CN108051847A - Utilize the method for lanthanum bromide detector measurement neutron dose rate and neutron dose rate instrument - Google Patents
Utilize the method for lanthanum bromide detector measurement neutron dose rate and neutron dose rate instrument Download PDFInfo
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Abstract
The invention discloses utilize the method for lanthanum bromide detector measurement neutron dose rate and neutron dose rate instrument, wherein, there are deterministic functional relations between neutron dose rate caused by the point for the net counting rate and the neutron at the middle subcharacter γ energy peak that the method for measurement neutron dose rate is generated using neutron in lanthanum bromide detector, by measuring gamma spectrum, and the deterministic functional relation is utilized, it calculates and obtains neutron dose rate.Therefore, using the embodiment of the present invention measurement neutron dose rate method can it is more convenient, quickly and accurately obtain neutron dose rate.
Description
Technical field
The invention belongs to radiation detection, enviromental monitoring equipment technical fields, specifically, the present invention relates to the use of lanthanum bromide
The method of detector measurement neutron dose rate and neutron dose rate instrument.
Background technology
Neutron dose rate instrument is a kind of radiation prison for the Neutron Ambient Dose Equivalent rate for being used to measure and evaluate neutron irradiation generation
Measurement equipment.At present, common radiation protection neutron dose rate instrument is formed substantially including slow body, neutron energy compensation material
Material, the sensitive counter of thermal neutron and electronics circuit.It is structurally characterized in that the sensitive counter of thermal neutron is spherical or cylindrical
Slow body is rolled at center；In slow body, from central detector it is a certain with a distance from it is upper set one with slow neutron penetrate hole neutron
Absorb sieve or with the absorbed layer containing boron material, incident neutron is injected after slow body by slowing down (or thermal neutron diffusion), is inhaled passing through
Slow (heat) neutron of a part is absorbed when receiving sieve (or absorbed layer), and a certain proportion of neutron passes through, through in the part for absorbing sieve
Son continues by slowing down or diffusion, and finally the part neutron of arrival central detector, which is detected, records.
Existing neutron dose rate instrument according to the difference of structure design, can be roughly divided into three classes：When single counter type,
For this kind of dose rate instrument using single spherical or cylindricality polyethylene as slow body, the centre of sphere places single proportional counter (such as BF3、3He) or6Li glass scintillators are mingled with some boron plastics or cadmium material isotonic energy compensating Jing Guo special designing among sphere
Material.Second is that multi-counter type, the slow body of this kind of dose rate instrument is that single ball or the design of more balls, probe use multiple counters
Device is (such as3He), the centre of sphere or spherical surface of slow body are individually positioned in, is mingled with neutron energy compensating material among sphere.Third, spectrum
Instrument type, thermal-neutron detector is wrapped in the slowing down spherical shell of different-diameter by this kind of dose rate instrument respectively, slow using different size
It is different to change the moderating power of ball, obtains the neutron response of different-energy, is solved by the degraded neutron power spectrum obtained to measurement
Spectrum, solves the actual power spectrum of Neutron Radiation Field, and then the neutron dose rate of radiation field is calculated.
