CN201421503Y - Handhold neutron-gamma radiation detector - Google Patents
Handhold neutron-gamma radiation detector Download PDFInfo
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- CN201421503Y CN201421503Y CN2009200694411U CN200920069441U CN201421503Y CN 201421503 Y CN201421503 Y CN 201421503Y CN 2009200694411 U CN2009200694411 U CN 2009200694411U CN 200920069441 U CN200920069441 U CN 200920069441U CN 201421503 Y CN201421503 Y CN 201421503Y
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- neutron
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- radiation detector
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Abstract
The utility model provides a handhold neutron-gamma radiation detector which comprises a neutron probe, a gamma probe and an electronic system used for treating signals of the neutron probe and signals of the gamma probe, wherein the signal output end of the neutron probe and the signal output end of the gamma probe are respectively connected with the signal input end of the electronic system, andthe neutron probe is arranged in a neutron moderator. A <6>LiI (Eu) scintillation crystal is adopted as a neutron detecting element, a CsI crystal is adopted as a gamma detecting element, the <6>LiI(Eu) scintillation crystal and the CsI crystal have sensitive response to neutron and gamma radiation, can measure the radiation level at the surrounding environment, also can add up the radiation dose, provides a new safety guarantee for the field of domestic accident emergency response, border control, customs detection, nuclear power plant safety protection and the like, has favorable social and economic benefits, provides an entirely new choice for the technical field of security, personal protection and environmental radiation monitor, and realizes the purpose of the utility model.
Description
Technical field
The utility model relates to a kind of radiation detector, particularly a kind of hand-held neutron-gamma radiation detector multiple functional and easy to carry that is applied to security, personal protection and environs radiation monitoring field.
Background technology
Preventing that radiomaterial from illegally transporting, seek radioactive source out of control in the accident, in the processes such as antinucleus terrorist incident and arms control verification activity, need radiation detector can detect neutron and gamma rays simultaneously, confirm radioactive source and radiocontamination kind and pollution level etc. quickly and accurately, for formulation protection plan, decision-making protection action provide master data.
At present, the technology of surveying gamma radiation both at home and abroad is very ripe, and the abundant personal dosimeter of kind is not only arranged, and has also occurred portable isotope identifier in succession, and they are in personal protection, safety inspection, and fields such as environmental protection and health care all are widely used.
Current radiation detector mainly is the neutron dose equivalent instrument that adopts reflective neutron-gamma personal dosimeter or adopt large-scale slow body, reflective neutron-gamma personal dosimeter can't carry out the measurement of fast neutron, can only measure the thermal neutron after the slowing down, cause reflective neutron-gamma personal dosimeter after leaving reflecting body, its sensitivity plunges and causes measuring serious distortion; The neutron dose equivalent instrument adopts BF usually owing to require that the neutron (0.025eV-20MeV) of broad energy range is all had response
3Proportional counter tube or
3He pipe coupling electrooptical device photomultiplier is as the neutron detection element, and adopting diameter is tygon ball about 20cm or the post slow body as neutron, and complete machine weight is many more than 10 kilograms, therefore, the general volume of neutron dose equivalent instrument is big and heavy, is difficult to portable.
In recent years, China's neutron application technology development is very rapid, neutron well logging, neutron bring out well logging, neutron photography, neutron and control cancer, neutron activation analysis etc. and be used widely, and China's nuclear power cause will have fast development before the year two thousand twenty, plan 31 at newly-built million kilowatt nuclear power station.Therefore, to neutron detection huge demand will be arranged.
At present, realize that the method for neutron detection mainly contains nuclear reaction method, the method for nuclear recoil, nuclear fission method and nuclear activation method, wherein nuclear reaction method is simple because of method, and test accurately is most widely used fast.The detector that utilizes the nuclear reaction method to survey neutron mainly contains
3He proportional counter tube, BF
3Proportional counter tube and
6LiI (Eu) scintillation crystal.Domestic having is respectively the product of neutron probe with the former two, and major part all is heavy A-B type rem instrument, is unsuitable for outdoor portably using.
