CN86204889U - High-energy r ray source device for calibration - Google Patents

High-energy r ray source device for calibration Download PDF

Info

Publication number
CN86204889U
CN86204889U CN 86204889 CN86204889U CN86204889U CN 86204889 U CN86204889 U CN 86204889U CN 86204889 CN86204889 CN 86204889 CN 86204889 U CN86204889 U CN 86204889U CN 86204889 U CN86204889 U CN 86204889U
Authority
CN
China
Prior art keywords
energy
rays
neutron
gamma
source device
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.)
Ceased
Application number
CN 86204889
Other languages
Chinese (zh)
Inventor
叶宗垣
李景文
跃钢
施德棠
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Institute of Atomic of Energy
Original Assignee
China Institute of Atomic of Energy
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by China Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN 86204889 priority Critical patent/CN86204889U/en
Publication of CN86204889U publication Critical patent/CN86204889U/en
Ceased legal-status Critical Current

Links

Images

Abstract

The utility model relates to a high energy r-rays calibration source device which utilizes radioactive neutron sources of Am-Be to generate a thermal neutron capture reaction on radiation samples of iron, nickle and magnesium dioxide through moderation to obtain monocolor r-rays with the energy of 5-10Mev. The monocolor r-rays are used for scaling energy linearity, energy resolution and relative efficiency of the r-rays detectors of Ge (Li), HPGe, NaI (Tl), etc.