Lanthanum bromide detector is a kind of new Inorganic scintillation bulk detector, has outstanding temporal resolution (hundreds of skins
Second), high energy resolution (<3%, for 662keV gamma-rays) and high detection efficient, it is widely used in gamma spectrum measurement.Make
For Inorganic scintillation build detector, lanthanum bromide detector is mainly made of lanthanum bromide crystal, and component mainly includes La and Br,
Consider from natural isotopic abundance, mainly139La,79Br and81Br, three kinds of nucleic are stable nuclide.But when neutron incides into
During lanthanum bromide crystalline material, nuclear reaction can occur with target substance nucleic for neutron, and key reaction type includes elastic scattering, non-resilient
Scattering and radiation capture.Wherein, if neutron kinetic energy is enough to excite target nucleus, inelastic scattering A (n, n ' γ) A ' occurs, then enter
Atomic nucleus can be passed to by a part for initial kinetic energy by hitting son, and target nucleus is made to be energized into excitation state, and when target nucleus de excitation releases γ and penetrates
Line, such as79Br (n, n ' γ)79mBr,79mBr de excitations can release the gamma-rays that energy is 217keV；It is anti-in the event of radiation capture
Answer A (n, γ) B, then target nucleus captures neutron, generates new target nucleus, and new core is generally in unstable excited state, excites energy
Depending on the combination energy and kinetic energy of neutron, excited nucleus can return ground state by emitting one or several γ quantum and transition, and can send out
Subsequent radioactive decay is penetrated, such as139La(n,γ)140La,140La is with β-Form decay be140Ce；79Br(n,γ)80Br
,80Br is with β-It decays with the mode of orbital electron capture and is80Kr；81Br(n,γ)82Br,82Br is with β-Mode decay and be82Kr.Core
The gamma-rays of different-energy caused by reaction can be brominated lanthanum detector and detect and differentiate.
In recent years, go deep into research, foreign study person by experimental studies have found that, utilize above-mentioned nuclear reaction generate γ
The physical mechanism of ray, using time-of-flight method, it can be achieved that detection of the lanthanum bromide detector to neutron, for example, for 700keV
Neutron, the detection efficient of 2in × 2in lanthanum bromide detectors is up to 5%.From detector itself, which is list
Better than other kinds of neutron detector.But above-mentioned detection method is based on time-of-flight method, is not particularly suited for radiation protection
Field.Because time-of-flight method be based on different-energy (flying speed) neutron leap it is a certain it is definite apart from required time not
Together, it will be the measurement the time required to leaping selected distance to the neutron to the measures conversion of neutron energy, pass through time of measuring point
Cloth, so that it is determined that neutron energy is distributed.This method need extremely precisely to record start time of the neutron in flying distance and
End of time, this is clearly what can not be realized in radiation protection field.
Therefore, the present invention proposes a kind of neutron dose rate instrument based on lanthanum bromide detector, for radiation protection field
Neutron dose rate measures.
The content of the invention
It is contemplated that it solves at least some of the technical problems in related technologies.For this purpose, the present invention
One purpose is to propose the measurement method of neutron dose rate and neutron dose rate instrument, using measurement neutron agent proposed by the present invention
The method of dose rate, this method can be reacted using lanthanum bromide detector with incident neutron, generate the feature γ of different-energy
Can peak, and detected and differentiated using lanthanum bromide detector, and then the net of neutron dose rate and feature γ energy peak can be utilized
Deterministic functional relation obtains neutron dose rate between counting rate.
Inventor has found, can realize detection of the lanthanum bromide detector to neutron using time-of-flight method, but pass through essence
Really start time and end of time of the record neutron in selected flying distance are led to determine that neutron energy is distributed in radiation protection
Domain can not realize that time-of-flight method is not particularly suited for radiation protection field.Inventors be surprised to learn that neutron is brilliant with lanthanum bromide
Body material react generation different-energy feature γ can peak the variation of net counting rate and the variation of neutron dose rate become
Gesture is consistent, using deterministic functional relation between the net counting rate at neutron dose rate and feature γ energy peak, can be passed through
The net counting rate combination for measuring one or several middle subcharacter γ energy peaks is calculated with spectrum unscrambling, realizes the survey of radiation field neutron dose rate
Amount.
For this purpose, according to the first aspect of the invention, the present invention proposes a kind of method for measuring neutron dose rate, according to
Specific embodiments of the present invention, the net meter at the middle subcharacter γ energy peak that the method is generated using neutron in lanthanum bromide detector
Digit rate and the neutron between neutron dose rate caused by the point there are deterministic functional relation, by measuring gamma spectrum,
And the deterministic functional relation is utilized, it calculates and obtains neutron dose rate.