6LiI (Eu) scintillation crystal has thermal neutron detection efficiency height, highly sensitive and neutron, gamma and screens advantages such as ability is good.
In sum, the radiation detector of using in environmental monitoring, radioactive source search and security monitoring at present exists and detects inaccurate or be difficult to portable shortcoming.
The utility model content
The purpose of this utility model is to provide a kind of hand-held neutron-gamma radiation detector, remedies the defective that above existing radiation detector exists, and simple in structure, volume is small and exquisite, and is in light weight, is easy to carry, easy to use.
The technical matters that the utility model solved can realize by the following technical solutions:
A kind of hand-held neutron-gamma radiation detector is characterized in that, it comprises neutron probe, gamma probe and the electronic system that the signal of described neutron probe and gamma probe is handled; The signal output part of described neutron probe and gamma probe is connected to the signal input part of described electronic system, and described neutron probe is arranged in the moderation of neutrons body.
In an embodiment of the present utility model, described neutron probe comprises screening can, neutron detection element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit, described neutron detection element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are arranged in the described screening can, described neutron detection element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are connected to each other successively, the signal input part of the described electronic system of output termination of described charge-sensitive pre-amplification circuit.
In an embodiment of the present utility model, described gamma probe comprises screening can, gamma detecting element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit, described gamma detecting element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are arranged in the described screening can, described gamma detecting element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are connected to each other successively, the signal input part of the described electronic system of output termination of described charge-sensitive pre-amplification circuit.
Photoelectric commutator in described neutron probe and the gamma probe is a photodiode.
In an embodiment of the present utility model, described electronic system comprises amplifier, discriminator, counter, controller, display and power supply, the signal input part of described amplifier connects the signal output part of described neutron probe and gamma probe respectively, the signal output part of described amplifier connects discriminator, counter and controller successively, described display is connected with controller, and described power supply is connected with amplifier, discriminator, counter, controller and display respectively.
Described power supply is that 5V can rechargeable repeatedly lithium battery.
In an embodiment of the present utility model, described neutron probe be one by
6LiI (Eu) scintillation crystal is as the neutron probe of neutron detection element.
In an embodiment of the present utility model, described gamma probe is one by the gamma probe of CsI (Tl) scintillation crystal as the gamma detecting element.
In an embodiment of the present utility model, described moderation of neutrons body is the goalpost shape moderation of neutrons body that high density polyethylene processes.
The thickness of described moderation of neutrons body is 2-6cm.
Described neutron probe is arranged on the geometric center of described moderation of neutrons body.
Hand-held neutron of the present utility model-gamma radiation detector has following characteristics:
(1) uses
6LiI (Eu) scintillation crystal substitutes BF
3Proportional counter tube and
3The He pipe is as the neutron detection element, replaces the G-M pipe as the gamma detecting element with the CsI crystal, and the extra small photodiode of matched volume makes neutron probe and gamma probe size small and exquisite as photo-electric conversion element, is very suitable for doing portable instrument;
(2) bread one deck high density polyethylene slow body outside described neutron probe, the tygon slow body makes the sensitivity of neutron probe higher between 2-6cm;
(3) adopt photodiode to make electrooptical device in described neutron probe and the gamma probe, complete machine need not to provide high pressure, has simplified the structure of instrument greatly.
A kind of hand-held neutron of the present utility model-gamma radiation detector adopts
6LiI (Eu) scintillation crystal is as the neutron detection element, adopt the CsI crystal as the gamma detecting element, sensitive to neutron and gamma radiation response, but measurement environment ambient radiation level, also can add up radiation dose, for fields such as domestic accident emergency response, border control, customs's detection and nuclear plant safety protection provide new safety guarantee, good society and economic benefit are arranged, for security, personal protection and environs radiation monitoring technical field provide a kind of brand-new selection, realize the purpose of this utility model.
