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CN109613602A - A kind of method of indium-doped glass measurement neutron - Google Patents

A kind of method of indium-doped glass measurement neutron Download PDF

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Publication number
CN109613602A
CN109613602A CN201811590250.XA CN201811590250A CN109613602A CN 109613602 A CN109613602 A CN 109613602A CN 201811590250 A CN201811590250 A CN 201811590250A CN 109613602 A CN109613602 A CN 109613602A
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China
Prior art keywords
indium
glass
neutron
measurement
scintillator
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CN201811590250.XA
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Chinese (zh)
Inventor
刘建忠
杨彪
王勇
李建伟
李德源
杨明明
赵迎喜
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China Institute for Radiation Protection
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China Institute for Radiation Protection
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Priority to CN201811590250.XA priority Critical patent/CN109613602A/en
Publication of CN109613602A publication Critical patent/CN109613602A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00Measuring neutron radiation
    • G01T3/06Measuring neutron radiation with scintillation detectors

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  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Molecular Biology (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Measurement Of Radiation (AREA)

Abstract

The present invention provides a kind of method of indium-doped glass measurement neutron, the glass scintillator for being mixed with the indium of preset ratio is reacted with incident neutron, the energy loss released is reacted in glass material, the atomic nucleus for making glass material is in excitation state, and when de excitation will launch a certain number of photons;By the optical signal through glass delivery to photomultiplier, the electric signal being converted into is recorded;Electric signal is obtained into neutron DE multiplied by fluence-dose conversion coefficient.Method provided by the invention can be based on glass is low in cost, easy to process, volume is changeable, acid and alkali-resistance is corrosion-resistant, after mixing a certain proportion of phosphide material, a kind of excellent neutron-sensitive material can be provided, the cost of neutron measurement can be reduced, there is preferable n, γ distinguishing ability, ability is well adapted to for adverse circumstances such as high temperature and humidity, corrosivity.

