CN109557575A - A kind of neutron multiplicity measuring device and its application method - Google Patents
A kind of neutron multiplicity measuring device and its application method Download PDFInfo
- Publication number
- CN109557575A CN109557575A CN201811541399.9A CN201811541399A CN109557575A CN 109557575 A CN109557575 A CN 109557575A CN 201811541399 A CN201811541399 A CN 201811541399A CN 109557575 A CN109557575 A CN 109557575A
- Authority
- CN
- China
- Prior art keywords
- detector
- sample room
- neutron
- measuring device
- shield
- 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
- 238000000034 method Methods 0.000 title claims abstract description 22
- 239000007788 liquid Substances 0.000 claims abstract description 31
- 238000005259 measurement Methods 0.000 claims description 18
- 239000000463 material Substances 0.000 claims description 14
- 238000004458 analytical method Methods 0.000 claims description 11
- 229920000573 polyethylene Polymers 0.000 claims description 4
- 239000004698 Polyethylene Substances 0.000 claims description 3
- 239000000203 mixture Substances 0.000 claims description 3
- -1 polyethylene Polymers 0.000 claims description 3
- 229910001220 stainless steel Inorganic materials 0.000 claims description 3
- 239000010935 stainless steel Substances 0.000 claims description 3
- 239000007787 solid Substances 0.000 claims 1
- 238000004445 quantitative analysis Methods 0.000 abstract description 6
- 238000001514 detection method Methods 0.000 description 15
- 229910052778 Plutonium Inorganic materials 0.000 description 14
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 14
- 238000010586 diagram Methods 0.000 description 12
- 230000004992 fission Effects 0.000 description 9
- 238000012545 processing Methods 0.000 description 8
- 239000011824 nuclear material Substances 0.000 description 6
- 238000005516 engineering process Methods 0.000 description 5
- 230000000155 isotopic effect Effects 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 239000011162 core material Substances 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 238000009826 distribution Methods 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012216 screening Methods 0.000 description 3
- DNYWZCXLKNTFFI-UHFFFAOYSA-N uranium Chemical compound [U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U] DNYWZCXLKNTFFI-UHFFFAOYSA-N 0.000 description 3
- 238000000342 Monte Carlo simulation Methods 0.000 description 2
- 230000001066 destructive effect Effects 0.000 description 2
- 230000005284 excitation Effects 0.000 description 2
- 230000005251 gamma ray Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 238000001228 spectrum Methods 0.000 description 2
- 230000002123 temporal effect Effects 0.000 description 2
- MWZXTPHEXZSJOF-UHFFFAOYSA-N [Au].[Pu] Chemical compound [Au].[Pu] MWZXTPHEXZSJOF-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000002452 interceptive effect Effects 0.000 description 1
- 238000012067 mathematical method Methods 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- FLDALJIYKQCYHH-UHFFFAOYSA-N plutonium(IV) oxide Inorganic materials [O-2].[O-2].[Pu+4] FLDALJIYKQCYHH-UHFFFAOYSA-N 0.000 description 1
- 230000008092 positive effect Effects 0.000 description 1
- 230000035755 proliferation Effects 0.000 description 1
- 238000011002 quantification Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 238000005070 sampling Methods 0.000 description 1
- 239000002900 solid radioactive waste Substances 0.000 description 1
- 239000002910 solid waste Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
- G01T3/06—Measuring neutron radiation with scintillation detectors
Abstract
The disclosure belongs to radio chemistry field, in particular to a kind of neutron multiplicity measuring device and its application method.The device includes: exploring block, sample room, signal processor;Wherein exploring block includes: detector and shield, and shield is provided with the groove for storing detector, and detector includes platform liquid scintillation bulk detector, and liquid scintillator detector quantity is more than or equal to two;Shield includes: main shield body and shielding slip lid, and main shield body is used to wrap up detector, and shielding slip lid is used to shield sample entrance;Detector is connect with signal processor;To provide a kind of neutron multiplicity measuring device and its application method that can be realized online data quantitative analysis using liquid scintillation bulk detector.
Description
Technical field
The disclosure belongs to radio chemistry field, in particular to a kind of neutron multiplicity measuring device and its application method.
