Polymers 0.000 claims description 6
- 229910052580 B4C Inorganic materials 0.000 claims description 5
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 5
- 239000011449 brick Substances 0.000 claims description 4
- 239000013078 crystal Substances 0.000 claims description 4
- 238000007739 conversion coating Methods 0.000 claims description 3
- 229910010271 silicon carbide Inorganic materials 0.000 claims description 3
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 claims description 3
- 238000002139 neutron reflectometry Methods 0.000 abstract description 2
- 238000012031 short term test Methods 0.000 abstract 1
- 229910052805 deuterium Inorganic materials 0.000 description 8
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 7
- 238000000034 method Methods 0.000 description 7
- 238000003947 neutron activation analysis Methods 0.000 description 7
- 238000004519 manufacturing process Methods 0.000 description 5
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- 238000004458 analytical method Methods 0.000 description 3
- 229910052796 boron Inorganic materials 0.000 description 3
- 238000011161 development Methods 0.000 description 3
- -1 polyethylene Polymers 0.000 description 3
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 230000006872 improvement Effects 0.000 description 2
- 150000002500 ions Chemical class 0.000 description 2
- 238000004020 luminiscence type Methods 0.000 description 2
- 238000005272 metallurgy Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 239000002994 raw material Substances 0.000 description 2
- 230000003213 activating effect Effects 0.000 description 1
- 239000004568 cement Substances 0.000 description 1
- 238000009614 chemical analysis method Methods 0.000 description 1
- 239000003245 coal Substances 0.000 description 1
- 238000012937 correction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 229920001903 high density polyethylene Polymers 0.000 description 1
- 239000004700 high-density polyethylene Substances 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 239000012770 industrial material Substances 0.000 description 1
- 238000009776 industrial production Methods 0.000 description 1
- 229910052500 inorganic mineral Inorganic materials 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000011707 mineral Substances 0.000 description 1
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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
- G01T1/36—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
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Abstract
The invention discloses a copper slag component content detection device based on neutron activation gamma energy spectrum analysis, which comprises a neutron generator, a neutron reflecting layer, a radiation shield, a gamma ray shield, a thermal neutron absorber, a gamma energy spectrum detector, a gamma detector shield, a neutron flux monitor, a neutron generator control module and a gamma energy spectrum measurement and processing module, wherein the neutron generator is connected with the neutron generator through the neutron flux monitor; the neutron reflection layer and the radiation shield sequentially wrap the neutron generator from inside to outside to jointly form a collimation and shield of the neutron generator; the gamma energy spectrum detector is arranged in a gamma detector shield, and a thermal neutron absorber is arranged at the front end of the detector. The neutron source of the device adopts small-size neutron generator, and gamma energy spectrum detector is 3 inches lanthanum bromide, measures and analyzes through instantaneous gamma ray energy and intensity after the copper slag activation, can realize the short-term test to copper slag composition and content.
Description
Technical Field
The invention belongs to the technical field of nuclear radiation detection, particularly relates to the technical field of thermal neutron activation analysis and prompt gamma-ray energy spectrum detection, and particularly relates to a copper slag component content detection device based on neutron activation gamma-ray energy spectrum analysis.
Background
In the field of metallurgy, the method is vital to the detection of raw materials or material components in the process, real-time and effective online component detection can effectively improve the process quality and production efficiency of products and the intelligent level of the process flow. By means of a neutron activation prompt gamma analysis technology, neutrons and a raw material to be detected generate a neutron activation reaction, and the on-line detection of the components and the content of the material is realized by detecting and analyzing a prompt gamma energy spectrum generated by activation. The component content of the material can be obtained in real time without a complex chemical analysis method. Because the neutrons have strong penetrating power, the neutrons can penetrate into the material, and the non-contact on-line detection of the components of the whole material is realized.
The neutron generator generates high-energy fast neutrons, the fast neutrons are scattered with the outer graphite reflecting layer and gradually slowed down into thermal neutrons with lower energy through multiple scattering, the thermal neutrons are emitted from the pore channel of the graphite reflecting layer, and are subjected to radiation capture reaction with the atomic nuclei of the material to be detected, and characteristic gamma rays are released. The content of the components in the material can be obtained by measuring the activation gamma energy spectrum of the material and carrying out qualitative and quantitative analysis on energy peaks in the energy spectrum.
