CN102043161A - Ambient neutron dose equivalent meter - Google Patents
Ambient neutron dose equivalent meter Download PDFInfo
- Publication number
- CN102043161A CN102043161A CN 201010294498 CN201010294498A CN102043161A CN 102043161 A CN102043161 A CN 102043161A CN 201010294498 CN201010294498 CN 201010294498 CN 201010294498 A CN201010294498 A CN 201010294498A CN 102043161 A CN102043161 A CN 102043161A
- Authority
- CN
- China
- Prior art keywords
- neutron
- dose equivalent
- probe
- moderation
- equivalent meter
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Images
Landscapes
- Measurement Of Radiation (AREA)
Abstract
The invention aims to disclose an ambient neutron dose equivalent meter. The ambient neutron dose equivalent meter is characterized by comprising a neutron probe, a neutron energy response adjustor and a control system, wherein a neutron detection element is arranged in the neutron probe, the neutron detection element is europium-doped lithium iodide scintillation crystal, the signal output end of the neutron probe is connected with the signal input end of the control system, and the neutron probe is placed at the position of the geometric center of the neutron energy response adjustor. Because the photomultiplier with high sensitivity is used as a photoelectric converter, the meter has light weight, portability, sensitive neutron response and good angle response, can accurately measure the ambient neutron dose equivalent level, has sound and light alarm function, is used for ambient neutron radiation monitoring of large nuclear facilities such as reactors, high-energy particle accelerators and the like, ensures neutron radiation safety of the ambient and the public, and fulfills the purpose of the invention.
Description
Technical field
The present invention relates to a kind of neutron detector, dose equivalent meter around particularly a kind of neutron that is used for neutron field monitoring.
Background technology
In recent years, China's neutron application technology development is rapid, and neutron well logging, neutron photography, neutron activation analysis etc. have been used widely, and nuclear facilities such as various accelerator neutron generators, nuclear power station, reactor and novel thermonuclear device are built in a large number; In addition, neutron also comes into one's own aspect the neutron radiation therapy day by day because of its unique biological characteristic.These nuclear facilities and neutron source application places can produce neutron irradiation in its surrounding environment, cause environmental pollution and the personnel health is sustained damage, so must monitor the neutron irradiation around nuclear facilities and the neutron source place.Have the occasion of neutron irradiation at these, the neutron dose equivalent is the routine monitoring project, and therefore, dose equivalent meter has the bigger market demand around the neutron of detected neutron dose equivalent.
At present, the method for detected neutron mainly contains nuclear reaction method, the method for nuclear recoil, nuclear fission method and nuclear activation method, and wherein nuclear reaction method is simple because of its method, and test accurately is most widely used fast.
Existing neutron detector mainly comprises gas detector, liquid scintillation agent detector and solid-state scintillator detector.Wherein, gas detector uses the gaseous state composition, as
3He and
10BF
3, need big relatively housing region hold the gaseous state composition, the volume ratio that occupies is bigger, makes its manufacturing and to have cost very high, and the instrument volume is big, and heaviness is difficult for portable; Similarly, also there is the relatively large shortcoming of volume in liquid scintillator.For the solid scintillator, its density is generally relatively large, and the panel detector structure of making is compact more, and therefore, the use of solid-state scintillator is popular day by day.
The solid-state scintillator that uses mainly contains and mixes europium at present
6The LiI crystal [
6LiI (Eu)], cerium activates
6Li-silicate glass etc., wherein, the europium of doping 0.06-0.08wt%
6The LiI crystal, it is considered to the most effective material that thermal neutron is surveyed in known being used to the energy resolution height of thermal neutron.
Around the existing neutron dose equivalent meter be mainly with
3He and
10BF
3As the neutron detection element, outside the neutron detection element, be surrounded by slow body and absorber, often sensitivity is lower, volume is excessive for these instruments, preponderance (about 10kg), is unsuitable for outdoorly carrying easily and using.At present, does not also have both at home and abroad and adopt the neutron dose equivalent meter on every side of mixing europium lithium iodide scintillation crystal.
Generally speaking, at present to the equipment of nuclear facilities and the monitoring of neutron source ambient radiation exist sensitivity not high, be difficult to portable shortcoming.