The method of the measurement neutron dose rate proposed according to the present invention, is actually based on inventor and is found that, neutron exists
The middle subcharacter γ generated in lanthanum bromide detector can the net counting rate at peak and neutron neutron dose rate caused by the point
Between there are deterministic functional relations.And then may be employed neutron dose rate instrument based on lanthanum bromide detector measure one or
The feature γ that several incident neutrons generate can peak combination, and using neutron dose rate and middle subcharacter γ can peak net counting rate it
Between deterministic functional relation obtain neutron dose rate.
In some embodiments of the invention, the method for the measurement neutron dose rate includes：
Neutron is detected using lanthanum bromide detector, it can peak to obtain feature γ；
Based on feature γ energy peak, calculate and obtain neutron dose rate, wherein, the neutron dose rate and the feature γ
In deterministic functional relation, functional relation is represented by the net counting rate at energy peak：
Di=f (Ni)
Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiNuclear reaction occurs for incident neutron and lanthanum bromide crystalline material
The net counting rate at the feature γ energy peak of generation, unit cps.
In some embodiments of the invention, in the deterministic functional relation, the scope of the net counting rate is：Ni
>0。
In some embodiments of the invention, in the deterministic functional relation, the measurement model of the neutron dose rate
Enclose for：Di>0。
In some embodiments of the invention, the neutron is generated by californium source.Thus, it is possible to it generates in different-energy
Son, and react with lanthanum bromide crystal, and then the feature γ energy peak of different-energy is generated, and then neutron dose rate can be utilized
Functional relation between the net counting rate of peak position obtains neutron dose rate.
In some embodiments of the invention, the feature γ energy peak is included selected from least one following：22.34±
5keV、54.64±5keV、83.05±5keV、101.1±5keV、119.2±5keV、166.5±5keV、207.1±5keV、
217.5±5keV、243.3±5keV、276.7±5keV、294.9±5keV、307.2±5keV、335±5keV、344±
5keV、387.9±5keV、536.9±10keV、606.9±10keV、650.5±5keV、725.1±10keV、766.8±
10keV842.7±10keV、872.4±10keV、962.8±10keV、1002±10keV、1043±10keV、1084±
10keV、1115±10keV、1268±10keV.Thus, it is possible to further improve the precision of measurement neutron dose rate.
In some embodiments of the invention, the deterministic functional relation be logarithmic function relation, the logarithm letter
Number relation is expressed as：
Di=alnNi+b
Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiIt reacts production for incident neutron and lanthanum bromide crystalline material
The net counting rate at raw feature γ energy peak, unit cps；A, b are constant, and a>0.
In some embodiments of the invention, the deterministic functional relation be linear fit function, the Linear Quasi
Closing function representation is：
Di=kNi+c
Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiIt reacts production for incident neutron and lanthanum bromide crystalline material
The net counting rate at raw feature γ energy peak, unit cps；K, c are constant, and k>0.
According to another aspect of the present invention, the invention also provides a kind of neutron dose rate instrument, the neutron dose rates
Instrument has lanthanum bromide detector, and the lanthanum bromide detector, which is suitable for reacting with incident neutron, generates feature γ energy peak, and visits
Measure the power spectrum of feature γ full energy peaks.
The neutron dose rate instrument proposed according to the present invention, by by lanthanum bromide detector for neutron dose rate instrument, can be with
Incident neutron is made to react with lanthanum bromide crystalline material, generates the feature γ energy peak of different-energy, and is detected using lanthanum bromide
Device detects the feature γ energy peak of generation.As a result, using neutron dose rate instrument proposed by the present invention, measurement one can be passed through
A or several middle subcharacter γ energy peaks combinations, and it is deterministic between the net counting rate at utilization neutron dose rate and feature γ energy peak
Functional relation realizes the measurement of radiation field neutron dose rate.
Description of the drawings
Fig. 1 is the background spectrum and measurement obtained using the neutron dose rate instrument measurement of one embodiment of the invention252Cf sources obtain
The measurement spectrogram arrived.
Fig. 2 is to be measured using the neutron dose rate instrument of one embodiment of the invention in the radiation field of different neutron dose rates
Obtained measurement spectrogram.