Due to the problem of integration of acquisition and industrial use of neutron generators, the development of practical application and popularization of early neutron activation analysis technology in domestic cement, coal and metallurgy industries is very slow. In recent years, with the strong promotion of the state on the modification and upgrading of the backward production process and the increasing enhancement of the environment protection supervising and checking strength, the power of the production enterprises for improving the economic and environment protection benefits is greatly improved. Foreign industrial detection equipment manufacturers aim at the wide application market prospect of China, and are beginning to vigorously promote the development and popularization of neutron activation analysis detection equipment. Aiming at various application scenes, neutron activation analysis detection equipment suitable for the production and use fields of domestic mineral resources is independently researched and developed, and the neutron activation analysis detection equipment has positive significance for breaking through the monopoly of foreign technologies and improving the domestic rate of equipment in the manufacturing industry.
With the improvement of the development technology of the domestic neutron generator, the compact and high-yield small deuterium neutron generator can meet the requirement of neutron activation analysis, and the application of the small neutron generator to the detection of industrial material components has feasibility. Compared with the traditional method for neutron activation analysis by using the Cf-252 radioactive source, the neutron generator does not generate neutrons and gamma radiation after being turned off, so that the on-site maintenance and operation are facilitated, and the radiation safety and controllability are higher.
Disclosure of Invention
In order to solve the technical problem, the invention provides a copper slag component content detection device based on neutron activation gamma energy spectrum analysis, which is used for online detection of copper slag components and content in industrial production.
The technical scheme adopted by the invention is as follows:
a copper slag component content detection device based on neutron activation gamma energy spectrum analysis comprises a gamma energy spectrum detector, a gamma detector shield, a first neutron reflecting layer, a second neutron reflecting layer, a thermal neutron absorber, copper slag, a gamma ray shield, a radiation shield, a neutron generator and a neutron flux monitor; the pair of gamma detector shields are provided with central round holes for placing the gamma energy spectrum detectors, and the thermal neutron absorber is placed in front of the central round holes; the second neutron reflecting layer is a hollow cuboid with an opening at the upper end, the opening at the upper end is covered by the gamma ray shielding body, and the neutron generator is wrapped in the second neutron reflecting layer; the gamma ray shielding body is positioned right above the neutron generator and right below the copper slag and is tightly attached to the gamma detector shielding body; the copper slag is arranged between the pair of gamma detector shields, and the first neutron reflecting layer is arranged right above the copper slag; the radiation shield surrounds the outermost periphery of the copper slag component content detection device; the neutron flux monitor is located in a cavity formed by the first neutron reflecting layer, the gamma detector shielding body and the gamma ray shielding body and is close to the copper slag.
The neutron generator generates neutrons with high flux and energy, the energy of the neutrons is reduced through the first neutron reflecting layer and the second neutron reflecting layer, and the neutrons are gathered to the copper slag to generate neutron activation reaction with elements in the copper slag; a large amount of instantaneous gamma rays are released after the copper slag is activated, the gamma rays enter the gamma energy spectrum detector to be absorbed and generate pulse signals, and the detection of the component content of the copper slag is realized by recording the energy and the intensity of the pulse signals.
Further, the gamma energy spectrum detector is a lanthanum bromide detector, the diameter and the length of the crystal are both 7.62cm, and the energy resolution of 661keV gamma rays is higher than 3.5%.
Furthermore, the gamma detector shield body is made of a lead-boron-polyethylene material and is used for shielding most neutrons and gamma rays generated by the neutrons and surrounding materials, and the measurement signal-to-noise ratio of the gamma energy spectrum detector to the gamma rays of the copper slag is improved.
Further, the device also comprises a neutron generator control module and a gamma energy spectrum measuring and processing module.
Furthermore, the first neutron reflecting layer and the second neutron reflecting layer are both made of high-purity graphite and are 5-15 cm thick.
Furthermore, the thermal neutron absorber is boron carbide and has a thickness of 1 cm.
