CN1834632A - Concrete material content on-line detection system based on pulse fast heating neutron instantaneous Gamna radiation malysis tech - Google Patents
Concrete material content on-line detection system based on pulse fast heating neutron instantaneous Gamna radiation malysis tech Download PDFInfo
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- CN1834632A CN1834632A CN 200610039603 CN200610039603A CN1834632A CN 1834632 A CN1834632 A CN 1834632A CN 200610039603 CN200610039603 CN 200610039603 CN 200610039603 A CN200610039603 A CN 200610039603A CN 1834632 A CN1834632 A CN 1834632A
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Abstract
This invention discloses pulse fast heat neutron prompt gamma cement material component online detecting system, it is aimed at status that need to online detecting cement material chemical components. It includes neutron generator, slowing down body, gamma ray detector, and complex shield safeguard system. Conveying belt crosses over the safeguard system, cement material need to be detected is on the belt, the slowing down body, neutron generator are fixed in the system and below the belt, two or more than two gamma ray detectors are fixed in the system and above the material, it is connected to digital amplifier systemthrough transmission line, the system, data getting system, data analysis system and data display system are in turn connected, so it can detect chemical components of the cement material and provide information for feed proportioning system to improve cement quality.
Description
Technical field
The utility model relates to a kind of on-line measuring device, especially a kind of pick-up unit of composition of the cement raw material of carrying on can online detection band conveyor, specifically a kind of based on the cement material composition on-line detecting system of sending out gamma (γ) ray analysis technology the fast thermal neutron of pulse wink.
Background technology
As everyone knows, the quality of cement and raw material composition are closely related, in order to guarantee the qualification rate of cement, must carry out strict control to raw material, and carry out the adjustment of raw material in good time, therefore must regularly carry out analysis of components, so that in time submitting necessary information at the batching station to the cement raw material on the conveying belt, at present, the method that generally adopts is the sampling off-line analysis mostly.This method sampling is few, and real-time is poor, and is representative poor, can not in time feed back the information of cement raw material, causes the hysteresis of information, belongs to afterwards and remedies, and does not utilize and improves the quality of products.
In recent years, the neutron prompt gamma-ray analysis technology (be called for short PGNAA) of inducting has become a kind of new detection means in the modern analytical technique.It is by examining with atoms of elements in the fast thermal neutron stream bombardment material, in very short time, launch gamma-rays with the atomic nucleus that neutron reacts, this part gamma-rays has carried information such as element kind and content, as long as analyze the on-line analysis that this part ray just can be realized the full element of material, but according to the knowledge of the applicant, still do not have at present a kind of PGNAA of utilization technology can carry out the device of dynamic on-line analysis to the cement raw material that belt is carried can be for selecting for use.
Summary of the invention
The purpose of this utility model is at being badly in need of the present situation that a kind of energy online in real time detects the cement raw material chemical analysis in the market, designing and send out gamma cement material composition on-line detecting system a kind of pulse fast neutron wink.
The technical solution of the utility model is:
A kind of based on the cement material composition on-line detecting system of sending out gamma (γ) ray analysis technology the fast thermal neutron of pulse wink, comprise neutron generator 1, slow body 2, gamma ray detector 5, electronic amplification system 7, data-acquisition system 8, computer data is handled and display system 9, composite shielding guard system 10, it is characterized in that conveying belt 3 passes composite shielding guard system 10, cement raw material 4 to be detected is positioned at and drives on its conveying belt that advances 3, slow body 2 is installed in the composite shielding guard system 10 and is positioned at the below of conveying belt 3, neutron generator 1 also is installed in the composite shielding guard system 10 and is positioned at the below of slow body 2, above cement raw material 4, two gamma ray detectors 5 are installed in the composite shielding guard system 10 at least, they link to each other with electronic amplification system 7 by transmission line, electronic amplification system 7 links to each other with data-acquisition system 8, and data-acquisition system 8 is handled with computer data and linked to each other with display system 9.
The neutron average energy of described neutron generator 1 emission is 14MeV.
Described composite shielding guard system 10 is by plumbous, tygon and contain boron polyethylene and form.
Described slow body 2 is constituted by lead layer and polyethylene layer, and their thickness ratio is lead layer: polyethylene layer=1: 0.4-0.8, their gross thickness is 8-10cm.