Background technique
With the development of nuclear industry, worldwide uranium, plutonium material are more and more, and preventing nuclear proliferation, it is current to have become
International community's question of common concern.Since uranium, plutonium material can generate fission neutron, utilize neutron detection technology
And isotope abundance is combined to carry out non-destructive analysis to them, it is the most common means in nuclear safeguards field.In China, core is set
Apply classification, the place of middle uranium, the detection of plutonium material and longtime running and the retired a large amount of radioactive solid wastes generated in the process
Reason, is increasingly becoming a difficult task.
Neutron multiplicity measuring technique is as a kind of non-destructive analysis skill developed by neutron coincidence measurement technology
Art especially has great importance in terms of nuclear material accountancy in nuclear safeguards field, while low in putting solid radioactive waste
Classification and Detection in also have broad application prospects.In the accurate quantification analysis of the above related fields U/Pu material, including
In terms of conventional sample analysis, storehouse are taken inventory, U/Pu production line is closed, which all plays positive effect.
In recent years, due to3He gas it is rare, researching and developing substitution in the world3The technology of He neutron counter tube, according to phase
Document is closed, Los Alamos National Laboratories, the U.S. have been developed that a kind of liquid scintillator detector module.Liquid dodges
The detection to fast neutron may be implemented in bright bulk detector, makes to meet the gate-width time and reaches ns magnitude, therefore can be effectively reduced
The influence of random signals event, and in high background environment, more preferably measurement accuracy can be obtained with the shorter time.Separately
Outside, relative to3He proportional counter tube, liquid scintillation bulk detector have better energy resolution characteristic, for impure plutonium gold
Belong to, PuO2And HEU, effectively (α, n) neutron and fission neutron can be distinguished.But currently based on liquid scintillation
After the neutron measurement device of bulk detector can only measure at the scene, then the another quantitative analysis for carrying out data, it cannot achieve data
On-line quantitative analysis.
Summary of the invention
(1) purpose invented
In order to overcome the deficiencies of the prior art, the disclosure, which specifically provides, a kind of can be realized using liquid scintillation bulk detector
The neutron multiplicity measuring device of online data quantitative analysis.
(2) technical solution
A kind of neutron multiplicity measuring device, which is characterized in that the device includes: exploring block, sample room, signal processing
Device;
Wherein exploring block includes: detector and shield, and shield is provided with the groove for storing detector, detection
Device includes liquid scintillation bulk detector, and liquid scintillator detector quantity is more than or equal to two;Shield includes: main shield body
With shielding slip lid, main shield body is used to wrap up detector, and shielding slip lid is used to shield sample entrance;Detector and signal processing
Device connection;
Wherein sample room is columnar structured, comprising: upper sample room, lower sample room, sliding rail and interior storehouse;Upper sample room is under
Sample room composition is columnar structured, and sliding rail is in the gap between upper sample room and lower sample room;Interior storehouse is installed on the slide rail,
And it is fixedly connected with shielding slip lid;Sample room is in the center of liquid scintillation bulk detector package;
Signal processor includes: analyzer, goes that stochastic circuit module, shift register, to be equipped with real time data processing soft
The computer of part;Signal picker is connect with detector, and signal picker, goes stochastic circuit module, shift register, installation
There is the computer of real time data processing software to be sequentially connected;
The device further includes appliance stand;
Wherein appliance stand includes: device front casing, device rear casing, platform trailer;It is outer after device front casing and device
Shell connects into hollow rectangular parallelepiped structure, and device front casing and device rear casing are placed on platform trailer, and exploring block is placed
In the hollow cuboid that device front casing and device rear casing are formed.
Shielding body thickness between detector and appliance stand is greater than the length of liquid scintillation bulk detector, and shield material
Matter is polyethylene.
Liquid scintillation bulk detector is seven, and seven hexagonal arrangements of liquid scintillation bulk detector.
Sample room material is stainless steel, and inside is provided with lead screen layer.
Platform trailer is provided with movable universal wheel.
The bracket for being used to support detector is additionally provided in appliance stand.
Analyzer uses mixing field analyzer.
The application method of above-mentioned neutron multiplicity measuring device, this method comprises:
1) detector is connect with signal processor;
2) sample room is opened, sample to be tested is horizontally placed on interior storehouse, closes sample room;
3) enabling signal processor;
4) measurement data, and shutdown signal processor are recorded;
5) sample room is opened, sample is taken out, closes sample room.