Fig. 3 is the relation between the net counting rate at neutron dose rate according to an embodiment of the invention and feature γ energy peak
Figure.
Fig. 4 is the relation between the net counting rate at neutron dose rate according to an embodiment of the invention and feature γ energy peak
Figure.
Fig. 5 is the relation between the net counting rate at neutron dose rate according to an embodiment of the invention and feature γ energy peak
Figure.
Fig. 6 is the relation between the net counting rate at neutron dose rate according to an embodiment of the invention and feature γ energy peak
Figure.
Specific embodiment
The embodiment of the present invention is described below in detail, the example of the embodiment is shown in the drawings, wherein from beginning to end
Same or similar label represents same or similar element or has the function of same or like element.Below with reference to attached
The embodiment of figure description is exemplary, it is intended to for explaining the present invention, and is not considered as limiting the invention.
According to an aspect of the present invention, the present invention proposes a kind of method for measuring neutron dose rate, according to the present invention
Specific embodiment, the middle subcharacter γ that the method is generated in lanthanum bromide detector using neutron can peak net counting rate with
The neutron, there are deterministic functional relation, by measuring gamma spectrum, and utilizes between neutron dose rate caused by the point
The deterministic functional relation calculates and obtains neutron dose rate.
The method of the measurement neutron dose rate proposed according to the present invention, is actually based on inventor and is found that, neutron exists
The middle subcharacter γ generated in lanthanum bromide detector can the net counting rate at peak and neutron neutron dose rate caused by the point
Between there are deterministic functional relations.And then may be employed neutron dose rate instrument based on lanthanum bromide detector measure one or
The feature γ that several incident neutrons generate can peak combination, and using neutron dose rate and middle subcharacter γ can peak net counting rate it
Between deterministic functional relation obtain neutron dose rate.
Specific implementation according to the present invention, the method for the measurement neutron dose rate of above-described embodiment include：Using lanthanum bromide
Detector detects neutron, can peak to obtain feature γ；Based on feature γ energy peak, calculate and obtain neutron dose
Rate, wherein, the net counting rate of the neutron dose rate and feature γ energy peak is in deterministic functional relation, and functional relation can
It is expressed as：
Di=f (Ni)
Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiNuclear reaction occurs for incident neutron and lanthanum bromide crystalline material
The net counting rate at the feature γ energy peak of generation, unit cps.
The method of measurement neutron dose rate according to the above embodiment of the present invention, may be employed neutron dose rate instrument measurement and enters
One or several feature γ for hitting sub- generation can be between peak and utilization neutron dose rate and the net counting rate at feature γ energy peak really
Qualitatively functional relation obtains the neutron dose rate of measured point position.
According to a particular embodiment of the invention, the N in above-mentioned certainty functional relationi>0, Di>0.This method is applicable in as a result,
Scope is more extensive.
According to a particular embodiment of the invention, be tested neutron by californium source (252Cf) generate.Thus, it is possible to utilize californium source
(252Cf the neutron of different-energy) can be generated, and is reacted with lanthanum bromide crystal, and then generates the feature γ energy of different-energy
Peak, and then the functional relation between neutron dose rate and the net counting rate of peak position can be utilized to obtain neutron dose rate.
According to a particular embodiment of the invention, feature γ energy peak can be including but not limited to selected from one of following：22.34
±5keV、54.64±5keV、83.05±5keV、101.1±5keV、119.2±5keV、166.5±5keV、207.1±
5keV、217.5±5keV、243.3±5keV、262±5keV、276.7±5keV、294.9±5keV、307.2±5keV、
335±5keV、344±5keV、387.9±5keV、536.9±10keV、606.9±10keV、650.5±5keV、725.1±
10keV、766.8±10keV 842.7±10keV、872.4±10keV、962.8±10keV、1002±10keV、1043±
10keV、1084±10keV、1115±10keV、1268±10keV。
According to a particular embodiment of the invention, the deterministic functional relation be logarithmic function relation, the logarithm letter
Number relation is expressed as：
Di=alnNi+b
Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiIt reacts production for incident neutron and lanthanum bromide crystalline material
The net counting rate at raw feature γ energy peak, unit cps；A, b are constant, and a>0.From there through above-mentioned functional relation, root
Neutron is detected according to lanthanum bromide detector, obtains the net counting rate N at feature γ energy peaki, and then effectively calculate neutron agent
Dose rate Di.Therefore, the method for the measurement neutron dose rate of the above embodiment of the present invention more convenient can rapidly measure neutron
Dosage rate.