Description

A kind of method of indium-doped glass measurement neutron
Technical field
The invention belongs to radiometric technique fields, and in particular to a kind of method of indium-doped glass measurement neutron.
Background technique
The main component of glass is SiO2, it is its maximum feature to visible transparent, while good, optical signal declines with transparency Reduction is widely used in various industries.Glass can not only conduct optical signal, photon can also be emitted under specific condition, while having body The advantages of product is changeable, low in cost, easy processing, therefore also by the attention of actinometry industry.
The material composition neutron (-detecting) phosphor to neutron-sensitive is mixed in glass, nuclear reaction occurs for these substances and neutron, It reacts the energy released and the atomic nucleus for making glass material is in excitation state, when de excitation, will launch a certain number of photons, this A optical signal is recorded after being converted into electric signal through glass delivery to photomultiplier.
Currently, the lithium glass of doping certain amount lithium has been applied in the measurement work of neutron, lithium glass conduct is such as used The portable Dose Equivalent Ratemeter of detecting element.The isotope that Li can be used for actinometry has Li-6 and Li-7, and wherein Li-7 pairs Gamma-rays is sensitive, is simply possible to use in γ measurement application;And Li-6 is not only larger with the reaction cross-section of neutron, while also to gamma-rays very Sensitivity, the period of the day from 11 p.m. to 1 a.m must distinguish the signal of neutron and γ in measurement, but have high energy gamma ingredient and it is γ strong in, because of arteries and veins Degree of leaping high is very nearly the same and becomes abnormal difficult.If using Li-6 and Li-7 simultaneously, two sets of test equipments can be needed simultaneously, it is right In portable apparatus, because the limited change of volume weight is more difficult.
Therefore, it is necessary to invent a kind of method of indium-doped glass measurement neutron to solve the above problems.
Summary of the invention
In view of the deficiencies in the prior art, the object of the present invention is to provide a kind of sides of indium-doped glass measurement neutron Method can reduce the cost of neutron measurement, have preferable n, γ distinguishing ability, for adverse circumstances such as high temperature and humidity, corrosivity Well adapt to ability.
To achieve the above objectives, the technical solution adopted by the present invention is that:
A kind of method of indium-doped glass measurement neutron, will be mixed with the glass scintillator and incident neutron of the indium of preset ratio It reacts, reacts the energy loss of releasing in glass material, the atomic nucleus for making glass material is in excitation state, when de excitation A certain number of photons will be launched;By the optical signal through glass delivery to photomultiplier, the electric signal being converted into is recorded; Electric signal is obtained into neutron DE multiplied by fluence-dose conversion coefficient.
Further, raw material of the incorporation containing indium generates glass scintillator containing indium in glass material, wherein indium accounts for the indium The 5%-10% of glass scintillator gross mass.
Further, indium accounts for the 7% of the indium glass scintillator gross mass.
Further, the raw material containing indium is roquesite or sulphur indium iron ore.
Further, also mixed with cerium (Ce) in the glass scintillator containing indium.
Further, the glass scintillator with a thickness of 1-6mm.
Effect of the invention is that method of the present invention, based on glass, low in cost, easy to process, volume can be big Can it is small, acid and alkali-resistance is corrosion-resistant, after mixing a certain proportion of phosphide material, can provide a kind of excellent neutron-sensitive material, can be with The cost for reducing neutron measurement, has preferable n, γ distinguishing ability, has well for adverse circumstances such as high temperature and humidity, corrosivity Adaptability.
Detailed description of the invention
Fig. 1 is the flow diagram of an embodiment of the method for the invention.
Specific embodiment
To keep the technical problems solved, the adopted technical scheme and the technical effect achieved by the invention clearer, below It will the technical scheme of the embodiment of the invention will be described in further detail in conjunction with attached drawing.Obviously, described embodiment is only It is a part of the embodiment of the present invention, instead of all the embodiments.Based on the embodiments of the present invention, ordinary skill people Member's every other embodiment obtained without making creative work, belongs to the scope of protection of the invention.
The main component of glass is SiO2, the reaction cross-section of Si and O and neutron is all smaller, therefore general glass cannot It is directly used in measurement neutron.(n, γ) capture reaction occurs for chemical element indium (In) and neutron, is truncated into 196b, therefore contain indium Glass scintillation physical efficiency is for measuring neutron.Specifically, be mainly used in high-throughput neutron measurement environment, as reactor core, after Processing cell and accident emergency etc..
Although gamma-rays can also interact with it may also be noted that indium is weight indium category, indium and neutron Reaction energy is up to 6.38 much higher than γ.The reaction of fusion reaction can be higher, and the impulse amplitude that neutron generates is much higher than γ pulse Highly, it can be easy to come with γ signal distinguishing using amplitude discriminator device, therefore indium-doped material can work well In mixed radiation field.