(3) beneficial effect
The device that the disclosure provides is analyzed using neutron multiplicity measuring technique, carries out accurate quantitative analysis to nuclear material to realize
It analyzes, without carrying out standard specimen scale in measurement process, measurement result bring may be influenced so as to avoid standard specimen use.This
Bottom neutron and (α, n) neutron are single neutron, do not have temporal correlation, such as Am-Li source neutron.And fission neutron is in the time
Upper to have correlation, the neutron number of fission event release has certain Probability Distribution, i.e. multiplicity is distributed.So as to
The interference for reducing non-fissile neutron to greatest extent to distinguish fission neutron and non-fissile neutron and basis material are to the shadow of measurement
It rings.
Disclosure device includes the shield of polythene material, increases neutron rebound rate to realize the function of detection efficient raising
Energy, while being also able to achieve prevents neutron signal evolution, protection operator, the extraneous neutron signal of shielding from interfering, fixing and supporting
Liquid dodges the function that neutron detector and sample are fast placed.
The device of the disclosure is provided with the sample room comprising lead layer in shield, and wherein lead layer thickness design is 10mm,
A quarter before the gamma-rays of 661keV being decayed to, alleviates the processing pressure of back end signal processor.
The signal processor of disclosure device mainly uses the mixing field analyzer of Hybrid Instruments company, real
Show and n/ γ examination is carried out to multiple signals, export neutron signal after screening and be stored in shift register, then to detection
While device provides partial high pressure, n/ γ signal screening, neutron signal output and sampling and analysis of signal are carried out, eventually by this
The cooperation of device design realizes neutron multiplicity on-line analysis.
Detailed description of the invention
Fig. 1 is neutron multiplicity measuring device structural schematic diagram in one embodiment of the disclosure;
Fig. 2 is exploring block structural schematic diagram in the measuring device of neutron multiplicity shown in Fig. 1;
Fig. 3 is structure sectional view in exploring block shown in Fig. 2;
Fig. 4 is detector array structural schematic diagram in exploring block shown in Fig. 2;
Fig. 5 is main shield body overall structure diagram in exploring block shown in Fig. 2;
Fig. 6 is main shield body structure sectional view in exploring block shown in Fig. 2;
Fig. 7 is shielding sliding lid construction schematic diagram in exploring block shown in Fig. 2;
Fig. 8 is the sample room structural schematic diagram that shield slip lid is free of in the measuring device of neutron multiplicity shown in Fig. 1;
Fig. 9 is upper sample cell structure schematic diagram in sample room shown in Fig. 8;
Figure 10 is lower sample room structural schematic diagram in sample room shown in Fig. 8;
Figure 11 is that band shields chamber structure schematic diagram in slip lid in sample room shown in Fig. 8;
Figure 12 is device front casing structural schematic diagram in the measuring device of neutron multiplicity shown in Fig. 1;
Figure 13 is device rear casing structural schematic diagram in the measuring device of neutron multiplicity shown in Fig. 1;
Figure 14 is platform trailer structural schematic diagram in the measuring device of neutron multiplicity shown in Fig. 1;
Wherein 1 exploring block, 2 analyzer 3 removes 6 detector of stochastic circuit module 4 shift register, 5 computer, 7 appliance stand
16 device front casing of sample room on the lower sample room 15 of 10 main shield body 11 of storehouse shielding, 12 sample room of slip lid, 13 sliding rail 14 in 8 brackets 9
17 device rear casing, 18 platform trailer
Specific embodiment
In order to more clearly illustrate the technical solution of the disclosure, describe in detail in conjunction with the embodiments:
As shown in Figure 1, 2, a kind of neutron multiplicity measuring device, the device include: exploring block 1, sample room 12, signal
Processor;Wherein exploring block 1 includes: the shield of detector 6 and polyethylene material, and shield is provided with for storing detection
The groove of device 6, detector 6 include seven liquid scintillation bulk detectors;Wherein signal processor includes: Hybrid
The mixing field analyzer 2 of Instruments company goes stochastic circuit module 3, shift register 4, is equipped with real time data processing
The computer 5 of software;Signal picker is connect with detector 6, and signal picker, goes stochastic circuit module 3, shift register
4, the computer 5 for being equipped with real time data processing software is sequentially connected.