Described electronic amplification system 7 is made up of pre-amplification circuit, comparison amplifying circuit, high-pass filtering circuit, low-pass filter circuit, ratio amplifying circuit and follower; Pre-amplification circuit is by amplifier A1; A2 and peripheral resistance R 1 thereof; R2; R3; R4; R5; capacitor C 1 constitutes; the signal that connects gamma ray detector 5 outputs is drawn in its input from the inverting input of amplifier A1; its output is drawn from the output terminal of amplifier A2 and is connect the comparison amplifying circuit; input end at amplifier A1 is connected to by diode CR1; the holding circuit that CR2 constitutes; it is used to prevent the too high damage pre-amplification circuit of applied signal voltage; relatively amplifying circuit is by amplifier A3; transistor Q1 and resistance R 6; R7; R8; R9; R10; R11; R12 and diode CR3 constitute; its input is drawn the output terminal that the output that connects pre-amplification circuit is amplifier A2 from the in-phase input end of amplifier A3; the inverting input of amplifier A3 connects the collector of transistor Q1 to obtain comparison signal voltage; relatively the output of amplifying circuit is drawn from the output terminal of amplifier A3 and is connect high-pass filtering circuit; high-pass filtering circuit is by amplifier A4; A5; capacitor C 2; C3; C4; resistance R 13; R14; R15; R16 constitutes; its input is drawn the output terminal that the output that connects the comparison amplifying circuit is amplifier A3 from the in-phase input end of amplifier A4; its output is drawn from the output terminal of amplifier A5 and is connect low-pass filter circuit; low-pass filter circuit is by amplifier A6; A7; resistance R 17; R18; capacitor C 5; C6; C7 constitutes; its input is drawn the output terminal that the output that connects high-pass filtering circuit is amplifier A5 from the in-phase input end of amplifier A6; its output is drawn from the output terminal of amplifier A7 and is connect by amplifier A8 and resistance R 19; the input of the ratio amplifying circuit that R20 constitutes is the in-phase input end of amplifier A8; the output of ratio amplifying circuit is drawn the in-phase input end that the input that connects the follower that is made of amplifier A9 is amplifier A9 from the output terminal of amplifier A8, and the output of follower is drawn the input end that connects data-acquisition system 8 from the output terminal of amplifier A9.
The utlity model has following advantage:
The utlity model has and need not sampling, full logistics, full elemental analysis, speed fast (1～2 minute), precision height, safe and reliable characteristics.By the elementary composition content in this equipment real-time online check and analysis cement material, can control classify and pile up, control batching automatically automatically, and then the serviceable life of improving mining site, improve cement quality.
The utility model also can be used for the similarly real-time occasion that detects of the online chemical analysis of needs.
Description of drawings
Fig. 1 is a structured flowchart synoptic diagram of the present utility model.
Fig. 2 is the electrical schematic diagram of electronic amplification system of the present utility model
Embodiment
Below in conjunction with accompanying drawing and enforcement the utility model is further described.
As shown in Figure 1.
A kind of based on the cement material composition on-line detecting system of sending out the gamma rays analytical technology the fast thermal neutron of pulse wink, comprise neutron generator 1, slow body 2, two (or more than two) gamma ray detector 5, electrical control cubicles 6, electronic amplification system 7, data-acquisition system 8, computer data is handled and display system 9, composite shielding guard system 10, wherein electrical control cubicles 6, electronic amplification system 7, data-acquisition system 8, computer data is handled and display system 9 is installed in the pulpit, neutron generator 1, slow body 2, gamma ray detector 5, conveying belt 3 is installed in the composite shielding guard system 10, conveying belt 3 passes composite shielding guard system 10, cement raw material 4 to be detected is positioned at and drives on its conveying belt that advances 3, slow body 2 is installed in the composite shielding guard system 10 and is positioned at the below of conveying belt 3, neutron generator 1 also is installed in the composite shielding guard system 10 and is positioned at the below of slow body 2, the operating voltage of neutron generator 1, orders etc. are by electrical control cubicles 6 controls, gamma ray detector 5 is installed in the composite shielding guard system 10 and is positioned at the top of cement raw material 4, it is controlled by electrical control cubicles 6 on the one hand, link to each other with electronic amplification system 7 by transmission line on the other hand, electronic amplification system 7 links to each other with data-acquisition system 8, and data-acquisition system 8 is handled with computer data and linked to each other with display system 9.
