CN107422359A - A kind of measuring method of the neutron gamma dosage based on liquid scintillation bulk detector - Google Patents
A kind of measuring method of the neutron gamma dosage based on liquid scintillation bulk detector Download PDFInfo
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- CN107422359A CN107422359A CN201710344835.2A CN201710344835A CN107422359A CN 107422359 A CN107422359 A CN 107422359A CN 201710344835 A CN201710344835 A CN 201710344835A CN 107422359 A CN107422359 A CN 107422359A
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- 239000007788 liquid Substances 0.000 title claims abstract description 20
- 238000000034 method Methods 0.000 title claims abstract description 16
- 238000001228 spectrum Methods 0.000 claims abstract description 19
- 238000012545 processing Methods 0.000 claims abstract description 5
- 238000004980 dosimetry Methods 0.000 claims abstract 5
- 230000002285 radioactive effect Effects 0.000 claims description 7
- 239000011159 matrix material Substances 0.000 claims description 5
- 238000004364 calculation method Methods 0.000 claims description 4
- 238000009795 derivation Methods 0.000 claims description 4
- 230000005855 radiation Effects 0.000 abstract description 6
- 238000004088 simulation Methods 0.000 abstract description 3
- 238000011160 research Methods 0.000 abstract description 2
- 238000005259 measurement Methods 0.000 description 7
- 210000001367 artery Anatomy 0.000 description 2
- 210000003462 vein Anatomy 0.000 description 2
- 230000008901 benefit Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000000151 deposition Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 239000000686 essence Substances 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 238000012216 screening Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/02—Dosimeters
- G01T1/023—Scintillation dose-rate meters
-
- 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
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Abstract
The invention discloses a kind of measuring method and system of the neutron gamma dosage based on liquid scintillation bulk detector, neutron, gamma are detected simultaneously using liquid scintillation detector；Using the output pulse of digitizer total digitalization record detector；Data acquisition and control unit processing pulse signal, screen out neutron, gamma pulses signal, and the pulse signal after examination is counted according to neutron, gamma respectively, obtains neutron, gamma pulses height spectrum；Calculated by simulation and draw neutron, G (e) functions of gamma respectively, G (e) functions of neutron, gamma are combined with respective pulse-height spectrum respectively, calculate neutron, the Neutron Ambient Dose Equivalent value of gamma.The neutron gamma Dosimetry based on liquid scintillation bulk detector in the present invention, it can be achieved to measure while mixed radiation field neutron, gamma dosage, pulse signals total digitalization collection and storage, support is provided for follow-up data processing, is monitored in actual dose with having wide application prospects in terms of scientific research.
Description
Technical field
The invention belongs to radiation field measurement field, more particularly, to a kind of neutron gamma based on liquid scintillation bulk detector
The measuring method of dosage.
Background technology
Radiation dose measurement is in scientific research field, nuclear industry, nuclear safety, environmental protection, industry and medical radiation source control, public affairs
The field such as safety has a wide range of applications altogether, therefore the measurement to dose of radiation is very important.Typically use liquid scintillation
Detector is realized to neutron, the measurement of gamma.Also, in recent years, the neutron related to scintillation detector/gamma screening techniques have
Very fast development.
The content of the invention
In view of this, the present invention is directed to propose a kind of measurement side of the neutron gamma dosage based on liquid scintillation bulk detector
Method, to be measured while realizing neutron in mixed radiation field, gamma close rate, realize the total digitalization collection of pulse signal with depositing
Storage, data supporting is provided for subsequent treatment.
To reach above-mentioned purpose, the technical proposal of the invention is realized in this way：
A kind of measuring method of the neutron gamma dosage based on liquid scintillation bulk detector, including：
1) neutron, gamma are detected simultaneously using liquid scintillation detector；
2) using the output pulse of digitizer total digitalization record detector；
3) data acquisition and control unit processing pulse signal, screen out neutron, gamma pulses signal, by the arteries and veins after examination
Rush signal to count according to neutron, gamma respectively, obtain neutron, gamma pulses height spectrum；
4) by simulate the method for calculations incorporated standard radioactive source scale be derived from respectively neutron, gamma G (e) letters
Number, G (e) functions of neutron, gamma are combined with neutron, gamma pulses height spectrum respectively, dosage around calculating neutron, gamma
Equivalent value.
Further, in the step 3, data acquisition uses LabVIEW softwares with control unit.