As shown in Figure 3,4, seven hexagonal arrangements of liquid scintillation bulk detector;Shield includes: 10 He of main shield body
Slip lid 11 is shielded, main shield body 10 is used to wrap up detector 6, and shielding slip lid 11 is used to shield sample entrance.
As shown in Fig. 7,8,9,10,11, wherein sample room 12 is columnar structured, comprising: upper sample room 15, lower sample room
14, sliding rail 13 and interior storehouse 9;Upper sample room 15 formed with lower sample room 14 it is columnar structured, sliding rail 13 be in upper sample room 15 with
In gap between lower sample room 14;Interior storehouse 9 is mounted on sliding rail 13, and is fixedly connected with shielding slip lid 11;12 material of sample room
Matter is stainless steel, and inside is provided with lead screen layer.
As shown in Figure 12,13,14, which further includes appliance stand 7;Wherein appliance stand 7 includes: device front casing
16, device rear casing 17, platform trailer 18;Device front casing 16 and device rear casing 17 connect into hollow rectangular parallelepiped structure, and
Device front casing 16 and device rear casing 17 are placed on platform trailer 18, and exploring block 1 is placed on device front casing 16 and dress
In the hollow cuboid for postponing the formation of shell 17, platform trailer 18 is provided with movable universal wheel;It is additionally provided in appliance stand 7
It is used to support the bracket 8 of detector 6, liquid scintillation bulk detector length is 127mm, therefore between detector 6 and appliance stand 7
Shield with a thickness of 130mm.
Neutron multiplicity measuring device is established according to upper structure, pass through Monte Carlo simulation calculation optimization and determines neutron moisture
Measure apparatus structure, wherein based on HPGe detector, neutron detection dodges neutron detector as base using liquid for isotopic abundance measurement
Plinth.For finally determining apparatus structure, electricity is screened using the pulse that can carry out pulse-shape discrimination to multiple signals simultaneously
Son learns equipment, and the neutron signal after screening is directly inputted to the production domesticization rapid neutron for being able to carry out high-speed data acquisition
In Pulse Signal Processing System, on line real time processing is carried out to data in conjunction with matched data processing software, it is final to obtain
To the amount of surveyed nuclear material.
Liquid dodges neutron multiplicity measuring technique, mainly using liquid scintillator as neutron detector, by collecting to side
The neutron signal that sample is issued using multiplicity analysis method, and combines the Pu sample analyzed by plutonium isotope each
Isotopics information is calculated the content of nuclear material to be measured.
1) liquid dodges detector working principle
The course of work of liquid scintillation bulk detector, i.e. projectile energy are changed into the process of output electric pulse, can be with
It is divided into following several stages:
Incoming particle enters in liquid scintillation body, loses its part or all of energy, swashs atom or molecule in scintillator
Hair and ionization.
It is again compound and be in the atom of excitation state and molecule emits fluorescence light during de excitation after be excited or ionization
Son.
Fluorescent photon is reflected through reflecting layer by light guide is transferred to photomultiplier tube photocathode, due to photoelectric effect,
Photocathode issues photoelectron after absorbing photon.
Photoelectron doubles between each dynode of photomultiplier tube, finally reaches anode and forms voltage or current impulse.
2) n- γ pulse-shape discrimination principle
The pulse signal feature that neutron signal is different from γ signal in neutron detector is dodged according to liquid, when rising based on pulse
Between principle, using zero-crossing timing method design n- γ pulse-shape discrimination electronic system, thus efficiently separate fast burst letter
Number with gamma-ray burst signal.So-called zero-crossing timing method, exactly if the voltage pulse that photomultiplier tube exports is done primary product
Point and differential, then after second differential obtained bipolar signal pulse and baseline crosspoint, i.e. the position of zero crossing, with voltage
The amplitude of pulse is unrelated, only related with the rise time of voltage pulse, i.e., only related with pulse shape.Different types of band electrochondria
Sub- zero-crossing timing is also different, can use the signal zero-crossing timing that different charged particles are formed thus to identify them.
