CN201413644Y - Board energy spectrum neutron doserate monitor - Google Patents
Board energy spectrum neutron doserate monitor Download PDFInfo
- Publication number
- CN201413644Y CN201413644Y CN2009201596115U CN200920159611U CN201413644Y CN 201413644 Y CN201413644 Y CN 201413644Y CN 2009201596115 U CN2009201596115 U CN 2009201596115U CN 200920159611 U CN200920159611 U CN 200920159611U CN 201413644 Y CN201413644 Y CN 201413644Y
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- slow body
- absorber
- dose rate
- power spectrum
- rate monitor
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The utility model discloses a board energy spectrum neutron doserate monitor with wide range of energy response and wide range of spatial response, comprising a spherical [3]He proportional counter, and an inside moderator, an absorber, a heavy metal moderator and an outsider moderator, which package the proportional counter in sequence inside out, and each packaging layer is a spherical structure.
Description
Technical field
The utility model relates to the nuclear safety monitoring technical field, is specifically related to a kind of neutron dose rate monitor.
Background technology
A-B type neutron " rem " counter is by boron trifluoride (BF
3) proportional counter tube, and be wrapped in BF
3Interior slow body outside the proportional counter tube, absorber and outer slow body constitute, and have advantages such as anti-strong electromagnetic, anti-γ field, have been widely used in domestic and international various accelerator and the nuclear reactor, are used for the monitoring of neutron dose rate.Present A-B type neutron " rem " counter ubiquity angular response is little, suitablely can distinguish shortcomings such as narrow range.Especially in isotropic high energy acclerator radiation field, the Conventional detectors energy response has very strong dependence of angle; And when neutron energy during, the slowing down effect of common A-B type neutron " rem " counter greater than 20MeV, deficiency so that the moderation of neutrons of higher-energy to being noted by the BF3 proportional counter tube.
The utility model content
It is wide that technical problem to be solved in the utility model provides a kind of roomage response scope, the wide power spectrum neutron dose rate monitor that the energy response scope is big.
The wide power spectrum neutron dose rate of the utility model monitor comprises spherical 3He proportional counter tube, and the interior slow body, absorber, heavy metal slow body and the outer slow body that successively wrap up proportional counter tube from inside to outside successively, and each integument is spherical structure.
As optimization, interior slow body and outer slow body all adopt hydrogenous material to make, for example materials such as tygon, graphite, paraffin, liquid hydrogen, polymethylmethacrylate or isocyanurate foam.Absorber is for example contained boron polyethylene, boron-loaded rubber, contains the cadmium tygon or is contained the cadmium elastomeric material by the material of boracic or cadmium.The heavy metal slow body is by lead or tungsten material.
Core component 3He proportional counter tube of the present utility model and outer multilayer package structure thereof all adopt spherical structure, have improved the angular response performance of neutron dose rate monitor, can improve detection efficiency.In addition, owing in original A-B rem counter, increase certain thickness heavy metal slow body, can greatly widen the energy response scope of this device.For example, when the heavy metal slow body is lead layer, when the neutron that energy is lower passes through lead layer, with lead nuclear elastic scattering takes place, off-energy not that is to say, this layer lead almost is " transparent " to low energy neutron, and therefore, its existence can not influence the original energy response of low energy neutron; When the neutron of higher-energy passes through lead layer, with lead nuclear effect generation inelastic scattering, and part energy is passed to plumbous nuclear, thereby make the high-energy neutron slowing down to being noted by proportional counter tube.
As optimization, the thickness of each integument is interior slow body 0.5cm～4cm; Absorber 0.1cm～2cm; Heavy metal slow body 0.1cm～2cm; Outer slow body 2cm～15cm.
As optimization, evenly be provided with hole on the absorber.As further optimization, the area of each hole is 0.9～1 square centimeter, all hole area sums be absorber surface long-pending 30%～40%.
The utility model is at the characteristics of high energy acclerator impulse radiation field, on the basis of original A-B neutron " rem " counter, major defect at its existence, adopt spherical 3He proportional counter tube and wrap up its outer multilayer spherical structure, and increased the heavy metal slow body layer of lead or tungsten, design angular response bigger, can distinguish wideer wide power spectrum neutron dose rate monitor.The utility model is applied widely, can be applicable to domestic and international various types of high energy acclerator, filled up the blank of on-line measurement high-energy neutron dose rate, improved scientific research and the technology application level of China, the neutron dose rate monitoring means of wide power spectrum is provided for China nuclear safety monitoring field in this technical field.
Description of drawings
Fig. 1 is the utility model embodiment cross-sectional view;
Fig. 2 is the utility model energy response curve synoptic diagram.
Parts that number in the figure is represented or position are the spherical counter tube of 1-3He direct ratio; The 2-slow body; The 3-absorber; 4-heavy metal slow body; The outer slow body of 5-; The energy response curve of 6-embodiment one; The 7-typical curve.