Further, in the step 4, G (e) function derivation methods are：By different standard radioactive sources, collection is not
Same pulse-height spectrum, while using detector position Neutron Ambient Dose Equivalent theoretical value during MCNP software computing scales, pass through
Formula is counter to release G (e) functions, and expression formula is as follows：
Pulse-height spectrum × G (e)=Neutron Ambient Dose Equivalent
In formula, G (e) functions are as a matrix.
Further, in the step 4, the standard source of gamma uses22Na、133Ba and137Cs etc.；The standard source of neutron
Using252Cf。
Relative to prior art, a kind of neutron gamma dosage measurement based on liquid scintillation bulk detector of the present invention
Method has the advantage that：Utilize liquid scintillation bulk detector detection neutron, gamma signal；Detector is realized using digitizer
Export the full record of pulse；Realize that pulse signal screens (neutron, gamma are screened), obtained by simulation and standard source experimental calculation
Neutron, gamma G (e) functions, then calculate neutron, gamma close rate respectively in connection with the pulse-height spectrum of neutron, gamma.
Brief description of the drawings
Fig. 1 is the measuring method schematic flow sheet described in the embodiment of the present invention.
Embodiment
It should be noted that in the case where not conflicting, the feature in embodiment and embodiment in the present invention can phase
Mutually combination.
Describe the present invention in detail below with reference to the accompanying drawings and in conjunction with the embodiments.
A kind of measuring method of the neutron gamma dosage based on liquid scintillation bulk detector, including：
1) neutron, gamma are detected simultaneously using liquid scintillation detector；
2) using the output pulse of digitizer total digitalization record detector；
3) data acquisition and control unit processing pulse signal, screen out neutron, gamma pulses signal, by the arteries and veins after examination
Rush signal to count according to neutron, gamma respectively, obtain neutron, gamma pulses height spectrum；
4) by simulate the method for calculations incorporated standard radioactive source scale be derived from respectively neutron, gamma G (e) letters
Number, G (e) functions of neutron, gamma are combined with neutron, gamma pulses height spectrum respectively, dosage around calculating neutron, gamma
Equivalent value.
It is worth noting that, in the step 3, data acquisition uses LabVIEW softwares with control unit, uses
LabVIEW softwares are handled the pulse signal of record, and then distinguish neutron, gamma, by the pulse signal after examination point
Not according to neutron, gamma integration statistics, neutron, the pulse-height spectrum of gamma are obtained.
It is worth noting that, in the step 4,
G (e) function derivation methods are：By different standard radioactive sources, different pulse-height spectrums are gathered, are utilized simultaneously
Detector position Neutron Ambient Dose Equivalent theoretical value during MCNP software computing scales, G (e) functions, table are released by the way that formula is counter
It is as follows up to formula：
Pulse-height spectrum × G (e)=Neutron Ambient Dose Equivalent
In formula, G (e) functions are as a matrix.
During anti-derivation G (e) function, the coefficient of G (e) functions is obtained using least square fitting, so as to obtain neutron spectra G
(E) function and γ spectrum G (E) functions.For G (e) functions as a matrix, it is that surrounding dosage is worked as that pulse-height spectrum, which is multiplied by the matrix,
Value.
It is worth noting that, in the step 4, the standard source of gamma uses22Na、133Ba and137The gamma ray sources such as Cs；In
The standard source of son uses252Cf.Energy response scale linearly dependent coefficient is 0.99963, and more than 0.95, test result is good.
Utilize liquid scintillation bulk detector pair22Na and252Cf is measured, and utilizes the simulation of MCNP softwares and standard source
G (E) function obtained is tested, radioactive source Neutron Ambient Dose Equivalent is calculated.To neutron, gamma dose equivalent rate measurement result
Relative deviation is respectively less than 50%.
The foregoing is merely illustrative of the preferred embodiments of the present invention, is not intended to limit the invention, all essences in the present invention
God any modification, equivalent substitution and improvements made etc., should be included in the scope of the protection with principle.
Claims (4)
- A kind of 1. neutron gamma Dosimetry based on liquid scintillation bulk detector, it is characterised in that：Including：1) neutron, gamma are detected simultaneously using liquid scintillation detector；2) using the output pulse of digitizer total digitalization record detector；3) data acquisition and control unit processing pulse signal, screen out neutron, gamma pulses signal, the pulse after examination are believed Counted number respectively according to neutron, gamma, obtain neutron, gamma pulses height spectrum；4) by simulate the method for calculations incorporated standard radioactive source scale be derived from respectively neutron, gamma G (e) functions, will Neutron, G (e) functions of gamma are combined with neutron, gamma pulses height spectrum respectively, calculate neutron, gamma Neutron Ambient Dose Equivalent Value.