Therefore, need a kind of neutron dose equivalent meter on every side especially, in light weight, be easy to portable, to the neutron response sensitivity, accurately neutron irradiation level around the measurement environment is used for the environmental neutron Radiation monitoring of large-scale nuclear facilities such as reactor, high-energy particle accelerator, guarantees the surrounding environment and the public's neutron irradiation safety.
Summary of the invention
The object of the present invention is to provide dose equivalent meter around a kind of neutron, lower with the existing instrumental sensitivity of dose equivalent meter around solving existing neutron, volume is big, and heaviness is unsuitable for the outdoor problem that portably uses etc.
Technical matters solved by the invention can realize by the following technical solutions:
Dose equivalent meter around a kind of neutron, it is characterized in that, it comprises neutron probe, neutron energy response regulation body and control system, be provided with the neutron detection element in the described neutron probe, described neutron detection element is for mixing europium lithium iodide scintillation crystal, the signal output part of described neutron probe links to each other with the signal input part of described control system, and described neutron probe is placed on the position of the geometric center of described neutron energy response regulation body.
In one embodiment of the invention, described mix lithium in the europium lithium iodide scintillation crystal (
6Li) abundance is 0.01-99%, and the doping of europium is 0.001-1wt%.
Further, described mix lithium in the europium lithium iodide scintillation crystal (
6Li) abundance is 92%, and the doping of europium is 0.08wt%.
In one embodiment of the invention, described neutron probe comprises screening can, neutron detection element, photoconduction, photoelectric commutator and pre-amplification circuit, described neutron detection element, photoconduction, photoelectric commutator and pre-amplification circuit are connected successively mutually and are nested in the described screening can, and the output terminal of described pre-amplification circuit is connected with described control system.
Further, described photoelectric commutator is the highly sensitive photomultiplier of one group of coupling.
In one embodiment of the invention, described neutron energy response regulation body is made of moderation of neutrons body and the slow neutron absorption layer that is embedded in the moderation of neutrons body, and the center position at the rear portion of described moderation of neutrons body is provided with the pit that is used for described neutron probe is placed on its geometric center position.
Further, the front portion of described moderation of neutrons body is that class is round table-like, and the rear portion of described moderation of neutrons body is cylindric, and the outside surface of described moderation of neutrons body equates to the distance between the inside surface.
Further, described moderation of neutrons body is processed by high density polyethylene, and the thickness of described moderation of neutrons body is 6-12cm.
Further, described slow neutron absorption layer adopts the material of boracic or cadmium element to make, and the thickness of described slow neutron absorption layer is 0.5-8mm.
In one embodiment of the invention, described control system comprises amplifier, discriminator, counter, controller, display, hummer, LED light, low-tension supply and high-voltage power supply; Described amplifier, discriminator, counter and controller are connected to each other successively, described display, hummer, LED light are connected with described controller respectively, described low-tension supply is connected to each other with amplifier, discriminator, counter, controller, display and high-voltage power supply respectively, described high-voltage power supply and described neutron probe are connected to each other, and the signal input part of described amplifier and the signal output part of described neutron probe are connected to each other.
Further, described low-tension supply is that 16V can rechargeable repeatedly lithium ion battery.
Dose equivalent meter has following advantage around the neutron of the present invention:
(1) adopts the highly sensitive europium lithium iodide of mixing
6LiI (Eu) scintillation crystal replaces
3He reaches
10BF
3As the neutron detection element of dose equivalent meter around the neutron, and adopt large volume
6The photomultiplier that LiI (Eu) scintillation crystal coupling is highly sensitive, light-weight equipment and be convenient to portable use;
(2) outside neutron probe, be surrounded by the moderation of neutrons body of certain thickness high density polyethylene, the front portion of moderation of neutrons body is that class is round table-like, and the rear portion is a cylindricality, the slow neutron absorption layer that the material of embedding boracic or cadmium element is made in the slow body, energy response is easy to regulate, and angular response is good;
(3) thickness of moderation of neutrons body can reach the irrelevant performance of fluence rate sensitivity and neutron energy between 6-12cm, be convenient to demarcate and in-site measurement, and instrument is easy to carry.
(4) have sound, light warning function, be used for the environmental neutron Radiation monitoring of large-scale nuclear facilities such as reactor, high-energy particle accelerator, can guarantee the neutron source surrounding environment and the public's neutron irradiation safety.
Characteristics of the present invention can be consulted the detailed description of the graphic and following better embodiment of this case and be obtained to be well understood to.