Furthermore, the gamma ray shielding body is made of old lead with lead content higher than 99.99%, and is formed by splicing a plurality of dovetail-shaped lead bricks, and the thickness of each lead brick is 5 cm.
Furthermore, the neutron flux monitor is a silicon carbide detector with a thermal neutron conversion coating, is positioned at the position irradiated by the copper slag, and corrects the source intensity fluctuation of the neutron generator by detecting the intensity of thermal neutrons in real time.
The detection device of the invention has the following advantages:
1. the invention adopts a safe and controllable small deuterium neutron generator as a neutron generator for activation reaction, and has higher radiation safety compared with the traditional Cf-252 isotope neutron source with continuous radioactivity.
2. Compared with the method without the reflecting layer, the neutron reflecting layer made of high-purity graphite has the advantages that the thermal neutron flux of the copper slag to be irradiated is improved by 30%, the neutron utilization efficiency of the neutron generator is higher, and the neutron activation reaction probability is improved by about 30%.
3. The gamma energy spectrum detector adopts the lanthanum bromide detector with better energy resolution and shorter luminescence decay time, can effectively improve the peak shape of the gamma energy spectrum, improve the resolution capability of a heavy peak, and can improve the detectable counting rate level. And two gamma energy spectrum detectors are distributed on two sides of the copper slag to be detected, so that the influence of uneven distribution of the copper slag can be effectively solved.
4. The invention adopts optimized structural design and shielding combination, effectively improves the signal-to-noise ratio of the detection device and improves the component content detection precision of the device. The gamma detector is wrapped by lead-boron polyethylene material, and can well shield interfering neutrons and gamma rays, including direct or scattered neutrons from the generator, secondary gamma rays generated by the reaction of the neutrons and surrounding structural materials, and the like. Meanwhile, a thermal neutron absorber is arranged outside the opening of the gamma detector shielding body, so that scattered neutrons are prevented from entering the detector and being subjected to activation reaction with the crystal. The gamma detector and the detector shield are arranged at an angle of 90 degrees with the channel for neutron emergence, so that the influence of direct neutron irradiation on the measurement of the detector is avoided.
In conclusion, the copper slag component content detection device based on neutron activation gamma energy spectrum analysis adopts the neutron generator with higher radiation safety; the gamma energy spectrum detector adopts a large-size lanthanum bromide detector with higher energy resolution and shorter luminescence attenuation, and the influence of uneven arrangement of copper slag materials is corrected by installing 2 gamma energy spectrum detectors; the lead-boron-polyethylene shield is wrapped outside the lanthanum bromide detector, the thermal neutron absorber is placed at the front end of the detector, the system structure and the optimization design of the detector layout are adopted, the interference of scattered neutrons and secondary gamma rays on measurement is effectively reduced, the signal-to-noise ratio of the instantaneous gamma ray measurement of the material is remarkably improved, and the rapid and accurate measurement of the components and the content of the copper slag can be realized.
Drawings
FIG. 1 is a schematic structural diagram of a copper slag component content detection device based on neutron activation gamma energy spectrum analysis.
The system comprises a gamma energy spectrum detector 1, a gamma detector shield 2, a first neutron reflecting layer 3, a thermal neutron absorber 4, copper slag 5, a gamma ray shield 6, a second neutron reflecting layer 7, a radiation shield 8, a neutron generator 9, a neutron flux monitor 10, a neutron generator control module 11 and a gamma energy spectrum measuring and processing module 12.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention. In addition, the technical features involved in the embodiments of the present invention described below may be combined with each other as long as they do not conflict with each other.
