CN114545485B - 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 90
- 239000010949 copper Substances 0.000 title claims abstract description 90
- 229910052802 copper Inorganic materials 0.000 title claims abstract description 90
- 239000002893 slag Substances 0.000 title claims abstract description 90
- 238000001514 detection method Methods 0.000 title claims abstract description 44
- 230000004913 activation Effects 0.000 title claims abstract description 30
- 238000010183 spectrum analysis Methods 0.000 title claims abstract description 14
- 238000001228 spectrum Methods 0.000 claims abstract description 54
- 230000005251 gamma ray Effects 0.000 claims abstract description 37
- 230000004907 flux Effects 0.000 claims abstract description 27
- 230000005855 radiation Effects 0.000 claims abstract description 21
- 239000006096 absorbing agent Substances 0.000 claims abstract description 20
- 238000012545 processing Methods 0.000 claims abstract description 13
- 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 28
- 238000002139 neutron reflectometry Methods 0.000 claims description 19
- 238000005259 measurement Methods 0.000 claims description 16
- 238000006243 chemical reaction Methods 0.000 claims description 15
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 7
- 229910052796 boron Inorganic materials 0.000 claims description 7
- 239000010439 graphite Substances 0.000 claims description 7
- 229910002804 graphite Inorganic materials 0.000 claims description 7
- -1 polyethylene Polymers 0.000 claims description 7
- 239000004698 Polyethylene Substances 0.000 claims description 6
- 238000004458 analytical method Methods 0.000 claims description 6
- 229910052805 deuterium Inorganic materials 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
- 238000001816 cooling Methods 0.000 claims description 3
- 150000002500 ions Chemical class 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
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 claims description 2
- 238000004519 manufacturing process Methods 0.000 description 6
- 238000000034 method Methods 0.000 description 6
- 238000003947 neutron activation analysis Methods 0.000 description 6
- 230000006872 improvement Effects 0.000 description 4
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 3
- 230000008901 benefit Effects 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 238000011161 development Methods 0.000 description 2
- 230000007613 environmental effect Effects 0.000 description 2
- 239000002994 raw material Substances 0.000 description 2
- 238000010521 absorption reaction Methods 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
- 238000013461 design Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 238000001730 gamma-ray spectroscopy 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
- 230000004807 localization Effects 0.000 description 1
- 238000004020 luminiscence type Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000011707 mineral Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 238000004451 qualitative analysis Methods 0.000 description 1
- 238000004445 quantitative analysis Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
Classifications
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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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- 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)
- Measurement Of Radiation (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
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 shielding body, a gamma ray shielding body, a thermal neutron absorber, a gamma energy spectrum detector, a gamma detector shielding body, a neutron flux monitor, a neutron generator control module and a gamma energy spectrum measuring and processing module, wherein the neutron generator is arranged on the neutron reflecting layer; the neutron reflecting layer and the radiation shielding body wrap the neutron generator in sequence from inside to outside to form collimation and shielding bodies of the neutron generator together; the gamma energy spectrum detector is arranged in the gamma detector shielding body, and a thermal neutron absorber is arranged at the front end of the detector. The neutron source of the device adopts a small neutron generator, the gamma energy spectrum detector is 3 inches of lanthanum bromide, and the rapid detection of the components and the content of copper slag can be realized by measuring and analyzing the energy and the intensity of the instantaneous gamma rays after the copper slag is activated.
Description
Technical Field
The invention belongs to the technical field of nuclear radiation detection, in particular to the technical field of thermal neutron activation analysis and prompt gamma energy spectrum detection, and particularly relates to a copper slag component content detection device based on neutron activation gamma energy spectrum analysis.
Background
In the metallurgical field, the method is crucial to the detection of the material components of raw materials or technical processes, and the real-time and effective online component detection can effectively improve the technical quality and the production efficiency of products and the intelligent level of the technical process. By means of neutron activation prompt gamma analysis technology, neutrons and raw materials to be detected undergo neutron activation reaction, and the prompt gamma energy spectrum generated by activation is detected and analyzed to realize the on-line detection of the components and the content of the materials. The component content of the material can be obtained in real time without a complex chemical analysis method. The neutrons have strong penetrating power, so that the neutrons can penetrate into the materials, and the non-contact on-line detection of all the material components is realized.
The neutron generator generates high-energy fast neutrons, the fast neutrons scatter with the graphite reflecting layer on the outer layer, the fast neutrons gradually slow down into thermal neutrons with lower energy through multiple scattering, the thermal neutrons are emitted from the pore channels of the graphite reflecting layer, and the thermal neutrons perform radiation capturing reaction with nuclei of materials to be detected and release characteristic gamma rays. The component content 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.