Refering to fig. 1, Fig. 1 is the flow diagram of one embodiment of the method for the invention.
A kind of method of indium-doped glass measurement neutron, comprising the following steps:
Step 101: the glass scintillator and incident neutron for being mixed with the indium of preset ratio react, and react the energy of releasing Amount loss is in excitation state in glass material, by the atomic nucleus for making glass material, and when de excitation will launch a certain number of light Son.
Step 102: by the optical signal through glass delivery to photomultiplier, recording the electric signal being converted into.
Step 103: electric signal is obtained into neutron DE multiplied by fluence-dose conversion coefficient, due to photon numbers with The energy that material absorbs is directly proportional, and the reaction of nuclear reaction can be certain, therefore can be by being proportional to the number of number of neutrons optical signal Measurement neutron.
Specifically, raw material of the incorporation containing indium generates glass scintillator containing indium in glass material.
Indium is mixed in glass material, inevitably results in the decrease of glass light conducting power, but during the purpose of this patent is Son measurement, it is of less demanding to the light conducting power of glass, as long as therefore indium to be accounted for the 5%- of the indium glass scintillator gross mass Requirement is just able to satisfy in 10%.
Preferably, indium accounts for the 7% of the indium glass scintillator gross mass.
The raw material containing indium is mineral containing indium.Specifically, such as roquesite or sulphur indium iron ore, do not limit herein It is fixed.
In a specific embodiment, it will be mixed containing 5% indium with glass material and generate glass scintillator containing indium.Again The glass scintillator containing indium is reacted with incident neutron, above-mentioned reaction can make Si by energy loss in glass material Excitation state is in O material, and when de excitation will necessarily release photon, photon numbers are proportional to the energy of loss, i.e. fission reaction Quantity is also just proportional to incident neutron number, so that the measurement for the neutron fluence realized, can obtain multiplied by fluence-dose conversion coefficient To Radiation Protection Quantities such as neutron DEs.
In another embodiment, it will be mixed containing 7% indium with glass material and generate glass scintillator containing indium.Again by institute It states glass scintillator containing indium to react with incident neutron, above-mentioned reaction can make Si and O material by energy loss in glass material Material is in excitation state, and when de excitation will necessarily release photon, and photon numbers are proportional to the energy of loss, the i.e. quantity of fission reaction, Also it is just proportional to incident neutron number, so that the measurement for the neutron fluence realized, can be obtained neutron multiplied by fluence-dose conversion coefficient The Radiation Protection Quantities such as dose equivalent.When indium accounts for the 7% of the gross mass of glass scintillator containing indium, higher neutron measurement not only can guarantee Efficiency, while there are also higher transparencies, guarantee that photon energy is sent to subsequent light-sensitive device, such as the photocathode of photomultiplier On, it can preferably realize measurement effect.
In another embodiment, it will be mixed containing 10% indium with glass material and generate glass scintillator containing indium.Again will The glass scintillator containing indium reacts with incident neutron, and above-mentioned reaction can make Si and O by energy loss in glass material Material is in excitation state, and when de excitation will necessarily release photon, and photon numbers are proportional to the energy of loss, the i.e. number of fission reaction Amount, is also just proportional to incident neutron number, so that the measurement for the neutron fluence realized, available multiplied by fluence-dose conversion coefficient The Radiation Protection Quantities such as neutron DE.
Indium-doped glass ingredient is mainly SiO2+ In can generally mix micro Ce activation, typical indium-doped glass detector Thickness is generally 1-6mm, and thin then n, γ distinguishing ability of thickness is strong but n low efficiency, and thickness thickness n, γ distinguishing ability is weak but n efficiency Height can select, it is not limited here according to the concrete condition of measurand.Preferably, indium-doped glass detector is with a thickness of 5mm.
It is different from the prior art, a kind of method of indium-doped glass measurement neutron provided by the invention is at low cost based on glass It is honest and clean, easy to process, volume is changeable, acid and alkali-resistance is corrosion-resistant, after mixing a certain proportion of phosphide material, can provide a kind of excellent Neutron-sensitive material, the cost of neutron measurement can be reduced, there is preferable n, γ distinguishing ability, for high temperature and humidity, corrosion The adverse circumstances such as property well adapt to ability.
It will be understood by those skilled in the art that method of the present invention is not limited to reality described in specific embodiment Example is applied, specific descriptions above are intended merely to explain the purpose of the present invention, are not intended to limit the present invention.Those skilled in the art It can derive other implementation manners according to the technical scheme of the present invention, also belong to the scope of the technical innovation of the present invention, it is of the invention Protection scope is defined by the claims and their equivalents.