According to a particular embodiment of the invention, the certainty functional relation, is represented by linear fit function.Function
Concrete form is represented by：
Di=kNi+c
Wherein, DiFor neutron dose rate, μ Sv/h；NiReact the spy of generation for incident neutron and lanthanum bromide crystalline material
Levy the net counting rate at γ energy peak, unit cps；K, c are constant, and k>0.From there through above-mentioned functional relation, according to bromination
Lanthanum detector detects neutron, obtains the net counting rate N at feature γ energy peaki, and then effectively calculate neutron dose rate Di。
Therefore, the method for the measurement neutron dose rate of the above embodiment of the present invention more convenient can rapidly measure neutron dose rate.
According to an aspect of the present invention, the present invention proposes a kind of neutron dose rate instrument, and neutron dose rate instrument has bromine
Change lanthanum detector, lanthanum bromide detector, which is suitable for reacting with incident neutron, generates feature γ energy peak, and detects and obtain feature γ
The power spectrum of full energy peak.
Neutron dose rate instrument according to the above embodiment of the present invention, by the way that lanthanum bromide detector is used for neutron dose rate
Instrument can make incident neutron react with lanthanum bromide crystalline material, generate the feature γ energy peak of different-energy, and utilize bromination
Lanthanum detector detects the feature γ energy peak of generation.The neutron dose rate instrument of the above embodiment of the present invention is used as a result, it can
With by measure one or several middle subcharacter γ can peaks combination, and using neutron dose rate and feature γ can peak net count
Deterministic functional relation between rate realizes the measurement of radiation field neutron dose rate.
According to a particular embodiment of the invention, the operation principle of neutron dose rate instrument is：Incident neutron and lanthanum bromide crystal
Material reacts, and the feature γ for generating different-energy can peak, the feature γ energy net counting rates at peak and the neutron dose of radiation field
There are deterministic functional relation between rate, it is：
Di=f (Ni)
Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiNuclear reaction occurs for incident neutron and lanthanum bromide crystalline material
The net counting rate at the feature γ energy peak of generation, unit cps.The variation of the net counting rate at the feature γ energy peak of different-energy is in
The variation tendency of sub- dosage rate is consistent, is combined by the net counting rate for measuring any one or several middle subcharacter γ energy peaks
It is calculated with corresponding spectrum unscrambling, can obtain the neutron dose rate of tested radiation field.
Embodiment 1
Neutron dose rate is measured using neutron dose rate instrument.Wherein, neutron dose rate instrument has lanthanum bromide detector, bromination
Lanthanum detector uses 3in × 3in lanthanum bromide detectors (LaBr3:Ce).Neutron source to be measured chooses californium source (Cf-252 sources).
252Cf sources and lanthanum bromide crystal react generation feature γ can peak include but is not limited to the energy that table 1 is listed
Value；Table 2 for neutron and lanthanum bromide crystal react generation feature γ can the energy at peak, feature γ can peak net counting rate with
Neutron dose rate, feature γ energy peak include but is not limited to 5 energy listed by table 2.
The background spectrum obtained using neutron dose rate instrument measurement and measurement252The measurement spectrum that Cf sources obtain is as shown in Figure 1；Fig. 2
The gamma spectra that neutron dose rate instrument detects during to measure different neutron dose rates, neutron dose rate include but is not limited to
7 kinds of dosage rate levels listed by Fig. 2；Relations of the Fig. 3 between neutron dose rate and feature γ energy peak net counting rate, neutron dose
Rate includes but is not limited to 7 kinds of dosage rate levels described in Fig. 3, and feature γ energy peak includes but is not limited to 5 kinds of energy listed by Fig. 3.