The method is subject to the problem of integration of neutron generator acquisition and industrial use, and the actual application and popularization of the early stage neutron activation analysis technology in the domestic cement, coal and metallurgical industries are very slow. In recent years, along with the strong promotion of the national improvement and upgrading of the lagging production process and the gradual enhancement of the environmental protection supervision, the power of improving the economic and environmental protection benefits of the improvement production line of the production enterprises is greatly improved. Foreign industrial detection equipment manufacturers aim at the vast application market prospect of China, and the development and popularization of neutron activation analysis detection equipment are greatly promoted. Aiming at various application scenes, neutron activation analysis detection equipment suitable for the domestic mineral resource production and use field is independently researched and developed, and the method has positive significance for breaking foreign technical monopoly and improving the localization rate of equipment in the manufacturing industry.
Along with the improvement of domestic neutron generator development technology, the compact high-yield small deuterium-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 been feasible. Compared with the traditional neutron activation analysis, the Cf-252 radiation source is adopted, the neutron generator does not generate neutrons and gamma radiation after being turned off, so that the on-site maintenance and operation are convenient, and the radiation safety and controllability are higher.
Disclosure of Invention
In order to solve the technical problems, 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 invention adopts the technical scheme that:
the copper slag component content detection device based on neutron activation gamma energy spectrum analysis comprises a gamma energy spectrum detector, a gamma detector shielding body, a first neutron reflecting layer, a second neutron reflecting layer, a thermal neutron absorber, copper slag, a gamma ray shielding body, a radiation shielding body, a neutron generator and a neutron flux monitor, wherein the first neutron reflecting layer and the second neutron reflecting layer are arranged on the surface of the copper slag; the gamma energy spectrum detectors are arranged in the gamma energy spectrum detectors, and the thermal neutron absorber is arranged in front of the central round hole; 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 reflection layer is arranged right above the copper slag; the radiation shielding body surrounds the outermost periphery of the copper slag component content detection device; the neutron flux monitor is positioned 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; and after the copper slag is activated, a large amount of instant gamma rays are released, the gamma rays enter the gamma energy spectrum detector to be absorbed and generate pulse signals, and the detection of the content of copper slag components 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 7.62cm, and the energy resolution of 661keV gamma rays is higher than 3.5%.
Furthermore, the gamma detector shielding body is made of lead-boron polyethylene material and is used for shielding most neutrons and gamma rays generated by the neutrons and surrounding materials, so that the measurement signal-to-noise ratio of the gamma spectrum detector to the gamma rays of the copper slag is improved.
Further, the system also comprises a neutron generator control module and a gamma energy spectrum measuring and processing module.
Further, the first neutron reflection layer and the second neutron reflection layer are both made of high-purity graphite, and the thickness of the first neutron reflection layer and the second neutron reflection layer is 5-15 cm.
Further, the thermal neutron absorber is boron carbide, and the thickness of the thermal neutron absorber is 1cm.
Further, the gamma ray shielding body material is old lead with the lead content higher than 99.99%, and is formed by splicing a plurality of dovetail-shaped lead bricks, wherein the thickness of the lead bricks is 5cm.
Further, the neutron flux monitor is a silicon carbide detector with a thermal neutron conversion coating and is positioned at the position irradiated by the copper slag, and the source intensity fluctuation of the neutron generator is corrected by detecting the intensity of thermal neutrons in real time.
The detection device of the invention has the following advantages:
1. the invention adopts the safe and controllable small-sized deuterium-deuterium neutron generator as the neutron generator of the activation reaction, and has higher radiation safety compared with the traditional Cf-252 isotope neutron source with continuous radioactivity.
2. Compared with a neutron reflecting layer made of high-purity graphite, the thermal neutron flux of copper slag to be irradiated is improved by 30% when the reflecting layer is not arranged, the neutron utilization efficiency of a 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 gamma energy spectrum, improve the resolution capability of heavy peaks, and can improve the detectable counting rate level. And two gamma energy spectrum detectors are distributed on two sides of copper slag to be detected, so that the influence of uneven distribution of the copper slag can be effectively solved.
4. The invention adopts the optimized structural design and shielding combination, effectively improves the signal-to-noise ratio of the detection device and improves the accuracy of detecting the component content of the device. The gamma detector is wrapped by lead-boron polyethylene material, and can well shield neutrons and gamma rays which interfere, including neutrons which are directly emitted or scattered from the generator, secondary gamma rays generated by the reaction of neutrons and surrounding structural materials, and the like. Meanwhile, a thermal neutron absorber is placed outside the opening of the shielding body of the gamma detector, so that scattered neutrons are prevented from entering the detector to perform an activation reaction with crystals. The gamma detector and the shielding body of the detector are placed at an angle of 90 degrees with the hole channel from which neutrons exit, so that the influence of direct radiation of neutrons on the measurement of the detector is avoided.