Embodiment
The utility model is described in further detail below in conjunction with accompanying drawing.
As shown in Figure 1, the utility model adopts ball-type proportional counter tube and structure, to realize 4 π orientation measurements.Be enclosed with interior slow body 2, absorber 3, heavy metal slow body 4 and the outer slow body 5 that is spherical structure successively beyond the spherical counter tube 1 of 3He direct ratio.
Figure 2 shows that the contrast of energy response curve 6 and the typical curve 7 that International Commission on Radiological Protection provides of the utility model embodiment one.What horizontal ordinate was represented among the figure is the energy (GeV) of incident neutron, and what ordinate was represented is the fluence of unit incident neutron correspondence.
The thickness of spherical each level of counter tube of the utility model parcel 3He direct ratio and the preferred forms of material therefor are: the thick interior slow body made from polythene material of 1.9cm; 0.6cm thick absorber with the boron-loaded rubber material; 0.6cm thick heavy metal slow body and the thick outer slow body made from lead material made from polythene material of 6.5cm.Empirical tests, the neutron dose rate monitor of making by the present embodiment method has reached best energy response scope and best roomage response scope, and the energy response scope is 0.025eV-1.6GeV.
The thickness of spherical each level of counter tube of the utility model parcel 3He direct ratio and another embodiment of material therefor are: the thickness and the material of spherical each level of counter tube of parcel 3He direct ratio are the thick interior slow body made from polythene material of 1.9cm; 0.6cm thick absorber with the boron-loaded rubber material; 0.6cm thick heavy metal slow body and the thick outer slow body made from polythene material of 6.5cm with the tungsten material.
Claims (9)
1. one kind wide power spectrum neutron dose rate monitor is characterized in that, comprises sphere
3He proportional counter tube, and the interior slow body, absorber, heavy metal slow body and the outer slow body that successively wrap up proportional counter tube from inside to outside successively, each integument is spherical structure.
2. wide power spectrum neutron dose rate monitor according to claim 1 is characterized in that, described interior slow body and outer slow body all adopt hydrogenous material to make; Described absorber is by the material of boracic or cadmium; Described heavy metal slow body is by lead or tungsten material.
3. wide power spectrum neutron dose rate monitor according to claim 1 is characterized in that the thickness of each integument is interior slow body 0.5cm～4cm; Absorber 0.1cm～2cm; Heavy metal slow body 0.1cm～2cm, outer slow body 2cm～15cm.
4. wide power spectrum neutron dose rate monitor according to claim 1 is characterized in that, parcel
3The thickness and the material of spherical each level of counter tube of He direct ratio are the thick interior slow body made from polythene material of 1.9cm; 0.6cm thick absorber with the boron-loaded rubber material; 0.6cm thick heavy metal slow body and the thick outer slow body made from lead material made from polythene material of 6.5cm.
5. wide power spectrum neutron dose rate monitor according to claim 1 is characterized in that, parcel
3The thickness and the material of spherical each level of counter tube of He direct ratio are the thick interior slow body made from polythene material of 1.9cm; 0.6cm thick absorber with the boron-loaded rubber material; 0.6cm thick heavy metal slow body and the thick outer slow body made from polythene material of 6.5cm with the tungsten material.
6. according to the described wide power spectrum neutron dose rate monitor of 1～5 arbitrary claim, it is characterized in that, evenly be provided with hole on the described absorber.
7. wide power spectrum neutron dose rate monitor according to claim 6 is characterized in that, set hole size is that the area of each hole is 0.9～1.0 square centimeter on the absorber.
8. wide power spectrum neutron dose rate monitor according to claim 6 is characterized in that, on the described absorber all hole area sums be absorber surface long-pending 30%～40%.