In present embodiment:
Neutron generator 1 can adopt electric controlled D-T neutron generator that Xi-an Petroleum Prospecting Instrument Gen. Factory neutron generator company produces, U.S. MF Physics neutron generator, French Sodren neutron generator, Russian ALL-RUSSIA INSTITUTE OF AUTOMATICS RF MINATOM neutron generator or German EADS company neutron generator.
Slow body 2 can adopt lead add tygon routinely technology made, mainly constitute by lead layer and polyethylene layer, their thickness ratio is lead layer: polyethylene layer=1: 0.4-0.8, their gross thickness is 8-10cm.
Gamma ray detector 5 can adopt the BGO crystal counter (as: Φ 4 that Proteus, Inc. produce " * 3 " Φ 5 that produces of BGO crystal counter or French Saint-Gobain " * 3 " the BGO crystal counter.
Electrical control cubicles 6 is conventional electrical control cubicles, general electrical technology personnel all can design according to the parameter of request for utilization and pertinent instruments, have no special requirements, wherein topmost one is voltage source (model can be BH1222), the 2nd, and high-voltage power supply (model can be Spellman SL130kV).
Electronic amplification system 7 mainly is made up of prime amplifier (model can be FH1048A) and linear amplifier (can adopt the BH1218 of Beijing Nuclear Instrument Factory), it mainly acts on is that the signal that gamma ray detector 5 is sent is handled and amplified, electronic amplification system 7 also can adopt circuit diagram shown in Figure 2 to be realized in addition, and it is made up of pre-amplification circuit, comparison amplifying circuit, high-pass filtering circuit, low-pass filter circuit, ratio amplifying circuit and follower; Pre-amplification circuit is by amplifier A1 (model can be AD829), A2 (model can be AD829) and peripheral resistance R 1 thereof, R2, R3, R4, R5; capacitor C 1 constitutes; the signal that connects gamma ray detector 5 outputs is drawn in its input from the inverting input of amplifier A1; its output is drawn from the output terminal of amplifier A2 and is connect the comparison amplifying circuit; input end at amplifier A1 is connected to the holding circuit that is made of diode CR1, CR2, and it is used to prevent the too high damage pre-amplification circuit of applied signal voltage.Relatively amplifying circuit is by amplifier A3 (model can be AD811), transistor Q1 (model can be 2222N) and resistance R 6, R7, R8, R9, R10, R11, R12 and diode CR3 constitute, its input is drawn the output terminal that the output that connects pre-amplification circuit is amplifier A2 from the in-phase input end of amplifier A3, the inverting input of amplifier A3 connects the collector of transistor Q1 to obtain comparison signal voltage, relatively the output of amplifying circuit is drawn from the output terminal of amplifier A3 and is connect high-pass filtering circuit, high-pass filtering circuit is by amplifier A4 (model can be AD829), A5 (model can be AD829), capacitor C 2, C3, C4, resistance R 13, R14, R15, R16 constitutes, its input is drawn the output terminal that the output that connects the comparison amplifying circuit is amplifier A3 from the in-phase input end of amplifier A4, its output is drawn from the output terminal of amplifier A5 and is connect low-pass filter circuit, low-pass filter circuit is by amplifier A6 (model can be AD829), A7 (model can be AD829), resistance R 17, R18, capacitor C 5, C6, C7 constitutes, its input is drawn the output terminal that the output that connects high-pass filtering circuit is amplifier A5 from the in-phase input end of amplifier A6, its output is drawn from the output terminal of amplifier A7 and is connect by amplifier A8 (model can be AD829) and resistance R 19, the input of the ratio amplifying circuit that R20 constitutes is the in-phase input end of amplifier A8, it is the in-phase input end of amplifier A9 that the output of ratio amplifying circuit is drawn the input that connects the follower that is made of amplifier A9 (model can be AD829) from the output terminal of amplifier A8, and the output of follower is drawn the input end that connects data-acquisition system 8 from the output terminal of amplifier A9.