In summary, the copper slag component content detection device based on neutron activation gamma energy spectrum analysis adopts a neutron generator with higher radiation safety; the gamma energy spectrum detector adopts a large-size lanthanum bromide detector with higher energy resolution and shorter luminous attenuation, and the influence of uneven placement of copper slag materials is corrected by installing 2 gamma energy spectrum detectors; the lead boron polyethylene shielding body is wrapped outside the lanthanum bromide detector, the thermal neutron absorber is placed at the front end of the detector, and the system structure and the detector layout are optimally designed, so that the interference of scattered neutrons and secondary gamma rays to measurement is effectively reduced, the signal-to-noise ratio of measurement of the instant gamma rays of materials is remarkably improved, and the rapid and accurate measurement of copper slag components and content can be realized.
Drawings
FIG. 1 is a schematic structural diagram of a copper slag component content detection device based on neutron activation gamma-ray spectroscopy analysis.
The device comprises a gamma energy spectrum detector 1, a gamma detector shielding body 2, a first neutron reflecting layer 3, a thermal neutron absorber 4, copper slag 5, a gamma ray shielding body 6, a second neutron reflecting layer 7, a radiation shielding body 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
The present invention will be described in further detail with reference to the drawings and examples, in order to make the objects, technical solutions and advantages of the present invention more apparent. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the scope of the invention. In addition, the technical features of the embodiments of the present invention described below may be combined with each other as long as they do not collide with each other.
The copper slag component content detection device based on neutron activation gamma energy spectrum analysis comprises a gamma energy spectrum detector 1, a gamma detector shielding body 2, a first neutron reflecting layer 3, a second neutron reflecting layer 7, a thermal neutron absorber 4, copper slag 5, a gamma ray shielding body 6, a radiation shielding body 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. Wherein, a pair of gamma detector shields 2 are provided with a central round hole for placing the gamma energy spectrum detector 1, and a thermal neutron absorber 4 is placed in front of the central round hole; the second neutron reflecting layer 7 is a hollow cuboid with an open upper end, the open upper end of the second neutron reflecting layer 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 shielding body 6 is positioned right above the neutron generator 9 and right below the copper slag 5 and is closely attached to the gamma detector shielding body 2; the copper slag 5 is arranged between the pair of gamma detector shields 2, and the first neutron reflection 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 next to the copper slag 5.
The neutron generator 9 generates neutrons with high flux and energy, reduces the energy of the neutrons through the first neutron reflecting layer 3 and the second neutron reflecting layer 7, and gathers the neutrons to the copper slag 5 to perform neutron activation reaction with elements in the copper slag. The copper slag 5 is activated to release a large amount of instant gamma rays, the gamma rays enter the gamma energy spectrum detector 1 to be absorbed and generate pulse signals, and the detection of the content of copper slag components 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 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 is 15cm, and the thickness is 1cm. Preferably, it has an energy resolution of greater than 3.5% for 661keV gamma rays.
The gamma detector shielding body 2 is made of lead-boron polyethylene material, the mass percentage of lead is 70%, the mass percentage of boron is 10%, and the mass percentage of polyethylene is 20%. The outer shape 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, so that 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 energy spectrum detector 1 in the gamma detector shield 2 is adjustable according to measurement requirements.
The thermal neutron absorber 4 is made of boron carbide, boron nuclide in the boron carbide material has a very high thermal neutron radiation capturing section, gamma ray energy released during neutron absorption can not interfere with measurement of the copper slag 5, and thermal neutrons are effectively prevented from entering the gamma energy spectrum detector 1. Preferably, the thickness of the thermal neutron absorber 4 is 1cm.
The gamma ray shielding body 6 is made of old lead with lead content higher than 99.99%, has lower radioactive background and fewer impurities, and is formed by splicing lead blocks with length and width of 20 x 10 x 5cm. The gamma ray shielding body 6 shields and absorbs a large amount of gamma rays generated by the reaction of neutrons and surrounding materials, and prevents the gamma rays generated by other surrounding materials from entering the gamma energy spectrum detector 1, so that the measurement signal-to-noise ratio of copper slag gamma rays is effectively improved. The energy of fast neutrons generated by the neutron generator 9 is reduced by the multiple scattering of the reflecting layer, so that the gamma ray shielding body 6 made of lead materials can further reduce the energy of neutrons to a hot zone, flux loss caused by excessive slowdown of neutrons is avoided, and meanwhile, the influence of interference gamma rays on copper slag component content measurement can be effectively shielded.