Description of drawings
Describe the present invention in detail below in conjunction with the drawings and specific embodiments;
Fig. 1 is the structure diagram of dose equivalent meter around the neutron of the present invention;
Fig. 2 is the structural representation of neutron probe of the present invention;
Fig. 3 is the structural representation of neutron energy response regulation body of the present invention;
Fig. 4 is the structured flowchart of control system of the present invention.
Embodiment
For technological means, creation characteristic that the present invention is realized, reach purpose and effect is easy to understand, below in conjunction with embodiment, further set forth the present invention.
Around the neutron of the present invention dose equivalent meter be mainly used in solve existing neutron dose equivalent instrument since the detecting element of selecting for use in the neutron probe make that instrumental sensitivity is lower, volume big, heavy and be unsuitable for the outdoor problem that portably uses.
As shown in Figure 1, dose equivalent meter around the neutron of the present invention, it comprises neutron probe 10, neutron energy response regulation body 20 and control system 30; Wherein, when mounted, the signal output part of neutron probe 10 links to each other with the signal input part of control system 30, thereby in use can be easily signal by 30 pairs of neutron probe 10 of control system carry out simple process, neutron probe 10 is placed on the geometric center place of neutron energy response regulation body 20.
As shown in Figure 2, neutron probe 10 comprises screening can 11, neutron detection element 12, photoconduction 13, photoelectric commutator 14 and pre-amplification circuit 15, neutron detection element 12, photoconduction 13, photoelectric commutator 14 and pre-amplification circuit 15 are connected successively mutually and are nested in the screening can 11, and the output terminal of pre-amplification circuit 15 is connected with control system 30.(referring to Fig. 4)
In the present embodiment, described mix lithium in the europium lithium iodide scintillation crystal (
6Li) abundance is 92%, and the doping of europium is 0.08wt%.
Mix the europium lithium iodide
6LiI (Eu) scintillation crystal has advantages such as light output is big, thermal neutron detection efficiency height, high sensitivity in use, can improve the whole neutron usability of dose equivalent meter on every side greatly; And in the selection of screening can 11, can adopt the screening can of aluminum with in light weight, durable characteristics such as splendid; And in the selection of the photoelectric commutator 14 of neutron probe 10, can adopt shore, Beijing pine CR125 photomultiplier, this photomultiplier can be better and the highly sensitive europium lithium iodide of mixing of large volume
6LiI (Eu) scintillation crystal coupling is used, and effectively carries out the opto-electronic conversion in the work.Because the main working parts of whole neutron probe 10 is mixed the europium lithium iodide by large volume
6LiI (Eu) scintillation crystal (form by Φ 25 * 5mm) coupling CR125 photomultipliers, for this reason, neutron probe 10 can be by to trying to achieve dose equivalent around the neutron fast when the radiation level of test neutron field after the conversion of fluence in the neutron field and dose equivalent.
As shown in Figure 3, neutron energy response regulation body 20 is made of moderation of neutrons body 21 and the slow neutron absorption layer 22 that is embedded in the moderation of neutrons body 21, and the center position at the rear portion of moderation of neutrons body 21 is provided with the pit 23 that is used for neutron probe 10 is placed on its geometric center position.
Wherein, moderation of neutrons body 21 is processed by high density polyethylene; This key character that sensitivity when working in order to reach the present invention and neutron energy are irrelevant, and be convenient to demarcate and in-site measurement, and instrument is easy to carry, and the thickness of moderation of neutrons body 21 can be arranged between the 6-12cm.
The front portion of moderation of neutrons body 21 is that class is round table-like, and the rear portion of moderation of neutrons body 21 is cylindric; And moderation of neutrons body 21 is when making, and the outside surface of moderation of neutrons body 21 equates that to the distance between the inside surface promptly the columned thickness at the round table-like height of class of moderation of neutrons body 21 front portions and radius and rear portion equates.
Slow neutron absorption layer 22 can adopt the material of boracic or cadmium element to make, and its thickness is controlled in the 0.5-8mm, and, make the energy response of the whole device of the present invention be easy to regulate because slow neutron absorption layer 22 adopts the mode that embeds moderation of neutrons body 21 to install.