Fig. 4 is after being normalized according to the maximum of each energy peak net counting rate, and neutron dose rate is counted only with feature γ energy peak
Relation between digit rate, neutron dose rate include but is not limited to 7 kinds of dosage rate levels described in Fig. 4, feature γ can peak include but
It is not limited to 4 kinds of energy listed by Fig. 4.When Fig. 5 is characterized γ peaks and takes 119.2keV peaks, neutron dose rate and feature γ can peak count only
Relation between digit rate, the functional relation are in logarithmic function relation, and neutron dose rate includes but is not limited to 7 kinds of agent described in Fig. 5
Dose rate is horizontal, and feature γ energy peak includes but is not limited to energy listed by Fig. 5.When Fig. 6 is characterized γ peaks and takes 119.2keV peaks, neutron
Relation between dosage rate and feature γ energy peak net counting rate, the linear fitting function relation of the functional relation, neutron dose rate
7 kinds of dosage rate levels described in including but not limited to Fig. 6, feature γ energy peak include but is not limited to energy listed by Fig. 6.
Table 1252Cf sources and lanthanum bromide crystal react the feature γ of generation can peak
The energy at subcharacter γ energy peak, the net counting rate and neutron dose rate at feature γ energy peak in table 2
Neutron and lanthanum bromide crystal are can be seen that according to the measured result of Fig. 3 and Fig. 4 to react the feature γ energy of generation
Qualitative functional relationship is represented by logarithmic function really between the net counting rate and neutron dose rate at peak.The concrete form of function can
It is expressed as：
Di=alnNi+b
Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiIt reacts production for incident neutron and lanthanum bromide crystalline material
The net counting rate at raw feature γ energy peak, unit cps；A, b are constant, and a>0.It is taken for example, Fig. 5 is characterized γ peaks
During 119.2keV peaks, neutron dose rate is in logarithmic function relation with feature γ energy peak net counting rate.The feature γ energy of different-energy
The variation of the net counting rate at peak and the variation tendency of neutron dose rate are consistent, i.e., by measuring any one or several neutrons
The net counting rate combination at feature γ energy peak can obtain the neutron dose rate of tested radiation field.
Neutron and lanthanum bromide crystal are can be seen that according to the measured result of Fig. 3 and Fig. 4 to react the feature γ energy of generation
Qualitative functional relationship is represented by linear fit function really between the net counting rate and neutron dose rate at peak.The specific shape of function
Formula is represented by：
Di=kNi+c
Wherein, DiFor neutron dose rate, μ Sv/h；NiReact the spy of generation for incident neutron and lanthanum bromide crystalline material
Levy the net counting rate at γ energy peak, unit cps；K, c are constant, and k>0.For example, Fig. 6, which is characterized γ peaks, takes 119.2keV peaks
When, neutron dose rate can the linear fitting function relation of peak net counting rate with feature γ.The feature γ of different-energy can peak it is net
The variation of counting rate and the variation tendency of neutron dose rate are consistent, i.e., by measuring any one or several middle subcharacter γ
The net counting rate combination at energy peak can obtain the neutron dose rate of tested radiation field.
In the description of this specification, reference term " one embodiment ", " some embodiments ", " example ", " specifically show
The description of example " or " some examples " etc. means specific features, structure, material or the spy for combining the embodiment or example description
Point is contained at least one embodiment of the present invention or example.In the present specification, schematic expression of the above terms is not
It must be directed to identical embodiment or example.Moreover, particular features, structures, materials, or characteristics described can be any
It is combined in an appropriate manner in a or multiple embodiments or example.In addition, without conflicting with each other, the technology of this field
Different embodiments described in this specification or example and different embodiments or exemplary feature can be combined by personnel
And combination.
Although the embodiment of the present invention has been shown and described above, it is to be understood that above-described embodiment is example
Property, it is impossible to limitation of the present invention is interpreted as, those of ordinary skill in the art within the scope of the invention can be to above-mentioned
Embodiment is changed, changes, replacing and modification.