3) neutron multiplicity analysis principle
Neutron multiplicity measuring technique is a kind of multiplicity distribution by measuring nuclear material fission neutron, to realize to core
Material carries out the quick NDA technology of accurate quantitative analysis, is not necessarily to carry out standard specimen scale in measurement process, make so as to avoid standard specimen
With may be influenced on measurement result bring.Background neutron and (α, n) neutron are single neutron, do not have temporal correlation,
Such as Am-Li source neutron.And fission neutron has correlation in time, the neutron number of fission event release has certain
Probability Distribution, i.e., multiplicity be distributed.This method can distinguish fission neutron and non-fissile neutron, reduce non-fissile to greatest extent
Influence of the interference and basis material of neutron to measurement.Measurement object includes metal Pu, containing plutonium oxide, residue, waste etc., fortune
Carry out data processing with mathematical method appropriate, can provide the self-reproduction coefficient M of measurement object, (α, n) reactivity,240PueffMatter
Measure the key parameters such as m.
By taking Pu material as an example, ideally, according to neutron multiplicity metrical information, can definitely it measure in sample
Effectively240PueffQuality,240PueffThe even core isotope generation for being defined as all Pu in sample is equivalent to240What Pu was generated meets
Neutron count rate D, it may be assumed that
240Pueff=2.52 (238Pu)+240Pu+1.68(242Pu)
Wherein,238Pu、240Pu and242Pu respectively indicates corresponding Pu isotopic mass.That is, 1g238The counting rate that Pu is generated
It is equivalent to 2.52g240The counting rate that Pu is generated, 1g242The counting rate that Pu is generated is equivalent to 1.68g240Pu
The counting rate of generation.
If the isotope composition of plutonium in sample it is known that if so obtain plutonium gross mass:
F in above formula238、f240、f242It is the abundance of various plutonium isotopes present in sample.
4) Plutonium isotopes abundances analysis principle
The acquisition of isotopics information each for Pu sample, using gamma energy spectrum method.As in the plutonium sample of nuclear material, often
The plutonium isotope seen has:238Pu、239Pu、240Pu、241Pu and242Pu.Wherein,239Content (abundance) value of Pu is to determine plutonium sample
The key of quality (attribute).In plutonium sample241Pu is service life shorter isotope,
In old plutonium sample usually also241Am、237U and237Np exists.
The principle of plutonium isotope analysis is the feature for passing through detector measurement first and each isotope in power spectrum being calculated
Gamma-rays peak area;Then it is corrected through detection efficient and branching ratio of the detector to the energy gamma-rays, it is same to obtain this in sample
The atomic nucleus number of position element;Finally the atomic nucleus number of each isotope and it will be normalized to 100%, so that each isotope be calculated
Atomic nucleus number shared percentage, i.e. isotope abundance in the sample.The key of problem is how scale detector is to institute
The detection efficient of various energy gamma-rays in the sample of measurement.It is well known that detection efficient is not only the function of energy of γ ray,
It and is the function of distance between sample shape (including sample size, sample media) and sample and detector.In such case
Under, the measurement object encountered may be multifarious, is not available corresponding standard source and carries out scale, therefore can be used to be measured
Sample itself carry out relative efficiency from scale.
Using above-mentioned neutron multiplicity measuring device, specific steps are as follows:
1) detector 6 is connect with signal processor;
2) sample room 12 is opened, sample to be tested is horizontally placed on interior storehouse 9, closes sample room 12;
3) enabling signal processor;
4) measurement data, and shutdown signal processor are recorded;
5) sample room 12 is opened, sample is taken out, closes sample room 12.
Using aforesaid operations step, the device detection efficient when threshold value is 0.5Cs is calculated by Monte Carlo simulation
It is 10.1%, device detection efficient is 16.03% when threshold value is 0.25Cs;Device detection efficient is greater than 15%, measures opposite mark
Quasi- deviation is less than 5%.
Obviously, those skilled in the art can carry out various modification and variations without departing from the essence of the disclosure to the disclosure
Mind and range.If in this way, these modifications and variations of the disclosure are belonged to the model of disclosure claim and its equivalent technology
Within enclosing, then the disclosure is also intended to include these modifications and variations.Above-described embodiment or embodiment are only to the disclosure
For example, the disclosure can also be implemented with other ad hoc fashions or other particular form, without departing from the disclosure
Main idea or substantive characteristics.Therefore, the embodiment of description is regarded as illustrative and non-limiting in any way.This
Scope of disclosure should be illustrated that any variation equivalent with the intention and range of claim also should include by appended claims
Within the scope of this disclosure.