As shown in Figure 4, control system 30 comprises amplifier 31, discriminator 32, counter 33, controller 34, display 35, hummer 36, LED light 37, low-tension supply 39 and high-voltage power supply 38; Amplifier 31, discriminator 32, counter 33 and controller 34 are connected to each other successively, display 35, hummer 36 and LED light 37 are connected with controller 34 respectively, low-tension supply 39 is connected to each other with amplifier 31, discriminator 32, counter 33, controller 34, display 35 and high-voltage power supply 38 respectively, high-voltage power supply 38 is connected to each other with neutron probe 10, and the signal output part of the signal input part of amplifier 31 and neutron probe 10 is connected to each other.
When thereby neutron probe 10 was started working output signal, the signal of output entered into discriminator 32 again and screens after now amplifying through amplifier 31; And 32 need of discriminator are the requirement of 1500mV according to the examination threshold value of neutron probe 10, select the appropriate signals value from output signal; Continue transported in the counter 33 through the signal of screening and carry out accurate counting, be transfused to then in the controller 34; Controller 34 carries out controls such as data processing, demonstration, storage and warning by operation interface, data show that by display 35 sound, light are reported to the police and indicated by hummer 36, LED light 37; 39 of low-tension supplies are respectively applied for to amplifier 31, discriminator 32, counter 33, controller 34, display 35, high-voltage power supply 38 working power are provided, low-tension supply 39 can adopt the 16V can rechargeable repeatedly lithium ion battery, by its characteristic used repeatedly and stronger durability, improve usability of the present invention greatly; 38 of high-voltage power supplies only are required to be neutron probe 10 and connect power supply, and the operating voltage of 900V is provided, the needs when satisfying the present invention and working.
In use, by corresponding experiment measuring,
241Under the Am-Be source, the neutron fluence rate sensitivity that records is 0.8cps/ (μ Svh
-1), instrument angular response good (0-90 °) less than 15%.Because moderation of neutrons body 21 adopts the thick tygon slow body of 6-12cm, realized that the fluence rate sensitivity of neutron and neutron energy are smooth from the 0.025eV-14MeV response, instruments weight 5kg is easy to carry, and has realized highly sensitive and portable advantage.And whole device is to the neutron response sensitivity, accurate neutron dose equivalent level around the measurement environment, have sound, light warning function, digitizing, intelligent level height, be used for the environmental neutron Radiation monitoring of large-scale nuclear facilities such as reactor, high-energy particle accelerator, guarantee the surrounding environment and the public's neutron irradiation safety.
More than show and described ultimate principle of the present invention and principal character and advantage of the present invention.The technician of the industry should understand; the present invention is not restricted to the described embodiments; that describes in the foregoing description and the instructions just illustrates principle of the present invention; without departing from the spirit and scope of the present invention; the present invention also has various changes and modifications, and these changes and improvements all fall in the claimed scope of the invention.The claimed scope of the present invention is defined by appending claims and equivalent thereof.
Claims (10)
1. dose equivalent meter around the neutron, it is characterized in that, it comprises neutron probe, neutron energy response regulation body and control system, be provided with the neutron detection element in the described neutron probe, described neutron detection element is for mixing europium lithium iodide scintillation crystal, the signal output part of described neutron probe links to each other with the signal input part of described control system, and described neutron probe is placed on the position of the geometric center of described neutron energy response regulation body.
2. dose equivalent meter around the neutron according to claim 1 is characterized in that, described mix lithium in the europium lithium iodide scintillation crystal (
6Li) abundance is 0.01-99%, and the doping of europium is 0.001-1wt%.
3. dose equivalent meter around the neutron according to claim 2 is characterized in that, described mix lithium in the europium lithium iodide scintillation crystal (
6Li) abundance is 92%, and the doping of europium is 0.08wt%.
4. dose equivalent meter around the neutron according to claim 1, it is characterized in that, described neutron probe comprises screening can, neutron detection element, photoconduction, photoelectric commutator and pre-amplification circuit, described neutron detection element, photoconduction, photoelectric commutator and pre-amplification circuit are connected successively mutually and are nested in the described screening can, and the output terminal of described pre-amplification circuit is connected with described control system.
5. dose equivalent meter around the neutron according to claim 4 is characterized in that, described photoelectric commutator is the highly sensitive photomultiplier of one group of coupling.