Description

High-energy r ray source device for calibration
The utility model belongs to a kind of easy HIGH ENERGY GAMMA RAY SOURCE device that is used for the scale gamma ray detector.
Usually the energy of the monoenergetic gamma ray radiator of scale gamma ray detector all below 3MeV, the performance of the detector under the scale high-energy condition, and just need utilize the gamma ray projector that the method for nuclear reaction obtains being suitable on accelerator or reactor.But getable monochromatic energy of is very limited on accelerator; On reactor with thermal capture can produce various energy gamma-rays referring to " the energy height is to 11MeV reactor high strength apportion gamma ray projector " (The Nuclear Reactor as A High Intensity Source For Dis-crete Gamma Rays up to 11MeV) of Ya Lieseke (Jarizyk) etc., Nucl.Instr.and Meth.13(1961) 287 and " the monochromatic gamma ray projector device of high strength " " atomic nuclear physics " 6(1984 of Li Jingwen etc.) 15.But, bring very big difficulty to use, and seem very inconvenient because of depending on reactor because background is big on every side.
The utility model purpose is to disclose the monochromatic gamma ray projector device that a kind of easy radioactivity neutron source of using Am-Be and so on produces 5~10MeV energy range.
Utilizing Am-Be neutron source to produce gamma-ray ultimate principle is by neutron and nuclear (its energy is between 5~10MeV for n, γ) the monochromatic gamma-rays of reaction emission characteristic.Am-Be neutron source is by (the gamma-ray probability of emission high-energy is very little for a, the n) gamma-rays of the main emission in reaction back 4.43MeV. 241The gamma-ray energy of Am emission itself is all below 1MeV, so the gamma-rays of Am-Be neutron source emission itself does not influence the gamma-ray use more than the 5MeV.By (n, a) reaction also can obtain monochromatic gamma-rays, but intensity is little.Because the capture cross-section of thermal neutron is far longer than the neutron of other energy, if the neutron of Am-Be neutron source emission is passed through the paraffin slowing down, make thermal capture become main effect, select suitable radiator then, the monochromatic gamma-rays that then can obtain being suitable for.
Accompanying drawing 1 is a high-energy gamma ray calibration source device synoptic diagram.As seen from the figure, neutron source [ 3 ] places the center of device, selects the less neutron source of gamma-rays background for use, as Am-Be neutron source or Pu-Be neutron source.Neutron source [ 3 ] is radiator [ 4 ] on every side, radiator sample such as iron, nickel or magnesium dichloride, and they are captured thermal neutron and produce the feature gamma-rays.It between neutron source and the radiator slowing down layer [ 1 ].Radiator [ 4 ] go up to be placed paraffin or tygon as reflection horizon [ 2 ] with the top all around, is used for the reverberation neutron, and can reduce the background that neutron scattering causes.Being sidelong and putting a bismuth plate, with the low-yield gamma-rays of filtering as filtrator [ 5 ] near one of detector.[ 6 ] are gamma ray detector among the figure.
Embodiment 1: neutron source [ 3 ] is Am-Be neutron source, and source strength is 10 5N/s, slowing down layer [ 1 ] are the thick paraffin of 1cm, and radiator [ 4 ] is the thick iron of 2cm, and reflection horizon [ 2 ] are the thick paraffin of 5cm, and filtrator [ 5 ] is the thick bismuth plate of 1cm.
For testing gamma-ray performance, use φ 45 * 45mm 3Coaxial Ge (Li) detector, it is right 60The gamma-ray energy resolution of the 1332keV of Co is 3.7keV.The wide 10keV of being about in the road of the multichannel analyzer that uses in the measurement uses 1173,1332(to resulting gamma-ray energy 60Co), 1461(is natural 40K) and 4430(Am-Be source itself) the γ source of keV carries out energy and broaches, and makes accurate energy value by nuclear energy level again.For reducing piling up of low-energy, at Ge(Li) outer mask of probe is the lead of 5mm and " cap " that the thick iron of 3mm is formed with thick, add the about 5mm of a bed thickness by boron carbide and epoxy resin mix and the solidifying body conduct that forms to the protection body of neutron.
Fig. 2 is the gamma ray spectrum that record obtained after 5 hours, and figure the right is three spectral lines of 7640keV, P among the figure, and S, D represent full energy peak respectively, escape peak and double escape peak.The left side of Fig. 2 is three rays of the 4.43MeV of Am-Be source emission itself, and their half width is about 80keV, and big like this width estimates to be mainly derived from the recoil effect of carbon nuclear emission neutron, and this gamma-ray intensity is about gamma-ray 20 times of 7640keV.Meanwhile, at the energy lower part, also have one to capture that neutron forms deuteron and the monoenergetic gamma rays of the 2223keV that launches by proton, this sees fully aware ofly in measurement, and its energy resolution is less than multiple channels wide (10keV).
With the known NaI(T1 of detection efficiency) total intensity of scintillation detector guestimate 7631 and these two rays of 7645KeV is 5 * 10 2Photons/second.
Embodiment 2: implementation condition is substantially the same manner as Example 1, and unique difference is to change the iron radiator into 8mm thick nickel plate.Fig. 3 measures the high energy part that obtained composing shape in 2 hours, and nickel is captured the gamma-rays that thermal neutron produces intensity maximum (8998keV) in the gamma-rays later on.It accounts for 40% of energetic gamma rays sum.Learn that according to interrelated data [ Nucl.Data 3A(1967) 367 ] number of whenever capturing 100 these rays of neutron is 26.7640keV is the background that causes of iron-bearing materials on every side among the figure.
Embodiment 3:Am-Be source neutron bombardment chlorine produces gamma-rays.Chlorine is captured the gamma-rays of thermal neutron emission, in the measurement of nuclear reaction gamma spectroscopy, is used as the standard of energy and intensity, and its gamma-ray energy is accurately measured, and measuring error is 0.2keV.
Use MgCl 2Crystalline powder is as radiator, and 1 kilogram of total amount is dressed up 6 small plastic bags and is trapped among around the Am-Be neutron source that is surrounded by the thick paraffin of 2cm MgCl 2The outside still is added with the thick paraffin layer of 5cm, in the one side by detector the thick bismuth filtrator of 1cm is arranged.Fig. 4 is the high energy part that writes down the gamma spectrum figure that obtained in 3 hours.As seen from the figure, in the gamma-rays that thermal neutron capture reaction produced of chlorine, intensity all shows greater than the energetic gamma rays of 2.75 γ/100n.They are respectively 8575.65keV(2.79), 7790.40keV(8.43), 7414.01keV(10.2), 6627.95keV(4.43), 6619.76keV(7.92), 6111.00keV(19.8), 5715.40keV(5.35), the gamma-rays number that 100 neutrons produce is whenever captured in numeric representation in the bracket.Magnesium is captured the gamma-rays that neutron produces, and its main energy is 3.92MeV.
In sum, utilizing neutron intensity is 10 5Samples such as the Am-Be of n/s or Pu-Be neutron source irradiation iron, nickel, magnesium dichloride obtain intensity 8998keV, 7638keV and 6111keV high-energy gamma ray that be suitable for, that monochromaticity is good, can be used as gamma ray detector such as Ge(Li), HPGe and NaI(T1) the scale of linearity, energy resolution and relative efficiency.Such cover scale source apparatus not only have the advantage that energy of monochromaticity is good, intensity is suitable for, energy is high, and device is simple, easy to use, does not rely on reactor.The utility model has also been opened up a kind of new purposes for radioactivity neutron source.