Claims (10)
1. a kind of neutron multiplicity measuring device, which is characterized in that the device includes: exploring block (1), sample room (12), letter
Number processor;
Wherein the exploring block (1) includes: detector (6) and shield, and the shield is provided with for storing detector
(6) groove, the detector (6) includes liquid scintillation bulk detector, and liquid scintillator detector quantity is more than or equal to two
It is a;The shield includes: main shield body (10) and shielding slip lid (11), and the main shield body (10) is used to wrap up detector
(6), the shielding slip lid (11) is used to shield sample entrance;The detector (6) connect with signal processor;
Wherein the sample room (12) is columnar structured, comprising: upper sample room (15), lower sample room (14), sliding rail (13) and
Interior storehouse (9);The upper sample room (15) and lower sample room (14) composition are columnar structured, and the sliding rail (13) is in upper sample room
(15) in the gap between lower sample room (14);The interior storehouse (9) is mounted on sliding rail (13), and solid with shielding slip lid (11)
Fixed connection;The sample room (15) is in the center of liquid scintillation bulk detector package.
2. a kind of neutron multiplicity measuring device according to claim 1, which is characterized in that the signal processor includes:
Analyzer (2) removes stochastic circuit module (3), shift register (4), the computer (5) for being equipped with real time data processing software;
The signal picker is connect with detector (6), and signal picker, go stochastic circuit module (3), shift register (4), peace
Computer (5) equipped with real time data processing software is sequentially connected.
3. a kind of neutron multiplicity measuring device according to claim 1, which is characterized in that the described device further includes device
Bracket (7);
Wherein described device bracket (7) includes: device front casing (16), device rear casing (17), platform trailer (18);The dress
It sets front casing (16) and device rear casing (17) and connects into hollow rectangular parallelepiped structure, and device front casing (16) and device rear casing
(17) it is placed on platform trailer (18), the exploring block (1) is placed on device front casing (16) and device rear casing (17)
In the hollow cuboid formed.
4. a kind of neutron multiplicity measuring device according to claim 1, which is characterized in that the detector (6) and device
Shielding body thickness between bracket (7) is greater than the length of liquid scintillation bulk detector, and shield material is polyethylene.
5. a kind of neutron multiplicity measuring device according to claim 1, which is characterized in that the liquid scintillation bulk detector
It is seven, and seven hexagonal arrangements of liquid scintillation bulk detector.
6. a kind of neutron multiplicity measuring device according to claim 1, which is characterized in that sample room (12) material is
Stainless steel, and inside is provided with lead screen layer.
7. a kind of neutron multiplicity measuring device according to claim 3, which is characterized in that platform trailer (18) setting
There is movable universal wheel.
8. a kind of neutron multiplicity measuring device according to claim 3, which is characterized in that in described device bracket (7) also
It is provided with the bracket (8) for being used to support detector (6).
9. a kind of neutron multiplicity measuring device according to claim 2, which is characterized in that the analyzer (2) is using mixed
Close field analysis instrument.
10. the application method of claim 1 described device, this method comprises:
1) detector (6) is connect with signal processor;
2) sample room (12) are opened, sample to be tested is horizontally placed on interior storehouse (9), closed sample room (12);
3) enabling signal processor;
4) measurement data, and shutdown signal processor are recorded;
5) sample room (12) are opened, takes out sample, closed sample room (12).