Description of drawings
Fig. 1 is the structural representation of hand-held neutron of the present utility model-gamma radiation detector;
Fig. 2 is the inner structure synoptic diagram of neutron probe of the present utility model;
Fig. 3 is the inner structure synoptic diagram of gamma probe of the present utility model;
Fig. 4 is the cross-sectional view of slow body of the present utility model;
Fig. 5 is the structured flowchart of electronic system of the present utility model.
Embodiment
For technological means, creation characteristic that the utility model is realized, reach purpose and effect is easy to understand, below in conjunction with concrete diagram, further set forth the utility model.
As shown in Figure 1, a kind of hand-held neutron-gamma radiation detector, it comprises neutron probe 10, gamma probe 20 and electronic system 40, gamma probe 20 places the rear portion of neutron probe 10, neutron probe 10 is arranged in the moderation of neutrons body 30, the signal output part of neutron probe 10 and gamma probe 20 is connected to the signal input part of electronic system 40, and the signal of 40 pairs of neutron probe 10 of electronic system and gamma probe 20 is handled.
As shown in Figure 2, neutron probe 10 comprises screening can 110, neutron detection element 120, optical conductor 130, photoelectric commutator 140 and charge-sensitive pre-amplification circuit 150, neutron detection element 120, optical conductor 130, photoelectric commutator 140 and charge-sensitive pre-amplification circuit 150 are arranged in the screening can 110, neutron detection element 120, optical conductor 130, photoelectric commutator 140 and charge-sensitive pre-amplification circuit 150 are connected to each other successively, the signal input part of the output termination electronic system 40 of charge-sensitive pre-amplification circuit 150.
As shown in Figure 3, gamma probe 20 comprises screening can 210, gamma detecting element 220, optical conductor 230, photoelectric commutator 240 and charge-sensitive pre-amplification circuit 250, gamma detecting element 220, optical conductor 230, photoelectric commutator 240 and charge-sensitive pre-amplification circuit 250 are arranged in the screening can 210, gamma detecting element 220, optical conductor 230, photoelectric commutator 240 and charge-sensitive pre-amplification circuit 250 are connected to each other successively, the signal input part of the output termination electronic system 40 of charge-sensitive pre-amplification circuit 250.
The gamma detecting element 220 of gamma probe 20 adopts CsI (Tl) scintillation crystal, and screening can 210 adopts the screening can of aluminum.
In the present embodiment, the photoelectric commutator 240 of the photoelectric commutator 140 of neutron probe 10 and gamma probe 20 is photodiode (shore pine S3590-08); Neutron probe 10 by
6LiI (Eu) scintillation crystal coupling light electric diode is formed, gamma probe 20 CsI by 3cc (Tl) scintillation crystal coupling light electric diode is formed, neutron probe 10 and gamma probe 20 radiation levels of testing respectively under neutron and the gamma mixing field separately, and by trying to achieve dosage and accumulated dose separately after fluence and the dose equivalent conversion.
As shown in Figure 5, electronic system 40 comprises amplifier 410,420, discriminator 430, counter 440, controller 450, display 460 and power supply 470, amplifier 410,420 signal input part connects the signal output part of neutron probe 10 and gamma probe 20 respectively, from neutron probe 10 and the next signal process amplifier 410 of gamma probe 20 outputs, after 420 amplifications, entering into discriminator 430 again screens, the examination threshold value of neutron probe 10 and gamma probe 20 is respectively 100mv and 64mv, enter into counter 440 through the signal of screening and carry out accurate counting, input controller 450, controller 450 shows by operation interface, controls such as storage and warning, data show by display 460; Power supply 470 is connected power supply with amplifier 410,420, discriminator 430, counter 440, controller 450 and display 460 respectively, and power supply 470 can rechargeable repeatedly lithium battery for 5V, and discriminator 430 and controller 450 can be designed to integral structure.