Claims (6)

1, a kind of high-energy gamma ray calibration source device, form by neutron source, slowing down layer, radiator, it is characterized in that utilizing radioactivity neutron source, is that thermal neutron and radiator cause that thermal capture produces monochromatic feature gamma-rays, is used for the scale gamma ray detector through slowing down layer slowing down.
2, high-energy gamma ray calibration source device according to claim 1 is characterized in that being equipped with reflection horizon and filtrator.
3, high-energy gamma ray calibration source device according to claim 1 and 2 is characterized in that radioactivity neutron source wherein is Am-Be neutron source or Pu-Be neutron source.
4, high-energy gamma ray calibration source device according to claim 1 and 2 is characterized in that moderation of neutrons material wherein is paraffin or tygon.
5, height energy gamma calibration source apparatus according to claim 1 and 2 is characterized in that radiative capture material wherein is iron, nickel or magnesium dichloride.
6, high-energy gamma ray calibration source device according to claim 1 and 2 is characterized in that reflection horizon wherein is paraffin or tygon, and filtrator is the bismuth plate.
CN 86204889 1986-07-04 1986-07-04 High-energy r ray source device for calibration Ceased CN86204889U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN 86204889 CN86204889U (en) 1986-07-04 1986-07-04 High-energy r ray source device for calibration

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN 86204889 CN86204889U (en) 1986-07-04 1986-07-04 High-energy r ray source device for calibration

Publications (1)

Publication Number Publication Date
CN86204889U true CN86204889U (en) 1987-06-24

Family

ID=4807838

Family Applications (1)

Application Number Title Priority Date Filing Date
CN 86204889 Ceased CN86204889U (en) 1986-07-04 1986-07-04 High-energy r ray source device for calibration

Country Status (1)

Country Link
CN (1) CN86204889U (en)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102590252A (en) * 2012-02-27 2012-07-18 长春工业大学 Device for rapidly detecting iron content of iron ore by utilizing D-D neutron generator
CN103069500A (en) * 2010-03-10 2013-04-24 南非核能有限公司 Method of producing radionuclides
CN103605149A (en) * 2013-11-26 2014-02-26 西北核技术研究所 Device and method for detection efficiency calibration of xenon sample HPGe
CN104597481A (en) * 2014-12-26 2015-05-06 北京放射性核素实验室 Gas sample calibration standard source and preparation method thereof
CN105353400A (en) * 2015-11-13 2016-02-24 中国计量科学研究院 Inlaying source device used for scintillation crystal detector gain automatic control
CN109269538A (en) * 2018-10-16 2019-01-25 中国海洋石油集团有限公司 One kind is with brill neutron He3 pipe scale test device