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201811541399.9A CN109557575A (en) | 2018-12-17 | 2018-12-17 | A kind of neutron multiplicity measuring device and its application method |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201811541399.9A CN109557575A (en) | 2018-12-17 | 2018-12-17 | A kind of neutron multiplicity measuring device and its application method |
Publications (1)
Publication Number | Publication Date |
---|---|
CN109557575A true CN109557575A (en) | 2019-04-02 |
Family
ID=65870122
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201811541399.9A Pending CN109557575A (en) | 2018-12-17 | 2018-12-17 | A kind of neutron multiplicity measuring device and its application method |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN109557575A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110727020A (en) * | 2019-10-11 | 2020-01-24 | 中广核研究院有限公司 | Measuring and scaling method, device and system for medium and low-level waste and storage medium |
CN113109862A (en) * | 2021-03-30 | 2021-07-13 | 陕西卫峰核电子有限公司 | Irradiation-resistant neutron detection device and installation method thereof |
CN116184482A (en) * | 2023-03-02 | 2023-05-30 | 中国人民解放军火箭军工程大学 | Helium-3-based neutron multiple self-adaptive measurement device and measurement method |
Citations (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB806306A (en) * | 1954-04-30 | 1958-12-23 | Gen Electric | Improvements in and relating to neutron detectors |
GB1197099A (en) * | 1967-08-25 | 1970-07-01 | Kernforschung Gmbh Ges Fuer | Method and device for the Non-Destructive Control of Nuclear Fuels |
US4483816A (en) * | 1982-03-31 | 1984-11-20 | The United States Of America As Represented By The Department Of Energy | Apparatus and method for quantitative assay of generic transuranic wastes from nuclear reactors |
US5083026A (en) * | 1990-02-12 | 1992-01-21 | Danev Elbaum | Method, apparatus and applications of the quantitation of multiple gamma-photon producing isotopes with increased sensitivity |
EP2275839A2 (en) * | 2002-11-06 | 2011-01-19 | American Science & Engineering, Inc. | X-ray backscatter mobile inspection van |
US20120061580A1 (en) * | 2010-09-13 | 2012-03-15 | Kline Craig R | Neutron detector having enhanced absorption and bifurcated detection elements |
US20120074326A1 (en) * | 2009-07-27 | 2012-03-29 | Guntram Pausch | Apparatus and method for neutron detection with neutron-absorbing calorimetric gamma detectors |
CN104678425A (en) * | 2015-02-02 | 2015-06-03 | 中国原子能科学研究院 | Fast-neutron multiple measuring-analyzing method based on liquid scintillation detector |
CN104820230A (en) * | 2015-04-24 | 2015-08-05 | 中国船舶重工集团公司第七一九研究所 | Low-background alpha and beta activity analyzer |
CN205301597U (en) * | 2015-12-28 | 2016-06-08 | 上海新漫传感技术研究发展有限公司 | Low background liquid scintillation spectrometer measuring device |
CN107024712A (en) * | 2017-05-24 | 2017-08-08 | 中国原子能科学研究院 | One kind is determined235The device of U mass |
CN107272044A (en) * | 2017-07-07 | 2017-10-20 | 中国工程物理研究院核物理与化学研究所 | One kind measurement85Kr interior Gas Filled Detector |
US10101472B1 (en) * | 2017-10-08 | 2018-10-16 | David Edward Newman | Radiation detector with two-dimensional directionality |
CN209879001U (en) * | 2018-12-17 | 2019-12-31 | 中国原子能科学研究院 | Neutron multiplicity measuring device |
-
2018
- 2018-12-17 CN CN201811541399.9A patent/CN109557575A/en active Pending
Patent Citations (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB806306A (en) * | 1954-04-30 | 1958-12-23 | Gen Electric | Improvements in and relating to neutron detectors |
GB1197099A (en) * | 1967-08-25 | 1970-07-01 | Kernforschung Gmbh Ges Fuer | Method and device for the Non-Destructive Control of Nuclear Fuels |
US4483816A (en) * | 1982-03-31 | 1984-11-20 | The United States Of America As Represented By The Department Of Energy | Apparatus and method for quantitative assay of generic transuranic wastes from nuclear reactors |
US5083026A (en) * | 1990-02-12 | 1992-01-21 | Danev Elbaum | Method, apparatus and applications of the quantitation of multiple gamma-photon producing isotopes with increased sensitivity |
EP2275839A2 (en) * | 2002-11-06 | 2011-01-19 | American Science & Engineering, Inc. | X-ray backscatter mobile inspection van |
US20120074326A1 (en) * | 2009-07-27 | 2012-03-29 | Guntram Pausch | Apparatus and method for neutron detection with neutron-absorbing calorimetric gamma detectors |
US20120061580A1 (en) * | 2010-09-13 | 2012-03-15 | Kline Craig R | Neutron detector having enhanced absorption and bifurcated detection elements |