The second neutron reflection layer 7 is a cuboid with an opening at the upper end and hollow, the material is high-purity graphite, the thickness is 15cm, the neutron generator 9 is wrapped in the cuboid, and the opening at the upper end of the second neutron reflection layer 7 enables the neutrons to exit from the square opening at the upper end after being scattered for multiple times in the second neutron reflection layer 7. The second neutron reflection layer 7 can collect neutrons which are generated by the neutron generator 9 and are diverged at the 4 pi angle to the square opening at the upper end for emitting, and 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 improve the utilization rate of the neutron generator 9. Preferably, the first neutron reflection layer 3 and the second neutron reflection layer 7 are made of high-purity graphite, and the thickness of the first neutron reflection layer and the second neutron reflection layer is 5-15 cm.
The radiation shielding body 8 is a cuboid composed of high-density polyethylene material, the thickness of the material is 15cm, and the main components of the copper slag component content detection device are as follows: the gamma energy spectrum detector 1, the gamma detector shielding body 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 shielding body 6, the neutron generator 9 and the neutron flux monitor 10 are wrapped. The radiation shield 8 is used for shielding and absorbing neutrons and gamma rays leaked from the neutron generator 9 to the surrounding environment, so that the surrounding radiation dose equivalent of the copper slag component content detection device is effectively reduced.
The neutron generator 9 is a small-sized deuterium-deuterium neutron generator, and the reaction generates neutrons with high flux and energy of 2.45MeV by accelerating deuterium ions to bombard deuterons.
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 into 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 fluctuation of the source intensity of the neutron generator 9 and correcting the fluctuation of the source intensity of the neutron generator 9 by detecting the intensity of thermal neutrons in real time.
The neutron generator control module 11 comprises high-pressure, ion source, cooling and vacuum control, provides conditions required by the operation of the neutron generator 9 and performs operation control, and ensures that the neutron generator 9 stably and efficiently generates neutrons. The whole device comprises the following measurement processes: the neutron generator control module 11 provides the required high pressure, ion source, cooling and vacuum for the neutron generator 9, so that deuterium deuteron reaction occurs in the neutron generator 9 and fast neutrons with higher energy are generated. Fast neutrons are emitted from the inside of the neutron generator 9 to the periphery, scattered in the second neutron reflecting layer 7, reduced in energy, and emitted from a square opening at the upper end of the second neutron reflecting layer 7 towards the copper slag 5 after multiple scattering. The energy of neutrons passing through the gamma ray shield 6 is further reduced and most of the gamma rays generated by 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, 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. Gamma rays generated by the activation of the copper slag 5 are received by the gamma energy spectrum detector 1, and pulse amplitude signals corresponding to gamma ray energy are generated. The signals are converted into digital signals through the gamma energy spectrum measuring and processing module 12 and are 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 the neutron activation of different nuclides is different, different nuclides can be distinguished through the different gamma ray energy, 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 copper slag component content can be realized through the analysis of the gamma ray energy and the intensity of the copper slag 5.
It will be readily appreciated by those skilled in the art that the foregoing description is merely a preferred embodiment of the invention and is not intended to limit the invention, but any modifications, equivalents, improvements or alternatives falling within the spirit and principles of the invention are intended to be included within the scope of the invention.