- 2. a kind of neutron gamma Dosimetry based on liquid scintillation bulk detector according to claim 1, it is special Sign is：In the step 3, data acquisition uses LABVIEW softwares with control unit.
- 3. a kind of neutron gamma Dosimetry based on liquid scintillation bulk detector according to claim 1, it is special Sign is：In the step 4, G (e) function derivation methods are：By different standard radioactive sources, different pulse heights are gathered Spectrum, while using detector position Neutron Ambient Dose Equivalent theoretical value during MCNP software computing scales, G is released by the way that formula is counter (e) function, expression formula are as follows：Pulse-height spectrum × G (e)=Neutron Ambient Dose EquivalentIn formula, G (e) functions are as a matrix.
- 4. a kind of neutron gamma Dosimetry based on liquid scintillation bulk detector according to claim 3, it is special Sign is：In the step 4, the standard source of gamma uses22Na、133Ba and137Cs etc.；The standard source of neutron uses252Cf。
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Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108051847A (en) * | 2017-12-05 | 2018-05-18 | 清华大学 | Utilize the method for lanthanum bromide detector measurement neutron dose rate and neutron dose rate instrument |
| CN108490477A (en) * | 2018-03-14 | 2018-09-04 | 中国人民解放军火箭军工程大学 | A kind of n- γ pulses discriminating methods and system based on improvement centroid algorithm |
| CN108627867A (en) * | 2018-03-14 | 2018-10-09 | 中国人民解放军火箭军工程大学 | A kind of real-time discrimination systems of digitlization n- γ |
| CN110057843A (en) * | 2019-04-16 | 2019-07-26 | 中国辐射防护研究院 | Radioactive source shipping container gamma shielding method for testing performance and system based on G (E) function |
| CN110361773A (en) * | 2019-06-05 | 2019-10-22 | 中国辐射防护研究院 | A method of positioning unknown power spectrum Neutron Radiation Field neutron source position |
| CN110806599A (en) * | 2019-12-12 | 2020-02-18 | 中国工程物理研究院激光聚变研究中心 | Pulse gating type neutron detector and detection method thereof |
| CN111221030A (en) * | 2019-12-03 | 2020-06-02 | 北京卫星环境工程研究所 | Neutron-gamma detector based on physical integration and neutron-gamma online screening method |
| CN112034177A (en) * | 2020-07-09 | 2020-12-04 | 中国工程物理研究院材料研究所 | Use of NPY as molecular marker for diagnosis of long-term low-dose ionizing radiation exposure |
| CN112882082A (en) * | 2021-01-12 | 2021-06-01 | 中国人民解放军海军工程大学 | Neutron-gamma ambient dose equivalent rate instrument based on pulse shape discrimination |
| CN113176603A (en) * | 2021-03-09 | 2021-07-27 | 中国工程物理研究院材料研究所 | Device for continuously measuring low-level radioactive nuclide in liquid effluent |
| CN113466913A (en) * | 2021-05-27 | 2021-10-01 | 中国工程物理研究院材料研究所 | Mixed radiation field dosage measuring system based on liquid scintillator detector |
| CN114035220A (en) * | 2021-11-30 | 2022-02-11 | 成都天核科技有限公司 | A kind of portable energy spectrum type n-γ personal dose equivalent measuring instrument and method thereof |
| CN114384578A (en) * | 2021-11-26 | 2022-04-22 | 西北核技术研究所 | A Simultaneous Screening Method for Interference of Fast Neutron and Silicon Reaction on 3He Sandwich Spectrometer |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102928866A (en) * | 2011-08-09 | 2013-02-13 | 中国辐射防护研究院 | Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector |
| CN104536032A (en) * | 2014-12-23 | 2015-04-22 | 四川大学 | Liquid scintillator detector n/gamma ray screening method based on support vector machine |
| CN104573337A (en) * | 2014-12-24 | 2015-04-29 | 西北核技术研究所 | Initial-spectrum-independent method for determining neutron energy spectrum in reactor steady-state neutron field |