CN104678425A (en) * | 2015-02-02 | 2015-06-03 | 中国原子能科学研究院 | Fast-neutron multiple measuring-analyzing method based on liquid scintillation detector |
CN104820230A (en) * | 2015-04-24 | 2015-08-05 | 中国船舶重工集团公司第七一九研究所 | Low-background alpha and beta activity analyzer |
CN205301597U (en) * | 2015-12-28 | 2016-06-08 | 上海新漫传感技术研究发展有限公司 | Low background liquid scintillation spectrometer measuring device |
CN107024712A (en) * | 2017-05-24 | 2017-08-08 | 中国原子能科学研究院 | One kind is determined235The device of U mass |
CN107272044A (en) * | 2017-07-07 | 2017-10-20 | 中国工程物理研究院核物理与化学研究所 | One kind measurement85Kr interior Gas Filled Detector |
US10101472B1 (en) * | 2017-10-08 | 2018-10-16 | David Edward Newman | Radiation detector with two-dimensional directionality |
CN209879001U (en) * | 2018-12-17 | 2019-12-31 | 中国原子能科学研究院 | Neutron multiplicity measuring device |
Non-Patent Citations (1)
Title |
---|
J. JOYCE ET AL.: ""Real-Time, Fast Neutron Coincidence Assay of Plutonium With a 4-ChannelMultiplexed Analyzer and Organic Scintillators"", IEEE TRANSACTIONS ON NUCLEAR SCIENCE, vol. 61, no. 3, pages 1340 - 1348 * |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110727020A (en) * | 2019-10-11 | 2020-01-24 | 中广核研究院有限公司 | Measuring and scaling method, device and system for medium and low-level waste and storage medium |
CN110727020B (en) * | 2019-10-11 | 2022-11-11 | 中广核研究院有限公司 | Measuring and scaling method, device and system for medium-low level waste and storage medium |
CN113109862A (en) * | 2021-03-30 | 2021-07-13 | 陕西卫峰核电子有限公司 | Irradiation-resistant neutron detection device and installation method thereof |
CN113109862B (en) * | 2021-03-30 | 2022-02-15 | 陕西卫峰核电子有限公司 | Irradiation-resistant neutron detection device and installation method thereof |
CN116184482A (en) * | 2023-03-02 | 2023-05-30 | 中国人民解放军火箭军工程大学 | Helium-3-based neutron multiple self-adaptive measurement device and measurement method |
CN116184482B (en) * | 2023-03-02 | 2023-07-07 | 中国人民解放军火箭军工程大学 | Helium-3-based neutron multiple self-adaptive measurement device and measurement method |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US7388206B2 (en) | Pulse shape discrimination method and apparatus for high-sensitivity radioisotope identification with an integrated neutron-gamma radiation detector | |
Back et al. | Pulse-shape discrimination with the counting test facility | |
US20070069146A1 (en) | Fiber optic thermal/fast neutron and gamma ray scintillation detector | |
US9632188B2 (en) | Noble gas detector for fissile content determination | |
CN109557575A (en) | A kind of neutron multiplicity measuring device and its application method | |
Langford et al. | Event identification in 3He proportional counters using risetime discrimination | |
Trombetta et al. | Fast neutron-and γ-ray coincidence detection for nuclear security and safeguards applications | |
Ely et al. | Final technical report for the neutron detection without helium-3 project | |
Gehrke et al. | Acquisition of quality γ-ray spectra with HPGe spectrometers | |
Langner et al. | Application guide to neutron multiplicity counting | |
Brody et al. | Photoproduction of K+ mesons in hydrogen | |
CN209879001U (en) | Neutron multiplicity measuring device | |
Morgan et al. | An experimental system for providing data to test evaluated secondary neutron and gamma-ray-production cross sections over the incident neutron energy range from 1 to 20 MeV | |
Murer et al. | 4 he detectors for mixed oxide (mox) fuel measurements | |
Yen et al. | A high-rate 10B-loaded liquid scintillation detector for parity-violation studies in neutron resonances | |
Shcherbakov et al. | A BGO detector system for studies of neutron capture by radioactive nuclides | |
Luo et al. | Application research on neutron-gamma discrimination based on BC501A liquid scintillator | |
CN113109861A (en) | Radiation detection device and method thereof | |
CN103424767A (en) | Method for measuring content of 235U and 239Pu in U-Pu mixture | |
Ruirui et al. | Detector development at the Back-n white neutron source | |
EP0042099A2 (en) | Self-regulating neutron coincidence counter | |
Trombetta et al. | Investigation of the use of coincidences between fast neutrons and gamma rays for the detection of special nuclear materials | |
Chandra et al. | Gamma-insensitive fast neutron detector with spectral source identification potential | |
US5164149A (en) | Nuclide separation type of precipitator system | |
Olsher et al. | Proton recoil scintillator neutron rem meter |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PB01 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination |