[go: up one dir, main page]

CN106324657B - The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron - Google Patents

The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron Download PDF

Info

Publication number
CN106324657B
CN106324657B CN201510387295.7A CN201510387295A CN106324657B CN 106324657 B CN106324657 B CN 106324657B CN 201510387295 A CN201510387295 A CN 201510387295A CN 106324657 B CN106324657 B CN 106324657B
Authority
CN
China
Prior art keywords
neutron
lithium
plastic scintillant
fluence
raw material
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.)
Active
Application number
CN201510387295.7A
Other languages
Chinese (zh)
Other versions
CN106324657A (en
Inventor
刘建忠
宋嘉涛
杨明明
王勇
任俊
李建伟
于潜
赵迎喜
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 for Radiation Protection
Original Assignee
China Institute for Radiation Protection
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 for Radiation Protection filed Critical China Institute for Radiation Protection
Priority to CN201510387295.7A priority Critical patent/CN106324657B/en
Publication of CN106324657A publication Critical patent/CN106324657A/en
Application granted granted Critical
Publication of CN106324657B publication Critical patent/CN106324657B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Landscapes

  • Measurement Of Radiation (AREA)

Abstract

The invention belongs to actinometry fields, and in particular to a method of the plastic scintillant and its measurement thermal neutron of doping neutron-sensitive substance lithium.The present invention mixes the raw material containing lithium in plastic scintillant, will mix lithium plastic scintillant and connect with photomultiplier tube, and is sealed in opaque shell, forms probe;Probe is placed in measurement environment, nuclear reaction occurs for the raw material containing lithium in incident neutron and plastic scintillant, material is set to be in excitation state, photon is released when de excitation, photon numbers are proportional to incident neutron number, the fluence of neutron can be calculated by recording electric impulse signal amount of the photomultiplier tube in the unit time, to realize the measurement of neutron fluence, neutron DE can be obtained multiplied by fluence-dose conversion coefficient.The present invention is cheap, has a wide range of application, and detection efficient is high.

Description

The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron
Technical field
The invention belongs to actinometry fields, and in particular to it is a kind of adulterate neutron-sensitive substance lithium plastic scintillant and its The method for measuring thermal neutron.
Background technique
Plastic scintillant generally does matrix by polystyrene, is blended into other organic additives and makees scitillating material, along with shifting Wave agent is made, it has, and detection efficient is high, photoyield is high, and signal pulse width is narrow, and processability is good, adaptive capacity to environment By force, stable mechanical performance, it is low in cost the advantages that and be widely used in actinometry work, but due to the master of plastic scintillant Wanting ingredient is C, H, O, they are lower with the section of neutron interaction, generally cannot be directly used to the monitoring field of neutron, is This, the period of the day from 11 p.m. to 1 a.m needs to adulterate or be embedded in other materials also to increase optical signal output in detection, is such as embedded in one layer in plastic scintillant ZnS:Ag film just can be used for fast neutron measurement.
Since ZnS:Ag film is opaque, the method that ZnS:Ag film is embedded in plastic scintillant can lose many light Son causes detection efficient and sensitivity to decline.
Summary of the invention
It is an object of the invention to aiming at the problems existing in the prior art, provide it is a kind of can be used for thermal neutron measurement mix The plastic scintillant of miscellaneous neutron-sensitive substance lithium, and use this method for mixing lithium Plastic scintillation bulk measurement thermal neutron.
Technical scheme is as follows: a kind of plastic scintillant adulterating neutron-sensitive substance lithium is made by polystyrene Matrix is blended into scitillating material and Wavelength shifter, wherein mixes the raw material containing lithium in the polystyrene substrate, contains lithium The incorporation of raw material accounts for the 7%-12% of plastic scintillant gross mass.
Further, the plastic scintillant of neutron-sensitive substance lithium is adulterated as described above, wherein the original containing lithium Material includes lithia, the salt containing lithium, during preparing plastic scintillant, the raw material containing lithium is poly- by corresponding proportion incorporation It is sufficiently mixed in styrene matrix.
The method of the Plastic scintillation bulk measurement thermal neutron of above-mentioned doping neutron-sensitive substance lithium, will mix lithium plastic scintillant with Photomultiplier tube connection, and be sealed in opaque shell, form probe;Probe is placed in measurement environment, incident neutron Nuclear reaction occurs with the raw material containing lithium in plastic scintillant, whole energy losses are being mixed lithium by the α particle that nuclear reaction is released In plastic scintillant, material is made to be in excitation state, when de excitation releases photon, and photon numbers are proportional to the energy of α particle loss, i.e., The quantity of nuclear reaction is also just proportional to incident neutron number, electric impulse signal amount of the record photomultiplier tube in the unit time The fluence of neutron is calculated, to realize the measurement of neutron fluence, neutron dose can be obtained multiplied by fluence-dose conversion coefficient and work as Amount.
Beneficial effects of the present invention are as follows: the present invention mixes neutron sensitive material lithium in plastic scintillant, the material containing lithium Material can effectively measure neutron.It is this cheap using the method for mixing lithium Plastic scintillation bulk measurement thermal neutron, application range Extensively, detection efficient is much higher than the method for being embedded in ZnS:Ag film in plastic scintillant.
Detailed description of the invention
Fig. 1 is to mix lithium plastic scintillant structure and nuclear reaction schematic diagram;
Fig. 2 is the schematic diagram of plastic scintillator detector.
Specific embodiment
The present invention is described in detail below with reference to the accompanying drawings and embodiments.
The chief component of scintillator detector has scintillator, collection optical system, photoelectric device (such as light for detecting light Electric multiplier tube), and to the divider that each electrode of photomultiplier tube is powered, they are closed in an opaque shell, It is referred to as probe, this belongs to the known features of this field.Wherein the primary structure of plastic scintillant generally does matrix by polystyrene, It is blended into other organic additives and makees scitillating material, along with Wavelength shifter is made, these materials are not sent out substantially containing C, H, O and thermal neutron Raw effect, therefore general plastic scintillant cannot be directly used to measurement thermal neutron.
With many substances nuclear reaction can occur for neutron, and a certain proportion of neutron sensitive material will be embedded in plastic scintillant Afterwards, incident neutron reacts with it, and reaction, which can pass to plastic scintillant material, makes its excitation, and when de excitation releases photon, photon warp Wavelength shifter is transferred to photomultiplier tube, is converted into electric signal and is recorded after amplifying by subsequent conditioning circuit.Photon numbers and material absorb Energy it is directly proportional, and the reaction of nuclear reaction can be certain, and photon numbers are also just proportional to number of neutrons.
As shown in Figure 1,6N+ occurs for Li and neutron6Li=α+3The nuclear reaction of H+4.8Mev,6The reaction cross-section of Li and neutron Higher and thermal neutron section is 910 targets, therefore is contained6The material of Li can effectively measure neutron, and method is to prepare former plastics While scintillator, the particle containing lithium is added.The present invention mixes the original containing lithium in the polystyrene substrate of plastic scintillant Material, the incorporation of the raw material containing lithium account for the 7%-12% of plastic scintillant gross mass.The raw material containing lithium can be chosen Lithia, the salt containing lithium, such as lithium chloride etc., by the raw material containing lithium by sufficiently mixed in corresponding proportion incorporation polystyrene substrate It closes.
It connect, is then connect again with photomultiplier tube, and sealed with light guide 2 as shown in Fig. 2, lithium plastic scintillant 1 will be mixed It in opaque shell, is formed and is popped one's head in, in figure, K is photocathode, and F is focusing electrode, D1~D10For dynode, A is anode.It will Probe is placed in measurement environment, and nuclear reaction occurs for the raw material containing lithium in incident neutron and plastic scintillant, due to α particle Extremely short range, the α particle that nuclear reaction is released can make material be in excitation state, move back by whole energy losses in plastic scintillant Photon will necessarily be released when sharp, photon numbers are proportional to the energy of α particle loss, the i.e. quantity of nuclear reaction, be also just proportional into Subnumber is hit, to realize the measurement of neutron fluence, the radiation such as neutron DE can be obtained multiplied by fluence-dose conversion coefficient Protection amount.
Embodiment
It mixes lithium plastic scintillant and matrix is made by the polystyrene for mixing the raw material containing lithium, be blended into scitillating material and Wavelength shifter It forms, specific preparation method is to make matrix with the polystyrene of the lithia containing corresponding proportion the first solute is added to three first Polymerization, which is made, after benzene and the second solute PoPo mixes lithium plastic scintillant block, then mixes lithium plastic scintillant through excision forming acquisition.
As shown in Figure 1, being incident on the reaction mixed and occurred in lithium plastic scintillant by neutron;To mix lithium plastic scintillant with Collection optical system, the photoelectric device (such as photomultiplier tube) for detecting light, and to the partial pressure that each electrode of photomultiplier tube is powered Device is enclosed in an opaque shell, forms probe, and probe internal structure is as shown in Figure 2.Probe is placed in measurement environment In, incident neutron reacts with the lithium mixed in lithium plastic scintillant, and reaction, which can pass to the first solute, makes it to three ditolyls Excitation, the fluorescence of launch wavelength 350-400nm, the second solute PoPo absorb the fluorescence emission wavelengths longer light when de excitation, Main peak position wavelength is transferred to photomultiplier tube through light guide in 423nm, photon, is converted into after electric impulse signal by signal amplification circuit Amplify and record, and the quantity of this electric pulse is proportional to the number that nuclear reaction occurs for neutron and lithium, be also just proportional into Number of neutrons is penetrated, the electric impulse signal amount of record unit time can calculate the fluence of neutron, realize the measurement of neutron fluence. One finally formed number of pulses of neutron has with the ratio, photomultiplier tube model and photomultiplier tube working condition for mixing lithium It closes, it, can be special with covering in the case where mixing determining lithium ratio-dependent, photomultiplier tube model and the completion of photomultiplier tube circuit design The method simulation of Caro is calculated and is obtained by the method for experimental verification.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art Mind and range.In this way, if these modifications and changes of the present invention belongs to the range of the claims in the present invention and its equivalent technology Within, then the present invention is also intended to include these modifications and variations.

Claims (1)

1. a kind of method for the Plastic scintillation bulk measurement thermal neutron for adulterating neutron-sensitive substance lithium, the plastic scintillant is by gathering Styrene makees matrix, is blended into scitillating material and Wavelength shifter, and the raw material containing lithium is mixed in the polystyrene substrate, contains lithium The incorporation of raw material account for the 7%-12% of plastic scintillant gross mass, it is characterised in that: lithium plastic scintillant and photoelectricity will be mixed Multiplier tube connection, and be sealed in opaque shell, form probe;Probe is placed in measurement environment, incident neutron and modeling Expect that nuclear reaction occurs for the raw material containing lithium in scintillator, whole energy losses are being mixed lithium plastics by the α particle that nuclear reaction is released In scintillator, material is made to be in excitation state, when de excitation releases photon, and photon numbers are proportional to the energy of α particle loss, i.e. core is anti- The quantity answered also just is proportional to incident neutron number, and recording electric impulse signal amount of the photomultiplier tube in the unit time can calculate Neutron DE can be obtained multiplied by fluence-dose conversion coefficient to realize the measurement of neutron fluence in the fluence of neutron out.
CN201510387295.7A 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron Active CN106324657B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201510387295.7A CN106324657B (en) 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201510387295.7A CN106324657B (en) 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron

Publications (2)

Publication Number Publication Date
CN106324657A CN106324657A (en) 2017-01-11
CN106324657B true CN106324657B (en) 2019-04-23

Family

ID=57728174

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201510387295.7A Active CN106324657B (en) 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron

Country Status (1)

Country Link
CN (1) CN106324657B (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108535769B (en) * 2017-03-03 2022-06-07 中国辐射防护研究院 Probe for testing and calibrating optical fiber neutron detection system and testing and calibrating method thereof
CN109143317B (en) * 2017-06-16 2023-05-16 中国辐射防护研究院 Neutron detection method and equipment for reducing gamma ray interference by using CsI scintillator
CN109143316B (en) * 2017-06-16 2023-09-15 中国辐射防护研究院 Neutron detection method and equipment for reducing gamma-ray interference by utilizing NaI (TI) scintillator
CN108152851B (en) * 2017-11-27 2020-11-20 中核控制系统工程有限公司 Fast and slow neutron composite detector
CN109613603B (en) * 2018-12-25 2023-10-20 中国辐射防护研究院 Method for measuring neutrons by using rubidium-doped glass
CN114721030B (en) * 2022-05-05 2023-04-18 四川大学 Preparation method of wave-shifting optical fiber

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN86108715A (en) * 1985-12-23 1987-08-26 施卢默格海外有限公司 Logging method and devices such as gamma-ray spectroscopy
CN1137239A (en) * 1993-10-12 1996-12-04 比奥特雷斯公司 Improved quantitation of gamma and X-ray emitting isotopes
CN1952689A (en) * 2005-10-19 2007-04-25 原子高科股份有限公司 scintillation activity meter
CN101128731A (en) * 2004-10-05 2008-02-20 澳联邦科学与工业研究组织 radiographic equipment
US7372041B1 (en) * 2007-01-17 2008-05-13 Radiation Monitoring Devices, Inc. Neutron detectors and related methods
WO2011087861A3 (en) * 2009-12-22 2012-05-31 Rapiscan Systems, Inc. Composite gamma-neutron detection system

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7141799B1 (en) * 2005-03-30 2006-11-28 Ut-Battelle, Llc Fiber optic thermal/fast neutron and gamma ray scintillation detector
KR101538194B1 (en) * 2008-03-24 2015-07-20 가부시끼가이샤 도꾸야마 Scintillator for neutron detection and neutron detector
US20120112074A1 (en) * 2010-11-08 2012-05-10 General Electric Company Neutron scintillator composite material and method of making same
CN103713311A (en) * 2012-09-28 2014-04-09 圣戈本陶瓷及塑料股份有限公司 Neutron detection device comprising gadolinium yttrium gallium aluminum garnet and use method thereof

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN86108715A (en) * 1985-12-23 1987-08-26 施卢默格海外有限公司 Logging method and devices such as gamma-ray spectroscopy
CN1137239A (en) * 1993-10-12 1996-12-04 比奥特雷斯公司 Improved quantitation of gamma and X-ray emitting isotopes
CN101128731A (en) * 2004-10-05 2008-02-20 澳联邦科学与工业研究组织 radiographic equipment
CN1952689A (en) * 2005-10-19 2007-04-25 原子高科股份有限公司 scintillation activity meter
US7372041B1 (en) * 2007-01-17 2008-05-13 Radiation Monitoring Devices, Inc. Neutron detectors and related methods
WO2011087861A3 (en) * 2009-12-22 2012-05-31 Rapiscan Systems, Inc. Composite gamma-neutron detection system

Also Published As

Publication number Publication date
CN106324657A (en) 2017-01-11

Similar Documents

Publication Publication Date Title
CN106324657B (en) The method adulterated the plastic scintillant of neutron-sensitive substance lithium and its measure thermal neutron
CN106324659A (en) Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof
US9182508B2 (en) Neutron detector using neutron absorbing scintillating particulates in plastic
CN106324655B (en) The method adulterated the plastic scintillant of neutron-sensitive substance uranium and its measure thermal neutron
US9244178B2 (en) Method for determining the irradiation dose deposited in a scintillator by ionising radiation and associated device
US9939538B2 (en) Accurate light-weight broad-energy neutron remmeter and use thereof
CN104464856A (en) Real-time monitoring device for neutron flux in fission reaction
CN106324658B (en) The method adulterated the plastic scintillant of neutron-sensitive substance cadmium and its measure thermal neutron
RU2189057C2 (en) Scintillation detector of neutron and gamma radiation
US5352040A (en) Dual neutron flux/temperature measurement sensor
Wilhelm et al. Development and operation of a 6LiF: ZnS (Ag)—scintillating plastic capture-gated detector
RU2143711C1 (en) Detector for registration of ionizing radiation
CN106324656B (en) The method adulterated the plastic scintillant of neutron-sensitive substance plutonium and its measure thermal neutron
Nakamura et al. Development of a ZnS/10B2O3 scintillator with low-afterglow phosphor
CN108535769B (en) Probe for testing and calibrating optical fiber neutron detection system and testing and calibrating method thereof
Fallot The detection of reactor antineutrinos for reactor core monitoring: an overview
Taggart et al. Optimizing the sensitivity of a GAGG: Ce-based thermal neutron detector
RU152877U1 (en) COMBINED NEUTRON FLOW SPECTROMETER MONITOR
CN204044030U (en) The heat insulation calibrating installation of β rays method flue gas monitoring instrument
Barton et al. A novel neutron multiplicity detector using lithium fluoride and zinc sulphide scintillator
Miller et al. Effects of detector cell size on dose rate measurements using organic scintillators
CN109613603B (en) Method for measuring neutrons by using rubidium-doped glass
Watanabe et al. Neutron-Induced Fission Cross Section of Pu 241 Below 11 eV
Kiff et al. Integrated readout of organic scintillator and ZnS: Ag/6 LiF for segmented antineutrino detectors
Pozzi et al. Detectors in active interrogation

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
GR01 Patent grant
GR01 Patent grant