The device for detecting the component content of the copper slag based on neutron activation gamma energy spectrum analysis comprises a gamma energy spectrum detector 1, a gamma detector shield 2, a first neutron reflecting layer 3, a second neutron reflecting layer 7, a thermal neutron absorber 4, the copper slag 5, a gamma ray shield 6, a radiation shield 8, a neutron generator 9, a neutron flux monitor 10, a neutron generator control module 11 and a gamma energy spectrum measuring and processing module 12. The pair of gamma detector shields 2 are provided with central circular holes for placing the gamma energy spectrum detectors 1, and the thermal neutron absorber 4 is placed in front of the central circular holes; the second neutron reflecting layer 7 is a hollow cuboid with an opening at the upper end, the opening at the upper end is covered by the gamma ray shielding body 6, and the neutron generator 9 is wrapped inside; the gamma ray shield 6 is positioned right above the neutron generator 9 and right below the copper slag 5 and is tightly attached to the gamma detector shield 2; the copper slag 5 is arranged between the pair of gamma detector shields 2, and the first neutron reflecting layer 3 is arranged right above the copper slag; the radiation shield 8 surrounds the outermost periphery of the copper slag component content detection device; the neutron flux monitor 10 is located in a cavity formed by the first neutron reflecting layer 3, the gamma detector shielding body 2 and the gamma ray shielding body 6 and is close to the copper slag 5.
The neutron generator 9 generates neutrons with high flux and energy, the energy of the neutrons is reduced through the first neutron reflecting layer 3 and the second neutron reflecting layer 7, and the neutrons are gathered to the copper slag 5 to generate neutron activation reaction with elements in the copper slag. And a large amount of prompt gamma rays are released after the copper slag 5 is activated, the gamma rays enter the gamma energy spectrum detector 1 to be absorbed and generate pulse signals, and the detection of the component content of the copper slag is realized by recording the energy and the intensity of the pulse signals.
The gamma energy spectrum detector 1 is a lanthanum bromide detector, the diameter and the length of a detector crystal are both 7.62cm, and the front end of the lanthanum bromide detector is tightly attached to the thermal neutron absorber 4; the thermal neutron absorber 4 is made of boron carbide, the diameter of the thermal neutron absorber is 15cm, and the thickness of the thermal neutron absorber is 1 cm. Preferably, it has an energy resolution higher than 3.5% for 661keV gamma rays.
The gamma detector shield 2 is made of lead-boron-polyethylene material, wherein the mass percent of lead is 70%, the mass percent of boron is 10%, and the mass percent of polyethylene is 20%. The appearance of the gamma detector shielding body 2 is a hollow cuboid and is used for shielding most neutrons and gamma rays generated by the neutrons and surrounding materials, and the measurement signal-to-noise ratio of the gamma energy spectrum detector 1 to the gamma rays of the copper slag 5 is improved. Preferably, the position of the gamma spectrum detector 1 in the gamma detector shield 2 can be adjusted according to the measurement requirements.
The thermal neutron absorber 4 is made of boron carbide, a boron nuclide in the boron carbide material has a high thermal neutron radiation capture cross section, the gamma ray energy released while absorbing neutrons cannot interfere with the measurement of the copper slag 5, and thermal neutrons are effectively prevented from entering the gamma energy spectrum detector 1. Preferably, the thermal neutron absorber 4 has a thickness of 1 cm.
The gamma ray shield 6 is made of old lead with lead content higher than 99.99%, has low radioactivity background and less impurities, and is preferably formed by splicing lead blocks with length, width and thickness of 20 x 10 x 5 cm. The gamma ray shielding body 6 shields and absorbs a large amount of gamma rays generated by the reaction of neutrons and surrounding materials, so that the gamma rays generated by other surrounding materials are prevented from entering the gamma energy spectrum detector 1, and the measurement signal-to-noise ratio of the copper slag gamma rays is effectively improved. Because the fast neutrons generated by the neutron generator 9 are scattered for many times by the reflecting layer to reduce certain energy, the gamma ray shielding body 6 made of lead materials can further reduce the energy of the neutrons to a hot zone, flux loss caused by excessive moderation of the neutrons is avoided, and meanwhile, the influence of interference gamma rays on the measurement of the copper slag component content can be effectively shielded.
The second neutron reflecting layer 7 is a hollow cuboid with an opening at the upper end, is made of high-purity graphite and is 15cm thick, the neutron generator 9 is wrapped in the second neutron reflecting layer 7, and neutrons are emitted from the square opening at the upper end after being scattered for many times in the second neutron reflecting layer 7 through the opening at the upper end of the second neutron reflecting layer 7. The second neutron reflecting layer 7 can collect neutrons which are emitted at an angle of 4 pi and generated by the neutron generator 9 to a square opening at the upper end of the second neutron reflecting layer for emitting, and the copper slag 5 to be detected is placed outside the square opening. The second neutron reflection layer 7 can improve the neutron flux level of the copper slag 5 to be detected, and effectively improves the utilization rate of the neutron generator 9. Preferably, the first neutron reflecting layer 3 and the second neutron reflecting layer 7 are both made of high-purity graphite and have the thickness of 5-15 cm.
The radiation shield 8 is a cuboid made of high-density polyethylene material, the thickness of the material is 15cm, and the copper slag component content detection device mainly comprises the following components: the gamma energy spectrum detector 1, the gamma detector shield 2, the first neutron reflecting layer 3, the second neutron reflecting layer 7, the thermal neutron absorber 4, the copper slag 5, the gamma ray shield 6, the neutron generator 9 and the neutron flux monitor 10 are wrapped in the shell. The radiation shield 8 is used for shielding and absorbing neutrons and gamma rays leaked from the neutron generator 9 to the surrounding environment, and effectively reduces the surrounding radiation dose equivalent of the copper slag component content detection device.
The neutron generator 9 is a small deuterium and deuterium neutron generator, and by accelerating deuterium ions to bombard deuterium nuclei, neutrons with high flux and energy of 2.45MeV are generated through reaction.
The neutron flux monitor 10 is a silicon carbide detector with a thermal neutron conversion coating. The output signal of the neutron flux monitor 10 and the output signal of the gamma energy spectrum detector 1 are simultaneously connected to the gamma energy spectrum measuring and processing module 12. The gamma energy spectrum measuring and processing module 12 comprises power supply, signal processing, acquisition and analysis of the gamma energy spectrum detector 1, and corrects the measurement result of the gamma energy spectrum detector 1 through the signal counting rate of the neutron flux monitor 10. The neutron flux monitor 10 is close to a copper slag sample to be detected and is used for monitoring the source intensity fluctuation of the neutron generator 9 and realizing the correction of the source intensity fluctuation of the neutron generator 9 by detecting the intensity of thermal neutrons in real time.
The neutron generator control module 11 includes high-voltage, ion source, cooling and vacuum control, provides the conditions required by the operation of the neutron generator 9 and performs operation control, and ensures that the neutron generator 9 can stably and efficiently generate neutrons. The measurement process of the whole device is as follows: the neutron generator 9 is provided with the required high pressure, ion source, cooling and vacuum by the neutron generator control module 11, so that deuterium and deuterium nuclear reactions occur inside the neutron generator 9 and fast neutrons with higher energy are generated. Fast neutrons are emitted from the interior of the neutron generator 9 to the periphery, are scattered in the second neutron reflecting layer 7, reduce energy, and are emitted from the square opening at the upper end of the second neutron reflecting layer 7 towards the copper slag 5 after being scattered for multiple times. The energy of the neutrons is further reduced when the neutrons pass through the gamma ray shield 6, and most of the gamma rays generated by the neutrons and the structural material of the neutron generator 9 can be absorbed by the gamma ray shield 6. The low-energy neutrons with lower energy penetrate into the copper slag 5 to perform neutron activation reaction with atomic nuclei in the copper slag 5, and release prompt gamma rays with energy from hundreds of KeV to 10 MeV. The gamma rays generated by activating the copper slag 5 are received by the gamma energy spectrum detector 1, and pulse amplitude signals corresponding to the energy of the gamma rays are generated. The signals are converted into digital signals through the gamma energy spectrum measuring and processing module 12 and collected, and the signals of the gamma energy spectrum detector 1 and the neutron flux monitor 10 are collected and analyzed through a program. Because the characteristic gamma ray energy generated by different nuclides after neutron activation is different, different nuclides can be distinguished through different gamma ray energies, meanwhile, the characteristic gamma ray intensity is in direct proportion to the content of the element in the copper slag 5, and the relationship between the calibrated element content and the characteristic gamma ray intensity is established through the measurement of a standard sample, so that the detection of the component content of the copper slag can be realized through the analysis of the gamma ray energy and the gamma ray intensity of the copper slag 5.