Claims (6)

1. a kind of method of indium-doped glass measurement neutron, which is characterized in that
The glass scintillator for being mixed with the indium of preset ratio is reacted with incident neutron, reacts the energy loss of releasing in glass In glass material, the atomic nucleus for making glass material is in excitation state, when de excitation will launch a certain number of photons;
By the optical signal through glass delivery to photomultiplier, the electric signal being converted into is recorded;
Electric signal is obtained into neutron DE multiplied by fluence-dose conversion coefficient.
2. a kind of method of indium-doped glass measurement neutron according to claim 1, which is characterized in that
Raw material of the incorporation containing indium generates glass scintillator containing indium in glass material, wherein it is total that indium accounts for the indium glass scintillator The 5%-10% of quality.
3. a kind of method of indium-doped glass measurement neutron according to claim 2, which is characterized in that
Indium accounts for the 7% of the indium glass scintillator gross mass.
4. a kind of method of indium-doped glass measurement neutron according to claim 2, which is characterized in that the raw material containing indium is Roquesite or sulphur indium iron ore.
5. a kind of method of indium-doped glass measurement neutron according to claim 1, which is characterized in that
Also mixed with cerium (Ce) in the glass scintillator containing indium.
6. a kind of method of indium-doped glass measurement neutron according to claim 1, which is characterized in that the glass scintillator With a thickness of 1-6mm.
CN201811590250.XA 2018-12-25 2018-12-25 A kind of method of indium-doped glass measurement neutron Pending CN109613602A (en)

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US5684847A (en) * 1994-11-02 1997-11-04 Framatome Silver-based alloy containing indium and cadmium for the production of neutron-absorber components, and use
US20050258372A1 (en) * 2002-10-29 2005-11-24 Mcgregor Douglas S High-efficiency neutron detectors and methods of making same
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US20100038551A1 (en) * 2008-08-14 2010-02-18 Zane William Bell Neutron absorption detector
CN101945974A (en) * 2008-03-24 2011-01-12 株式会社德山 Scintillator for neutron detection and neutron detector
CN102498417A (en) * 2009-07-27 2012-06-13 前视红外放射有限责任公司 Apparatus and method for neutron detection by capture-gamma calorimetry
CN102498416A (en) * 2009-07-27 2012-06-13 前视红外放射有限责任公司 Apparatus and method for neutron detection with neutron-absorbing calorimetric gamma detectors
CN104898157A (en) * 2014-03-04 2015-09-09 环境保护部核与辐射安全中心 Device and method for measuring neutron dose equivalent
CN106324659A (en) * 2015-06-30 2017-01-11 中国辐射防护研究院 Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof
CN107966727A (en) * 2017-11-27 2018-04-27 中核控制系统工程有限公司 A kind of neutron composite detecting device
JP2018200235A (en) * 2017-05-26 2018-12-20 株式会社八神製作所 Neutron detector and neutron measurement device

Patent Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5684847A (en) * 1994-11-02 1997-11-04 Framatome Silver-based alloy containing indium and cadmium for the production of neutron-absorber components, and use
US20050258372A1 (en) * 2002-10-29 2005-11-24 Mcgregor Douglas S High-efficiency neutron detectors and methods of making same
CN1903763A (en) * 2006-08-09 2007-01-31 中国建筑材料科学研究总院 Glass scintillator for thermal neutron detection and its preparation method
CN101945974A (en) * 2008-03-24 2011-01-12 株式会社德山 Scintillator for neutron detection and neutron detector
US20100038551A1 (en) * 2008-08-14 2010-02-18 Zane William Bell Neutron absorption detector
CN102498417A (en) * 2009-07-27 2012-06-13 前视红外放射有限责任公司 Apparatus and method for neutron detection by capture-gamma calorimetry
CN102498416A (en) * 2009-07-27 2012-06-13 前视红外放射有限责任公司 Apparatus and method for neutron detection with neutron-absorbing calorimetric gamma detectors
CN104898157A (en) * 2014-03-04 2015-09-09 环境保护部核与辐射安全中心 Device and method for measuring neutron dose equivalent
CN106324659A (en) * 2015-06-30 2017-01-11 中国辐射防护研究院 Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof
JP2018200235A (en) * 2017-05-26 2018-12-20 株式会社八神製作所 Neutron detector and neutron measurement device
CN107966727A (en) * 2017-11-27 2018-04-27 中核控制系统工程有限公司 A kind of neutron composite detecting device

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