Claims (9)
- A kind of 1. method for measuring neutron dose rate, which is characterized in that the method is produced using neutron in lanthanum bromide detector There are deterministic between neutron dose rate caused by the point for the net counting rate and the neutron at raw middle subcharacter γ energy peak Functional relation by measuring gamma spectrum, and utilizes the deterministic functional relation, calculates and obtain neutron dose rate.
- 2. according to the method described in claim 1, it is characterised in that it includes：Neutron is detected using lanthanum bromide detector, it can peak to obtain feature γ；Based on feature γ energy peak, calculate and obtain neutron dose rate, wherein, the neutron dose rate can peak with the feature γ Net counting rate in deterministic functional relation, functional relation is represented by：Di=f (Ni)Wherein, DiFor neutron dose rate, unit is μ Sv/h；NiNuclear reaction occurs for incident neutron and lanthanum bromide crystalline material to generate Feature γ can peak net counting rate, unit cps.
- 3. according to the method described in claim 2, it is characterized in that, in the deterministic functional relation, the net counting rate Scope be：Ni>0。
- 4. according to the method described in claim 2, it is characterized in that, in the deterministic functional relation, the neutron dose The measurement range of rate is：Di>0。
- 5. according to the method described in claim 1, it is characterized in that, the neutron is generated by californium source.
- 6. method according to claim 1 or 5, which is characterized in that the feature γ can peak include selected from it is following at least it One：22.34±5keV、54.64±5keV、83.05±5keV、101.1±5keV、119.2±5keV、173.5±5keV、 207.1±5keV、217.5±5keV、243.3±5keV、262±5keV、276.7±5keV、294.9±5keV、307.2± 5keV、335±5keV、344±5keV、387.9±5keV、536.9±10keV、606.9±10keV、650.5±10keV、 725.1±10keV、766.8±10keV 842.7±10keV、872.4±10keV、962.8±10keV、1002±10keV、 1043±10keV、1084±10keV、1115±10keV、1268±10keV。
- 7. according to the method described in claim 2,5 or 6, which is characterized in that the deterministic functional relation is logarithmic function Relation, the logarithmic function relation are expressed as：Di=alnNi+bWherein, DiFor neutron dose rate, unit is μ Sv/h；NiIt reacts generation for incident neutron and lanthanum bromide crystalline material The net counting rate at feature γ energy peak, unit cps；A, b are constant, and a>0.
- 8. according to the method described in claim 2,5 or 6, which is characterized in that the deterministic functional relation is linear fit Function, the linear fit function representation are：Di=kNi+cWherein, DiFor neutron dose rate, unit is μ Sv/h；NiIt reacts generation for incident neutron and lanthanum bromide crystalline material The net counting rate at feature γ energy peak, unit cps；K, c are constant, and k>0.
- 9. a kind of neutron dose rate instrument, which is characterized in that the neutron dose rate instrument has lanthanum bromide detector, the lanthanum bromide Detector, which is suitable for reacting with incident neutron, generates feature γ energy peak, and detects and obtain the power spectrum of feature γ full energy peaks.
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| CN201711269585.7A CN108051847B (en) | 2017-12-05 | 2017-12-05 | Utilize the method and neutron dose rate instrument of lanthanum bromide detector measurement neutron dose rate |
| PCT/CN2018/116973 WO2019109812A1 (en) | 2017-12-05 | 2018-11-22 | Method for measuring neutron dose rate by means of lanthanum bromide detector, and neutron dose rate meter |
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|---|---|---|---|---|
| CN109669207A (en) * | 2019-02-01 | 2019-04-23 | 清华大学 | Utilize the method for lanthanum bromide detector measurement Neutron Radiation Field neutron energy spectrum |
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| WO2019109812A9 (en) | 2019-10-17 |
| CN108051847B (en) | 2019-10-29 |
| WO2019109812A1 (en) | 2019-06-13 |
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