6. dose equivalent meter around the neutron according to claim 1, it is characterized in that, described neutron energy response regulation body is made of moderation of neutrons body and the slow neutron absorption layer that is embedded in the moderation of neutrons body, and the center position at the rear portion of described moderation of neutrons body is provided with the pit that is used for described neutron probe is placed on its geometric center position.
7. dose equivalent meter around the neutron according to claim 6 is characterized in that the front portion of described moderation of neutrons body is that class is round table-like, and the rear portion of described moderation of neutrons body is cylindric, and the outside surface of described moderation of neutrons body equates to the distance between the inside surface.
8. dose equivalent meter around the neutron according to claim 6 is characterized in that described moderation of neutrons body is processed by high density polyethylene, and the thickness of described moderation of neutrons body is 6-12cm; Described slow neutron absorption layer adopts the material of boracic or cadmium element to make, and the thickness of described slow neutron absorption layer is 0.5-8mm.
9. dose equivalent meter around the neutron according to claim 1 is characterized in that described control system comprises amplifier, discriminator, counter, controller, display, hummer, LED light, low-tension supply and high-voltage power supply; Described amplifier, discriminator, counter and controller are connected to each other successively, described display, hummer, LED light are connected with described controller respectively, described low-tension supply is connected to each other with amplifier, discriminator, counter, controller, display and high-voltage power supply respectively, described high-voltage power supply and described neutron probe are connected to each other, and the signal input part of described amplifier and the signal output part of described neutron probe are connected to each other.
10. dose equivalent meter around the neutron according to claim 9 is characterized in that described low-tension supply is that 16V can rechargeable repeatedly lithium ion battery.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201010294498 CN102043161A (en) | 2010-03-16 | 2010-09-20 | Ambient neutron dose equivalent meter |
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201020132525 | 2010-03-16 | ||
| CN201020132525.8 | 2010-03-16 | ||
| CN 201010294498 CN102043161A (en) | 2010-03-16 | 2010-09-20 | Ambient neutron dose equivalent meter |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102043161A true CN102043161A (en) | 2011-05-04 |
Family
ID=43909487
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN 201010294498 Pending CN102043161A (en) | 2010-03-16 | 2010-09-20 | Ambient neutron dose equivalent meter |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102043161A (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102253404A (en) * | 2011-06-28 | 2011-11-23 | 中国原子能科学研究院 | Portable neutron detection device |
| CN104898157A (en) * | 2014-03-04 | 2015-09-09 | 环境保护部核与辐射安全中心 | Device and method for measuring neutron dose equivalent |
| CN104898158A (en) * | 2014-03-04 | 2015-09-09 | 环境保护部核与辐射安全中心 | Method and device for measuring neutron dose equivalent |
| CN107257601A (en) * | 2017-08-01 | 2017-10-17 | 赫文波 | Intelligent radiation protecting systems |
| 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 |
| CN108535769A (en) * | 2017-03-03 | 2018-09-14 | 中国辐射防护研究院 | A kind of probe and its test calibration method tested for optical fiber neutron detection system with calibration |
| CN108535760A (en) * | 2018-04-02 | 2018-09-14 | 中国疾病预防控制中心辐射防护与核安全医学所 | Nuclear emergency dosage card and nuclear emergency Dosimetry |
| CN109100372A (en) * | 2018-07-04 | 2018-12-28 | 安徽库硕矿产品销售有限公司 | Portable composition of ores detection device |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1651548A (en) * | 2004-02-06 | 2005-08-10 | 乌克兰国家科学研究院闪烁物质研究所 | Scintillating material based on doped lithium iodide |
| CN201047875Y (en) * | 2006-06-12 | 2008-04-16 | 李建平 | Modified type A-B neutron ''Rem'' counter |
| CN201421503Y (en) * | 2009-03-26 | 2010-03-10 | 上海新漫传感技术研究发展有限公司 | Handhold neutron-gamma radiation detector |
-
2010