By corresponding experiment measuring,
241Under the Am-Be source, the neutron response that records is 0.4-0.5CPS/ (μ Sv.h
-1),
137Under the Cs source, the gamma sensitivity that records is greater than 120CPS/ (μ Sv.h
-1), more than the index of two sensitivity in quasi-instrument, all be in forward level, we can say that hand-held neutron of the present utility model-gamma detector successfully realized highly sensitive and portable advantage simultaneously.
More than show and described ultimate principle of the present utility model and principal character and advantage of the present utility model.The technician of the industry should understand; the utility model is not restricted to the described embodiments; that describes in the foregoing description and the instructions just illustrates principle of the present utility model; under the prerequisite that does not break away from the utility model spirit and scope; the utility model also has various changes and modifications; these changes and improvements all fall in claimed the utility model scope, and the claimed scope of the utility model is defined by appending claims and equivalent thereof.
Claims (11)
1, a kind of hand-held neutron-gamma radiation detector is characterized in that, it comprises neutron probe, gamma probe and the electronic system that the signal of described neutron probe and gamma probe is handled; The signal output part of described neutron probe and gamma probe is connected to the signal input part of described electronic system, and described neutron probe is arranged in the moderation of neutrons body.
2, hand-held neutron as claimed in claim 1-gamma radiation detector, it is characterized in that: described neutron probe comprises screening can, the neutron detection element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit, described neutron detection element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are arranged in the described screening can, described neutron detection element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are connected to each other successively, the signal input part of the described electronic system of output termination of described charge-sensitive pre-amplification circuit.
3, hand-held neutron as claimed in claim 1-gamma radiation detector, it is characterized in that: described gamma probe comprises screening can, the gamma detecting element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit, described gamma detecting element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are arranged in the described screening can, described gamma detecting element, optical conductor, photoelectric commutator and charge-sensitive pre-amplification circuit are connected to each other successively, the signal input part of the described electronic system of output termination of described charge-sensitive pre-amplification circuit.
4, as claim 2 or 3 described hand-held neutron-gamma radiation detectors, it is characterized in that: described photoelectric commutator is a photodiode.
5, hand-held neutron as claimed in claim 1-gamma radiation detector, it is characterized in that: described electronic system comprises amplifier, discriminator, counter, controller, display and power supply, the signal input part of described amplifier connects the signal output part of described neutron probe and gamma probe respectively, the signal output part of described amplifier connects discriminator, counter and controller successively, described display is connected with controller, and described power supply is connected with amplifier, discriminator, counter, controller and display respectively.
6, hand-held neutron as claimed in claim 5-gamma radiation detector is characterized in that: described power supply is that 5V can rechargeable repeatedly lithium battery.
7, hand-held neutron as claimed in claim 1-gamma radiation detector is characterized in that: described neutron probe be one by
6LiI (Eu) scintillation crystal is as the neutron probe of neutron detection element.
8, hand-held neutron as claimed in claim 1-gamma radiation detector is characterized in that: described gamma probe is one by the gamma probe of CsI (T1) scintillation crystal as the gamma detecting element.
9, hand-held neutron as claimed in claim 1-gamma radiation detector is characterized in that: described moderation of neutrons body is the goalpost shape moderation of neutrons body that high density polyethylene processes.
10, hand-held neutron as claimed in claim 9-gamma radiation detector, it is characterized in that: the thickness of described moderation of neutrons body is 2-6cm.