It will be understood by those skilled in the art that the foregoing is only a preferred embodiment of the present invention, and is not intended to limit the invention, and that any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (9)
1. The utility model provides a copper slag composition content detection device based on neutron activation gamma energy spectrum analysis which characterized in that: the device comprises a gamma energy spectrum detector (1), a gamma detector shield (2), a first neutron reflecting layer (3), a second neutron reflecting layer (7), a thermal neutron absorber (4), copper slag (5), a gamma ray shield (6), a radiation shield (8), a neutron generator (9) and a neutron flux monitor (10); the pair of gamma detector shields (2) are provided with central round holes for placing the gamma energy spectrum detectors (1), and the thermal neutron absorber (4) is placed in front of the central round holes; the second neutron reflecting layer (7) is a hollow cuboid with an opening at the upper end, the opening at the upper end is covered by the gamma ray shielding body (6), and the neutron generator (9) is wrapped in the second neutron reflecting layer; the gamma ray shield (6) is positioned right above the neutron generator (9) and right below the copper slag (5) and is tightly attached to the gamma detector shield (2); the copper slag (5) is arranged between the pair of gamma detector shields (2), and the first neutron reflecting layer (3) is arranged right above the copper slag; the radiation shield (8) surrounds the outermost periphery of the copper slag component content detection device; the neutron flux monitor (10) is positioned in a cavity formed by the first neutron reflecting layer (3), the gamma detector shielding body (2) and the gamma ray shielding body (6) and is close to the copper slag (5).
2. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: the neutron generator (9) generates neutrons with high flux and energy, the energy of the neutrons is reduced through the first neutron reflecting layer (3) and the second neutron reflecting layer (7), and the neutrons are gathered to the copper slag (5) to perform neutron activation reaction with elements in the copper slag; the copper slag component content detection method is characterized in that a large number of prompt gamma rays are released after the copper slag (5) is activated, the gamma rays enter the gamma energy spectrum detector (1) to be absorbed and generate pulse signals, and the detection of the component content of the copper slag is realized by recording the energy and the intensity of the pulse signals.
3. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: the gamma energy spectrum detector (1) is a lanthanum bromide detector, the diameter and the length of a detector crystal are both 7.62cm, and the energy resolution ratio of 661keV gamma rays is higher than 3.5%.
4. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: the gamma detector shield (2) is made of lead-boron-polyethylene materials and used for shielding most neutrons, the neutrons and gamma rays generated by surrounding materials, and the measurement signal-to-noise ratio of the gamma energy spectrum detector (1) to the gamma rays of the copper slag (5) is improved.
5. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: also comprises a neutron generator control module (11) and a gamma energy spectrum measuring and processing module (12).
6. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: the first neutron reflecting layer (3) and the second neutron reflecting layer (7) are both made of high-purity graphite and are 5-15 cm thick.
7. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: the thermal neutron absorber (4) is boron carbide and is 1cm thick.
8. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: the gamma ray shielding body (6) is made of old lead, the lead content is higher than 99.99%, the gamma ray shielding body is formed by splicing a plurality of dovetail-shaped lead bricks, and the thickness of each lead brick is 5 cm.
9. The device for detecting the content of the copper slag components based on neutron activation gamma energy spectrum analysis according to claim 1, wherein: the neutron flux monitor (10) is a silicon carbide detector with a thermal neutron conversion coating, is positioned at the irradiation position of the copper slag (5), and corrects the source intensity fluctuation of the neutron generator (9) by detecting the intensity of thermal neutrons in real time.
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| CN102175702A (en) * | 2010-11-22 | 2011-09-07 | 贾文宝 | Online detecting device of coal components |
| CN102095741A (en) * | 2011-01-10 | 2011-06-15 | 长沙开元仪器股份有限公司 | Method for detecting coal quality composition on conveying belt and device thereof |
| CN108918565A (en) * | 2018-05-11 | 2018-11-30 | 南京航空航天大学 | A kind of sample Elemental redistribution measuring device and method based on prompt gamma ray neutron activation analysis technique |
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