9. wide power spectrum neutron dose rate monitor according to claim 7 is characterized in that, on the described absorber all hole area sums be absorber surface long-pending 30%～40%.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009201596115U CN201413644Y (en) | 2009-06-11 | 2009-06-11 | Board energy spectrum neutron doserate monitor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009201596115U CN201413644Y (en) | 2009-06-11 | 2009-06-11 | Board energy spectrum neutron doserate monitor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN201413644Y true CN201413644Y (en) | 2010-02-24 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN2009201596115U Expired - Fee Related CN201413644Y (en) | 2009-06-11 | 2009-06-11 | Board energy spectrum neutron doserate monitor |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102736100A (en) * | 2012-07-13 | 2012-10-17 | 中国科学院合肥物质科学研究院 | Spherical multilayer polyethylene moderation body and neutron energy spectrum and fluence measurement device of single probe |
| CN102866416A (en) * | 2012-09-10 | 2013-01-09 | 中国科学院合肥物质科学研究院 | Continuous neutron spectrum real-time detection system |
| CN102967875A (en) * | 2011-08-29 | 2013-03-13 | 通用电气公司 | Boron-10 compounds for neutron capture layer |
| CN103472477A (en) * | 2012-06-08 | 2013-12-25 | 中国原子能科学研究院 | Middle and high energy neutron detector |
| CN104898156A (en) * | 2015-05-29 | 2015-09-09 | 中国科学院合肥物质科学研究院 | Directional wide-energy-range neutron monitor probe |
| CN105785425A (en) * | 2016-04-26 | 2016-07-20 | 成都理工大学 | Water injection and drainage full-automatic multisphere neutron spectrometer and measurement method |
| CN106980137A (en) * | 2017-05-12 | 2017-07-25 | 中国工程物理研究院核物理与化学研究所 | A kind of fast neutron detector |
| CN108562929A (en) * | 2018-04-18 | 2018-09-21 | 中国科学院合肥物质科学研究院 | The wide moderate energy neutron source strength measuring system of one heavy metal species multiplication |
| CN109387865A (en) * | 2017-08-11 | 2019-02-26 | 中国辐射防护研究院 | A kind of portable more ball neutron spectrometer systems and its method for monitoring neutron irradiation |
| CN112526583A (en) * | 2020-10-26 | 2021-03-19 | 南京即衡科技发展有限公司 | Neutron source position measuring device and method based on cadmium zinc telluride detector array |
| CN112526584A (en) * | 2020-10-26 | 2021-03-19 | 南京即衡科技发展有限公司 | Neutron energy spectrum measuring device and measuring method thereof |
| CN113504559A (en) * | 2021-07-05 | 2021-10-15 | 中国科学院近代物理研究所 | High current pulse wide energy spectrum neutron dose rate monitoring device |
-
2009
- 2009-06-11 CN CN2009201596115U patent/CN201413644Y/en not_active Expired - Fee Related
Cited By (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102967875A (en) * | 2011-08-29 | 2013-03-13 | 通用电气公司 | Boron-10 compounds for neutron capture layer |
| CN102967875B (en) * | 2011-08-29 | 2017-08-15 | 通用电气公司 | The compound of boron 10 for neutron capture layer |
| CN103472477A (en) * | 2012-06-08 | 2013-12-25 | 中国原子能科学研究院 | Middle and high energy neutron detector |
| CN102736100B (en) * | 2012-07-13 | 2015-03-18 | 中国科学院合肥物质科学研究院 | Spherical multilayer polyethylene moderation body and neutron energy spectrum and fluence measurement device of single probe |
| CN102736100A (en) * | 2012-07-13 | 2012-10-17 | 中国科学院合肥物质科学研究院 | Spherical multilayer polyethylene moderation body and neutron energy spectrum and fluence measurement device of single probe |
| CN102866416A (en) * | 2012-09-10 | 2013-01-09 | 中国科学院合肥物质科学研究院 | Continuous neutron spectrum real-time detection system |
| CN102866416B (en) * | 2012-09-10 | 2015-06-17 | 中国科学院合肥物质科学研究院 | Continuous neutron spectrum real-time detection system |
| CN104898156A (en) * | 2015-05-29 | 2015-09-09 | 中国科学院合肥物质科学研究院 | Directional wide-energy-range neutron monitor probe |
| CN104898156B (en) * | 2015-05-29 | 2018-02-09 | 中国科学院合肥物质科学研究院 | One kind orients wide moderate energy neutron monitor probe |
| CN105785425B (en) * | 2016-04-26 | 2018-08-03 | 成都理工大学 | A kind of full-automatic more ball neutron spectrometers of water filling draining and measurement method |
| CN105785425A (en) * | 2016-04-26 | 2016-07-20 | 成都理工大学 | Water injection and drainage full-automatic multisphere neutron spectrometer and measurement method |
| CN106980137A (en) * | 2017-05-12 | 2017-07-25 | 中国工程物理研究院核物理与化学研究所 | A kind of fast neutron detector |
| CN109387865A (en) * | 2017-08-11 | 2019-02-26 | 中国辐射防护研究院 | A kind of portable more ball neutron spectrometer systems and its method for monitoring neutron irradiation |
| CN108562929A (en) * | 2018-04-18 | 2018-09-21 | 中国科学院合肥物质科学研究院 | The wide moderate energy neutron source strength measuring system of one heavy metal species multiplication |
| CN112526583A (en) * | 2020-10-26 | 2021-03-19 | 南京即衡科技发展有限公司 | Neutron source position measuring device and method based on cadmium zinc telluride detector array |
| CN112526584A (en) * | 2020-10-26 | 2021-03-19 | 南京即衡科技发展有限公司 | Neutron energy spectrum measuring device and measuring method thereof |
| CN113504559A (en) * | 2021-07-05 | 2021-10-15 | 中国科学院近代物理研究所 | High current pulse wide energy spectrum neutron dose rate monitoring device |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20100224 Termination date: 20160611 |
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| CF01 | Termination of patent right due to non-payment of annual fee |