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103069500A (en) * 2010-03-10 2013-04-24 南非核能有限公司 Method of producing radionuclides
CN103069500B (en) * 2010-03-10 2016-10-12 南非核能有限公司 The method producing radionuclide
CN102590252A (en) * 2012-02-27 2012-07-18 长春工业大学 Device for rapidly detecting iron content of iron ore by utilizing D-D neutron generator
CN103605149A (en) * 2013-11-26 2014-02-26 西北核技术研究所 Device and method for detection efficiency calibration of xenon sample HPGe
CN103605149B (en) * 2013-11-26 2015-11-25 西北核技术研究所 A kind of device and method of scale xenon sample HPGe detection efficiency
CN104597481A (en) * 2014-12-26 2015-05-06 北京放射性核素实验室 Gas sample calibration standard source and preparation method thereof
CN105353400A (en) * 2015-11-13 2016-02-24 中国计量科学研究院 Inlaying source device used for scintillation crystal detector gain automatic control
CN109269538A (en) * 2018-10-16 2019-01-25 中国海洋石油集团有限公司 One kind is with brill neutron He3 pipe scale test device

Similar Documents

Publication Publication Date Title
Mendoza et al. Measurement and analysis of the Am 241 neutron capture cross section at the n_TOF facility at CERN
Shizuma et al. Residual 152Eu and 60Co activities induced by neutrons from the Hiroshima atomic bomb
Binney et al. A review of the delayed fission neutron technique
Tarim et al. Source-to-detector distance dependence of efficiency and energy resolution of a 3" x3" NaI (Tl) detector
CN86204889U (en) High-energy r ray source device for calibration
Sonay et al. Neutron background measurements with a hybrid neutron detector at the Kuo-Sheng Reactor Neutrino Laboratory
Çetin Determination of natural radioactivity concentrations in surface soils in the Yeşilırmak River in Amasya, Turkey
Kansal et al. Evaluation and analysis of 226Ra, 232Th and 40K and radon exhalation rate in the soil samples for health risk assessment
Cesareo et al. Nuclear resonant scattering of gamma rays in Ni, Cd, Sn and Bi
Poston et al. Calculation of the HPRR neutron spectrum for simulated nuclear accident conditions
Lau et al. Absolute determination of uranium concentration by hyperpure germanium LEPS
Prestwich et al. A determination of the carbon thermal neutron capture cross section
Mohammadi et al. Thermoluminescence dosimetry of fast neutrons using silver activated lithium borate phosphors
Wang et al. Comparisons between calculated and measured gamma-ray energy-deposition rates in a one-dimensional mixed fast-neutron/gamma-ray field
Mustapha et al. Jordan Journal of Physics
Hassan et al. Measuring the amount of environmental pollution resulting from nuclear radiation in selected samples of rice consumed in Najaf governorate
Koehler et al. Decay of 141Nd (II)
Eom et al. Feasibility Study of Fast Neutron Activation Analysis of Iron with LaBr3: Ce Scintillation Detector
Oliver PIN diode and neutron spectrum measurements at the Army Pulse Radiation Facility
Moriuchi et al. Construction of Response Functions for Various Cylindrical and Spherical NaI (T1) Scintillation Detectors for Gamma Rays and the Test Results
Suleiman et al. Evaluation of naturally occurring radionuclide in soil samples from Ajiwei Mining Sites in Niger State, Nigeria
Xayheungsy et al. Natural radioactivity in the soil of Thoulakhom district in Vientiane province, Laos
Hahn et al. Internal Conversion Coefficients in the Decay of Au 199
Oprea et al. Measurement of the 241Am (n, γ) cross section at the n_TOF facility at CERN
Karmakar et al. Thickness Dependent Sensitivity of GAGG: Ce Scintillation detectors for Thermal Neutrons: GEANT4 Simulations and Experimental Measurements

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C14 Grant of patent or utility model
GR01 Patent grant
C17 Cessation of patent right
CE01 Termination of patent right