The principle of work of above-mentioned electronic amplification system 7 is:
(1) Singal In represents the signal input, connects the signal of gamma ray detector 5 outputs, and this signal is a current signal, transforms through R1, R2, A1 and is enlarged into voltage signal, and voltage signal is through R3, R4, the anti-phase amplification of R5, A2.Diode CR1, CR2 prevented that large-signal from entering amplifier A1, and diode CR3 (being stabilivolt) prevented that large-signal from entering amplifier A2, all shielded.R6, R7, A3 form homophase and amplify, and R8, R9, R10, R12, Q1 provide dc offset voltage for this homophase amplifies, and output terminal is fluctuateed near bias voltage.C1 is a building-out capacitor, and R11 is a build-out resistor.
(2) C2, C3, C4, R13, R14, R15, A4, A5 form Hi-pass filter, and cutoff frequency is about 100KHz; C5, C6, C7, R16, R17, R18, A6, A7 form low-pass filter, and cutoff frequency is about 10MHz, and the two constitutes bandpass filter, and gain trace is with the velocity attenuation of 40dB.R19, R20, A8 constitute homophase and amplify, the regulating system gain.A9 is used for voltage follow, reduces output impedance, strengthens driving force, and Singal Out represents signal output.
Data-acquisition system 8 can adopt multichannel spectrometer to be realized (can adopt the ASA-100 of canberra company and the special high-accuracy digitizing multichannel spectrometer DL1024 of continent development).
Computer data is handled and display system 9 mainly is made up of computing machine and software, and the computing machine that computing machine can adopt IBM Corporation to produce, software can adopt the analysis software dlcna001 based on spectrum storehouse dlmc.
Composite shielding guard system 10 is by lead+tygon+contain the radiation proof case structure body that boron polyethylene is formed, and also can adopt the patent No. is 2004200802856 the disclosed structure of Chinese patent.
The course of work of the present utility model is:
The electric controllable pulse neutron generator 1 of electrical control cubicles 6 controls produces pulse fast neutron (14MeV), the pulse fast neutron is the fast thermal neutron of a certain proportion of pulse by slow body 2 slowing downs, the fast thermal neutron of pulse passes transmission belt 3 and shines on the cement 4 on the transmission belt, non-bullet nuclear reaction takes place in the C in pulse fast neutron and the cement, O nucleic, send and wink send out bullet feature gamma-rays non-, the main nucleic generation of in pulse thermal neutron and the cement all other capturing nucleus reaction is sent and is sent out feature wink and capture gamma-rays.By two or more gamma-ray detectors 5 (BGO detector), according to pulse sequence, write down non-bullet feature gamma-rays respectively and capture the feature gamma-rays, change these feature gamma-rays into electric impulse signal, by electronics circuit 7 signal is amplified, carry out the record of gamma spectrum by cable transmission to data-acquisition system 8 (multichannel spectrometer) then, can be transferred to computer data processing and display system 9 by spectrum signal then, utilize the standard power spectrum storehouse of the material that has stored, analysis software by special use carries out data processing, last display analysis result.
Principle of work of the present utility model is:
Utilize electric controlled D-T neutron generator reaction to produce the 14MeV fast neutron, by slowing down, form the fast thermal neutron of a certain proportion of pulse, non-bullet scattering takes place in nucleic such as the C in fast neutron and the cement, O, produce and non-bullet wink send out the feature gamma-rays, utilize these rays can detect C, O element in the cement; Utilize the capture reaction generation of other essential element in thermal neutron and the cement to send out the feature gamma-rays wink, can detect other essential element Si, Al, Fe, Ca, Mg, Na, K, S except that C, O.According to pulse sequence, write down non-bullet feature gamma-rays respectively and capture feature gamma-rays power spectrum, utilize spectral library least square method analytical technology (is 2004100649846 patented claim in the application number of application in 2004 referring to the applicant), can provide the content (comprising C, O element) of all main nucleic in the cement.