| WO2016144403A9 (en) * | 2014-12-15 | 2016-11-10 | The Regents Of The University Of Michigan | Scintillator-based neutron and gamma-ray dosimeter |
-
2017
- 2017-05-16 CN CN201710344835.2A patent/CN107422359A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102928866A (en) * | 2011-08-09 | 2013-02-13 | 中国辐射防护研究院 | Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector |
| WO2016144403A9 (en) * | 2014-12-15 | 2016-11-10 | The Regents Of The University Of Michigan | Scintillator-based neutron and gamma-ray dosimeter |
| CN104536032A (en) * | 2014-12-23 | 2015-04-22 | 四川大学 | Liquid scintillator detector n/gamma ray screening method based on support vector machine |
| CN104573337A (en) * | 2014-12-24 | 2015-04-29 | 西北核技术研究所 | Initial-spectrum-independent method for determining neutron energy spectrum in reactor steady-state neutron field |
Non-Patent Citations (1)
| Title |
|---|
| 陈法国: "G (E)函数在高能γ射线剂量测量中的应用", 《核电子学与探测技术》 * |
Cited By (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108051847B (en) * | 2017-12-05 | 2019-10-29 | 清华大学 | Utilize the method and neutron dose rate instrument of lanthanum bromide detector measurement neutron dose rate |
| CN108051847A (en) * | 2017-12-05 | 2018-05-18 | 清华大学 | Utilize the method for lanthanum bromide detector measurement neutron dose rate and neutron dose rate instrument |
| CN108490477A (en) * | 2018-03-14 | 2018-09-04 | 中国人民解放军火箭军工程大学 | A kind of n- γ pulses discriminating methods and system based on improvement centroid algorithm |
| CN108627867A (en) * | 2018-03-14 | 2018-10-09 | 中国人民解放军火箭军工程大学 | A kind of real-time discrimination systems of digitlization n- γ |
| CN110057843A (en) * | 2019-04-16 | 2019-07-26 | 中国辐射防护研究院 | Radioactive source shipping container gamma shielding method for testing performance and system based on G (E) function |
| CN110361773B (en) * | 2019-06-05 | 2023-09-15 | 中国辐射防护研究院 | Method for positioning neutron source position of neutron radiation field of unknown energy spectrum |
| CN110361773A (en) * | 2019-06-05 | 2019-10-22 | 中国辐射防护研究院 | A method of positioning unknown power spectrum Neutron Radiation Field neutron source position |
| CN111221030A (en) * | 2019-12-03 | 2020-06-02 | 北京卫星环境工程研究所 | Neutron-gamma detector based on physical integration and neutron-gamma online screening method |
| CN110806599A (en) * | 2019-12-12 | 2020-02-18 | 中国工程物理研究院激光聚变研究中心 | Pulse gating type neutron detector and detection method thereof |
| CN112034177A (en) * | 2020-07-09 | 2020-12-04 | 中国工程物理研究院材料研究所 | Use of NPY as molecular marker for diagnosis of long-term low-dose ionizing radiation exposure |
| CN112034177B (en) * | 2020-07-09 | 2022-09-02 | 中国工程物理研究院材料研究所 | Use of NPY as molecular marker for diagnosis of long-term low-dose ionizing radiation exposure |
| CN112882082A (en) * | 2021-01-12 | 2021-06-01 | 中国人民解放军海军工程大学 | Neutron-gamma ambient dose equivalent rate instrument based on pulse shape discrimination |
| CN113176603A (en) * | 2021-03-09 | 2021-07-27 | 中国工程物理研究院材料研究所 | Device for continuously measuring low-level radioactive nuclide in liquid effluent |
| CN113176603B (en) * | 2021-03-09 | 2022-05-17 | 中国工程物理研究院材料研究所 | Device for continuously measuring low-level radioactive nuclide in liquid effluent |
| CN113466913A (en) * | 2021-05-27 | 2021-10-01 | 中国工程物理研究院材料研究所 | Mixed radiation field dosage measuring system based on liquid scintillator detector |
| CN114384578A (en) * | 2021-11-26 | 2022-04-22 | 西北核技术研究所 | A Simultaneous Screening Method for Interference of Fast Neutron and Silicon Reaction on 3He Sandwich Spectrometer |
| CN114035220A (en) * | 2021-11-30 | 2022-02-11 | 成都天核科技有限公司 | A kind of portable energy spectrum type n-γ personal dose equivalent measuring instrument and method thereof |
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Application publication date: 20171201 |