11, hand-held neutron as claimed in claim 1-gamma radiation detector, it is characterized in that: described neutron probe is arranged on the geometric center of described moderation of neutrons body.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009200694411U CN201421503Y (en) | 2009-03-26 | 2009-03-26 | Handhold neutron-gamma radiation detector |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009200694411U CN201421503Y (en) | 2009-03-26 | 2009-03-26 | Handhold neutron-gamma radiation detector |
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| CN201421503Y true CN201421503Y (en) | 2010-03-10 |
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ID=41808163
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| CN2009200694411U Expired - Fee Related CN201421503Y (en) | 2009-03-26 | 2009-03-26 | Handhold neutron-gamma radiation detector |
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Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102043161A (en) * | 2010-03-16 | 2011-05-04 | 上海新漫传感技术研究发展有限公司 | Ambient neutron dose equivalent meter |
| CN102043160A (en) * | 2010-03-12 | 2011-05-04 | 上海新漫传感技术研究发展有限公司 | Card type personal neutron dosimeter |
| CN102445706A (en) * | 2011-09-26 | 2012-05-09 | 华瑞科学仪器(上海)有限公司 | Neutron detector |
| CN102540270A (en) * | 2011-12-14 | 2012-07-04 | 上海新漫传感技术研究发展有限公司 | Device for monitoring and identifying radioactive substances |
| CN102778687A (en) * | 2012-05-17 | 2012-11-14 | 河南师范大学 | Nuclear radiation detector |
| CN103339528A (en) * | 2010-11-12 | 2013-10-02 | 圣戈本陶瓷及塑料股份有限公司 | Radiation detection system and a method of using the same |
| CN104807391A (en) * | 2014-01-27 | 2015-07-29 | 核工业航测遥感中心 | Solid radium source central point measuring instrument and detecting method thereof |
| CN107505648A (en) * | 2017-08-23 | 2017-12-22 | 绵阳美菱软件技术有限公司 | A kind of air-conditioning remote control |
| CN110320547A (en) * | 2018-03-30 | 2019-10-11 | 中国辐射防护研究院 | Integrated form wide-range gamma neutron detection device |
| CN113138404A (en) * | 2021-04-02 | 2021-07-20 | 中国舰船研究设计中心 | Neutron, gamma integration electronic type dose monitoring devices |
| CN113138405A (en) * | 2021-04-02 | 2021-07-20 | 中国舰船研究设计中心 | Personal dosage monitoring and management system and method for ship |
-
2009
- 2009-03-26 CN CN2009200694411U patent/CN201421503Y/en not_active Expired - Fee Related
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102043160A (en) * | 2010-03-12 | 2011-05-04 | 上海新漫传感技术研究发展有限公司 | Card type personal neutron dosimeter |
| CN102043161A (en) * | 2010-03-16 | 2011-05-04 | 上海新漫传感技术研究发展有限公司 | Ambient neutron dose equivalent meter |
| CN103339528A (en) * | 2010-11-12 | 2013-10-02 | 圣戈本陶瓷及塑料股份有限公司 | Radiation detection system and a method of using the same |
| CN103339528B (en) * | 2010-11-12 | 2015-09-23 | 圣戈本陶瓷及塑料股份有限公司 | Radiation detection system and using method thereof |
| CN102445706A (en) * | 2011-09-26 | 2012-05-09 | 华瑞科学仪器(上海)有限公司 | Neutron detector |
| CN102540270A (en) * | 2011-12-14 | 2012-07-04 | 上海新漫传感技术研究发展有限公司 | Device for monitoring and identifying radioactive substances |
| CN102778687B (en) * | 2012-05-17 | 2016-08-24 | 河南师范大学 | A kind of nuclear radiation detector |
| CN102778687A (en) * | 2012-05-17 | 2012-11-14 | 河南师范大学 | Nuclear radiation detector |
| CN104807391A (en) * | 2014-01-27 | 2015-07-29 | 核工业航测遥感中心 | Solid radium source central point measuring instrument and detecting method thereof |
| CN107505648A (en) * | 2017-08-23 | 2017-12-22 | 绵阳美菱软件技术有限公司 | A kind of air-conditioning remote control |
| CN110320547A (en) * | 2018-03-30 | 2019-10-11 | 中国辐射防护研究院 | Integrated form wide-range gamma neutron detection device |
| CN113138404A (en) * | 2021-04-02 | 2021-07-20 | 中国舰船研究设计中心 | Neutron, gamma integration electronic type dose monitoring devices |
| CN113138405A (en) * | 2021-04-02 | 2021-07-20 | 中国舰船研究设计中心 | Personal dosage monitoring and management system and method for ship |
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| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20100310 Termination date: 20180326 |