Claims (5)
1, a kind of based on the cement material composition on-line detecting system of sending out the gamma rays analytical technology the fast thermal neutron of pulse wink, comprise neutron generator (1), slow body (2), gamma ray detector (5), electronic amplification system (7), data-acquisition system (8), computer data is handled and display system (9), composite shielding guard system (10), it is characterized in that conveying belt (3) passes composite shielding guard system (10), cement raw material to be detected (4) is positioned at and drives on its conveying belt that advances (3), slow body (2) is installed in the composite shielding guard system (10) and is positioned at the below of conveying belt (3), neutron generator (1) also is installed in the composite shielding guard system (10) and is positioned at the below of slow body (2), top in cement raw material (4), two gamma ray detectors (5) are installed in the composite shielding guard system (10) at least, they link to each other with electronic amplification system (7) by transmission line, electronic amplification system (7) links to each other with data-acquisition system (8), and data-acquisition system (8) is handled with computer data and linked to each other with display system (9).
2, according to claim 1 based on the cement material composition on-line detecting system of sending out the gamma rays analytical technology the fast thermal neutron of pulse wink, it is characterized in that the neutron average energy of described neutron generator (1) emission is 14MeV.
3, according to claim 1 based on the cement material composition on-line detecting system of sending out the gamma rays analytical technology the fast thermal neutron of pulse wink, it is characterized in that described composite shielding guard system (10) is by plumbous, tygon with contain boron polyethylene and form.
4, according to claim 1 based on the cement material composition on-line detecting system of sending out the gamma rays analytical technology the fast thermal neutron of pulse wink, it is characterized in that described slow body (2) is constituted by lead layer and polyethylene layer, their thickness ratio is, lead layer: polyethylene layer=1: 0.4-0.8, their gross thickness is 8-10cm.
5, according to claim 1 based on the cement material composition on-line detecting system of sending out the gamma rays analytical technology the fast thermal neutron of pulse wink, it is characterized in that described electronic amplification system (7) is made up of pre-amplification circuit, comparison amplifying circuit, high-pass filtering circuit, low-pass filter circuit, ratio amplifying circuit and follower; Pre-amplification circuit is by amplifier A1, A2 and peripheral resistance R 1 thereof, R2, R3, R4, R5, capacitor C 1 constitutes, the signal that connects gamma ray detector (5) output is drawn in its input from the inverting input of amplifier A1, its output is drawn from the output terminal of amplifier A2 and is connect the comparison amplifying circuit, relatively amplifying circuit is by amplifier A3, transistor Q1 and resistance R 6, R7, R8, R9, R10, R11, R12 and diode CR3 constitute, its input is drawn the output terminal that the output that connects pre-amplification circuit is amplifier A2 from the in-phase input end of amplifier A3, the inverting input of amplifier A3 connects the collector of transistor Q1 to obtain comparison signal voltage, relatively the output of amplifying circuit is drawn from the output terminal of amplifier A3 and is connect high-pass filtering circuit, high-pass filtering circuit is by amplifier A4, A5, capacitor C 2, C3, C4, resistance R 13, R14, R15, R16 constitutes, its input is drawn the output terminal that the output that connects the comparison amplifying circuit is amplifier A3 from the in-phase input end of amplifier A4, its output is drawn from the output terminal of amplifier A5 and is connect low-pass filter circuit, low-pass filter circuit is by amplifier A6, A7, resistance R 17, R18, capacitor C 5, C6, C7 constitutes, its input is drawn the output terminal that the output that connects high-pass filtering circuit is amplifier A5 from the in-phase input end of amplifier A6, its output is drawn from the output terminal of amplifier A7 and is connect by amplifier A8 and resistance R 19, the input of the ratio amplifying circuit that R20 constitutes is the in-phase input end of amplifier A8, the output of ratio amplifying circuit is drawn the in-phase input end that the input that connects the follower that is made of amplifier A9 is amplifier A9 from the output terminal of amplifier A8, and the output of follower is drawn the input end that connects data-acquisition system (8) from the output terminal of amplifier A9.
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| CN109690300A (en) * | 2016-06-09 | 2019-04-26 | 凤凰有限责任公司 | System and method for carrying out the active scan of nuclear fuel rod |
| CN108107062A (en) * | 2017-12-14 | 2018-06-01 | 东莞理工学院 | A kind of detection device of neutron radiation shield concrete |
| CN109747042A (en) * | 2017-12-14 | 2019-05-14 | 东莞理工学院 | A kind of radiation shield concrete slurry collocation mechanism of neutron research that can be detected |
| CN109747042B (en) * | 2017-12-14 | 2020-08-07 | 东莞理工学院 | Radiation-proof concrete paste configuration mechanism capable of detecting neutron research |
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