- 2010-09-20 CN CN 201010294498 patent/CN102043161A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1651548A (en) * | 2004-02-06 | 2005-08-10 | 乌克兰国家科学研究院闪烁物质研究所 | Scintillating material based on doped lithium iodide |
| CN201047875Y (en) * | 2006-06-12 | 2008-04-16 | 李建平 | Modified type A-B neutron ''Rem'' counter |
| CN201421503Y (en) * | 2009-03-26 | 2010-03-10 | 上海新漫传感技术研究发展有限公司 | Handhold neutron-gamma radiation detector |
Non-Patent Citations (1)
| Title |
|---|
| 《核电子学与探测技术》 19980531 汲长松 等 6Li和7Li双玻璃闪烁体C补偿法测量中子注量 全文 1-10 第18卷, 第3期 * |
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102253404B (en) * | 2011-06-28 | 2014-06-25 | 中国原子能科学研究院 | Portable neutron detection device |
| CN102253404A (en) * | 2011-06-28 | 2011-11-23 | 中国原子能科学研究院 | Portable neutron detection device |
| CN104898158B (en) * | 2014-03-04 | 2019-02-15 | 环境保护部核与辐射安全中心 | Neutron DE measurement method and measuring device |
| CN104898157A (en) * | 2014-03-04 | 2015-09-09 | 环境保护部核与辐射安全中心 | Device and method for measuring neutron dose equivalent |
| CN104898158A (en) * | 2014-03-04 | 2015-09-09 | 环境保护部核与辐射安全中心 | Method and device for measuring neutron dose equivalent |
| CN104898157B (en) * | 2014-03-04 | 2019-02-22 | 环境保护部核与辐射安全中心 | Neutron DE measuring device and measuring method |
| CN108535769B (en) * | 2017-03-03 | 2022-06-07 | 中国辐射防护研究院 | Probe for testing and calibrating optical fiber neutron detection system and testing and calibrating method thereof |
| CN108535769A (en) * | 2017-03-03 | 2018-09-14 | 中国辐射防护研究院 | A kind of probe and its test calibration method tested for optical fiber neutron detection system with calibration |
| CN107949146A (en) * | 2017-08-01 | 2018-04-20 | 赫文波 | Intelligent radiation protecting systems |
| CN107257601A (en) * | 2017-08-01 | 2017-10-17 | 赫文波 | Intelligent radiation protecting systems |
| 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 |
| CN108535760A (en) * | 2018-04-02 | 2018-09-14 | 中国疾病预防控制中心辐射防护与核安全医学所 | Nuclear emergency dosage card and nuclear emergency Dosimetry |
| CN109100372A (en) * | 2018-07-04 | 2018-12-28 | 安徽库硕矿产品销售有限公司 | Portable composition of ores detection device |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN102043161A (en) | Ambient neutron dose equivalent meter | |
| CN201662623U (en) | Portable neutron-gammarayspectrometer | |
| CN201421503Y (en) | Handhold neutron-gamma radiation detector | |
| CN201589866U (en) | High-sensitivity neutron detector | |
| CN105510956A (en) | Anti-Compton scattering detector | |
| CN102928864B (en) | Method and system for measuring gas tritium based on multi-wire proportional chamber | |
| CN103616713A (en) | Detector and detecting system | |
| CN111366964A (en) | Fixed integrated device for monitoring regional gamma neutron radiation | |
| CN112904403B (en) | Wide-energy-spectrum neutron fluence online monitoring system | |
| CN103163551A (en) | Optical fiber coupled radiation detector used for slow neutron measurement | |
| CN112526584A (en) | Neutron energy spectrum measuring device and measuring method thereof | |
| CN112764086A (en) | Miniaturized compound gamma spectrometer | |
| CN2771855Y (en) | Container internal nuclear material and its radioactive matter detecting device | |
| CN103901051A (en) | Single-path potassium measuring instrument based on beta rays | |
| CN201017035Y (en) | Novel high-sensitivity surroundings neutron detector | |
| CN208026877U (en) | A kind of neutron detector Performance Test System | |
| CN101750623B (en) | Portable energy adjusting device for heat energy-100 MeV neutron | |
| CN205176286U (en) | Anti - compton scatter detector | |
| CN107449789A (en) | Sample concentration detection means and system | |
| CN108461165A (en) | A kind of underwater nuclear reactor state real-time detecting method | |
| CN108281208A (en) | A kind of underwater nuclear reactor state real-time detection system | |
| CN208255099U (en) | A kind of void detector | |
| CN209842076U (en) | Measuring device | |
| Tuo et al. | Alpha contamination monitoring instrument based on LRAD technique for complex surface monitoring | |
| CN211653160U (en) | X-gamma radiation air kerma rate measuring device for environmental monitoring |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C12 | Rejection of a patent application after its publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20110504 |