Claims (6)
1. Copper slag component content detection device based on neutron activation gamma energy spectrum analysis, its characterized in that: the detector comprises a gamma energy spectrum detector (1), a gamma detector shielding body (2), a first neutron reflecting layer (3) and a second neutron reflecting layer (7), a thermal neutron absorber (4), copper slag (5), a gamma ray shielding body (6), a radiation shielding body (8), a neutron generator (9) and a neutron flux monitor (10); wherein, a pair of gamma detector shields (2) are provided with a central round hole for placing the gamma energy spectrum detector (1), and a thermal neutron absorber (4) is placed in front of the central round hole; 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 shielding body (6) is positioned right above the neutron generator (9) and right below the copper slag (5) and is tightly attached to the gamma detector shielding body (2); the copper slag (5) is arranged between a pair of gamma detector shields (2), and the first neutron reflecting layer (3) is arranged right above the copper slag; the radiation shielding body (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);
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; the copper slag (5) is activated to release a large amount of instant gamma rays, the gamma rays enter the gamma energy spectrum detector (1) to be absorbed and generate pulse signals, and the detection of the content of copper slag components is realized by recording the energy and the intensity of the pulse signals;
the thermal neutron absorber (4) is boron carbide;
the system also comprises a neutron generator control module (11) and a gamma energy spectrum measuring and processing module (12); the output signal of the neutron flux monitor and the output signal of the gamma energy spectrum detector are simultaneously connected into the gamma energy spectrum measuring and processing module; the gamma energy spectrum measuring and processing module is used for realizing power supply, signal processing, acquisition and analysis of the gamma energy spectrum detector, and correcting the measurement result of the gamma energy spectrum detector through the signal counting rate of the neutron flux monitor; the neutron flux monitor (10) is a silicon carbide detector with a thermal neutron conversion coating and is positioned at the irradiation position of the copper slag (5), and the source intensity fluctuation of the neutron generator (9) is corrected by detecting the intensity of thermal neutrons in real time;
the opening at the upper end of the second neutron reflecting layer enables the neutrons to be emitted from the square opening at the upper end after being scattered for multiple times in the second neutron reflecting layer; the second neutron reflecting layer gathers neutrons which are generated by the neutron generator and are divergent in a 4 pi angle to the square opening at the upper end for emitting, and the copper slag to be detected is placed outside the square opening; the second neutron reflection layer improves the neutron flux level of copper slag to be detected and the utilization rate of a neutron generator;
providing required high pressure, an ion source, cooling and vacuum for the neutron generator through the neutron generator control module, so that deuterium deuteron reaction occurs in the neutron generator and fast neutrons with higher energy are generated; fast neutrons are emitted from the inside of the neutron generator to the periphery, scattered in the second neutron reflecting layer, reduced in energy, and emitted from a square opening at the upper end of the second neutron reflecting layer towards the copper slag after multiple scattering; the energy of neutrons passing through the gamma ray shield is further reduced, and most of the gamma rays generated by neutrons and the structural materials of the neutron generator can be absorbed by the gamma ray shield; the low-energy neutrons with lower energy penetrate into the copper slag, perform neutron activation reaction with atomic nuclei in the copper slag, and release instant gamma rays with energy from hundreds of KeV to 10 MeV; gamma rays generated by the copper slag activation are received by the gamma energy spectrum detector, and pulse amplitude signals corresponding to gamma ray energy are generated; the signals are converted into digital signals through the gamma energy spectrum measuring and processing module and are collected, and the signals of the gamma energy spectrum detector and the neutron flux monitor are collected and analyzed through a program; different nuclides are 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, and a calibrated relation between the element content and the characteristic gamma ray intensity is established through measurement of a standard sample, so that the detection of the copper slag component content is realized through analysis of the gamma ray energy and the intensity of the copper slag.
2. The copper slag component content detection device based on neutron activation gamma energy spectrum analysis according to claim 1, wherein the copper slag component content detection device is characterized in that: the gamma energy spectrum detector (1) is a lanthanum bromide detector, the diameter and the length of detector crystals are 7.62cm, and the energy resolution ratio of 661keV gamma rays is higher than 3.5%.
3. The copper slag component content detection device based on neutron activation gamma energy spectrum analysis according to claim 1, wherein the copper slag component content detection device is characterized in that: the gamma detector shielding body (2) is made of 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 (1) to the gamma rays of the copper slag (5) is improved.
4. The copper slag component content detection device based on neutron activation gamma energy spectrum analysis according to claim 1, wherein the copper slag component content detection device is characterized in that: the first neutron reflection layer (3) and the second neutron reflection layer (7) are made of high-purity graphite, and the thickness of the first neutron reflection layer is 5-15 cm.
5. The copper slag component content detection device based on neutron activation gamma energy spectrum analysis according to claim 1, wherein the copper slag component content detection device is characterized in that: the thickness of the thermal neutron absorber (4) is 1cm.
6. The copper slag component content detection device based on neutron activation gamma energy spectrum analysis according to claim 1, wherein the copper slag component content detection device is characterized in that: the gamma ray shielding body (6) is made of old lead, the lead content is higher than 99.99%, and the gamma ray shielding body is formed by splicing a plurality of dovetail-shaped lead bricks, wherein the thickness of the lead bricks is 5cm.
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| CN202210174070.3A CN114545485B (en) | 2022-02-24 | 2022-02-24 | Copper slag component content detection device based on neutron activation gamma energy spectrum analysis |
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| 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 |
| CN102175702A (en) * | 2010-11-22 | 2011-09-07 | 贾文宝 | Online detecting device of coal components |
| 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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| 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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