Nothing Special   »   [go: up one dir, main page]

CN106324656B - The method adulterated the plastic scintillant of neutron-sensitive substance plutonium and its measure thermal neutron - Google Patents

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

Info

Publication number
CN106324656B
CN106324656B CN201510386745.0A CN201510386745A CN106324656B CN 106324656 B CN106324656 B CN 106324656B CN 201510386745 A CN201510386745 A CN 201510386745A CN 106324656 B CN106324656 B CN 106324656B
Authority
CN
China
Prior art keywords
neutron
plutonium
plastic scintillant
plastic
fluence
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
CN201510386745.0A
Other languages
Chinese (zh)
Other versions
CN106324656A (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 CN201510386745.0A priority Critical patent/CN106324656B/en
Publication of CN106324656A publication Critical patent/CN106324656A/en
Application granted granted Critical
Publication of CN106324656B publication Critical patent/CN106324656B/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 plutonium.The present invention mixes the raw material containing plutonium in plastic scintillant, will mix plutonium 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 plutonium 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 plutonium 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 plutonium 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 plutonium, and use this method for mixing plutonium Plastic scintillation bulk measurement thermal neutron.
Technical scheme is as follows: a kind of plastic scintillant adulterating neutron-sensitive substance plutonium is made by polystyrene Matrix is blended into scitillating material and Wavelength shifter, wherein mixes the raw material containing plutonium in the polystyrene substrate, contains plutonium The incorporation of raw material accounts for the 5%-10% of plastic scintillant gross mass.
Further, the plastic scintillant of neutron-sensitive substance plutonium is adulterated as described above, wherein the original containing plutonium Material includes plutonium dioxide, tri-chlorination plutonium, and during preparing plastic scintillant, the raw material containing plutonium is mixed by corresponding proportion It is sufficiently mixed in polystyrene substrate.
The method of the Plastic scintillation bulk measurement thermal neutron of above-mentioned doping neutron-sensitive substance plutonium, will mix plutonium 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 plutonium in plastic scintillant, nuclear reaction releases energy total loss and mixing plutonium plastic scintillant In, so that material is in excitation state, when de excitation releases photon, and photon numbers are proportional to the energy of α particle loss, the i.e. number of nuclear reaction Amount is also just proportional to incident neutron number, and neutron can be calculated by recording electric impulse signal amount of the photomultiplier tube in the unit time Fluence neutron DE can be obtained multiplied by fluence-dose conversion coefficient to realize the measurement of neutron fluence.
Beneficial effects of the present invention are as follows: the present invention mixes neutron sensitive material plutonium in plastic scintillant, the material containing plutonium Material can effectively measure neutron.It is this cheap using the method for mixing plutonium 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 plutonium 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 1,239Pu fissions under the bombardment of neutron, releases the energy of about 170Mev, mainly distributes to Two fission fragments A and B, therefore the material containing plutonium can effectively measure neutron, method is to prepare the same of former plastic scintillant When, the particle containing plutonium is added.The present invention mixes the raw material containing plutonium in the polystyrene substrate of plastic scintillant, contains plutonium The incorporation of raw material accounts for the 5%-10% of plastic scintillant gross mass.The raw material containing plutonium can choose plutonium dioxide, three Raw material containing plutonium is mixed in polystyrene substrate by corresponding proportion and is sufficiently mixed by plutonium chloride etc..
It connect, is then connect again with photomultiplier tube, and sealed with light guide 2 as shown in Fig. 2, plutonium 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 plutonium in incident neutron and plastic scintillant, and plutonium nuclear fission is raw At fission fragment material can be made to be in excitation state by energy loss in plastic scintillant, when de excitation, will necessarily release photon, Photon numbers are proportional to the quantity of fission reaction, the i.e. quantity of nuclear reaction, are also just proportional to incident neutron number, to realize neutron The Radiation Protection Quantities such as neutron DE can be obtained multiplied by fluence-dose conversion coefficient in the measurement of fluence.
Embodiment
It mixes plutonium plastic scintillant and matrix is made by the polystyrene for mixing the raw material containing plutonium, be blended into scitillating material and Wavelength shifter It forms, specific preparation method is to make matrix with the polystyrene of the plutonium dioxide containing corresponding proportion the first solute is added to three Polymerization, which is made, after toluene and the second solute PoPo mixes plutonium plastic scintillant block, then mixes plutonium Plastic scintillation through excision forming acquisition Body.
As shown in Figure 1, being incident on the reaction mixed and occurred in plutonium plastic scintillant by neutron;To mix plutonium 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 plutonium mixed in plutonium 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 plutonium, 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 plutonium It closes, it, can be special with covering in the case where mixing determining plutonium 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 plutonium, plastic scintillant is by polystyrene Make matrix, be blended into scitillating material and Wavelength shifter, the raw material containing plutonium, the raw material containing plutonium are mixed in the polystyrene substrate Incorporation account for the 5%-10% of plastic scintillant gross mass, it is characterised in that: plutonium plastic scintillant and photomultiplier tube will be mixed Connection, and be sealed in opaque shell, form probe;Probe is placed in measurement environment, incident neutron and Plastic scintillation Nuclear reaction occurs for the raw material containing plutonium in body, and nuclear reaction releases energy total loss in mixing plutonium plastic scintillant, makes material In excitation state, when de excitation, releases photon, and photon numbers are proportional to the energy of α particle loss, the i.e. quantity of nuclear reaction, also just just Than in incident neutron number, the fluence of neutron can be calculated by recording electric impulse signal amount of the photomultiplier tube in the unit time, from And realize the measurement of neutron fluence, neutron DE can be obtained multiplied by fluence-dose conversion coefficient.
CN201510386745.0A 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance plutonium and its measure thermal neutron Active CN106324656B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201510386745.0A CN106324656B (en) 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance plutonium and its measure thermal neutron

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201510386745.0A CN106324656B (en) 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance plutonium and its measure thermal neutron

Publications (2)

Publication Number Publication Date
CN106324656A CN106324656A (en) 2017-01-11
CN106324656B true CN106324656B (en) 2019-04-23

Family

ID=57728063

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201510386745.0A Active CN106324656B (en) 2015-06-30 2015-06-30 The method adulterated the plastic scintillant of neutron-sensitive substance plutonium and its measure thermal neutron

Country Status (1)

Country Link
CN (1) CN106324656B (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114942468B (en) * 2022-05-23 2024-08-16 西北核技术研究所 Method and device for non-contact rapid detection of special nuclear material

Family Cites Families (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2619622B1 (en) * 1987-08-21 1989-11-17 Commissariat Energie Atomique CHARACTERIZATION DEVICE OF FISSILE MATERIAL COMPRISING AT LEAST ONE DETECTION OF NEUTRONIC RADIATION DETECTOR WITHIN A GAMMA RADIATION DETECTION SCINTILLATOR
RU2189057C2 (en) * 2000-11-13 2002-09-10 Уральский государственный технический университет Scintillation detector of neutron and gamma radiation
US7115872B2 (en) * 2003-12-10 2006-10-03 John William Bordynuik Portable radiation detector and method of detecting radiation
RU2259573C1 (en) * 2004-03-23 2005-08-27 ГОУ ВПО Уральский государственный технический университет-УПИ Scintillation detector for fast and thermal neutrons
US7525101B2 (en) * 2006-05-26 2009-04-28 Thermo Niton Analyzers Llc Neutron and gamma ray monitor
US7372041B1 (en) * 2007-01-17 2008-05-13 Radiation Monitoring Devices, Inc. Neutron detectors and related methods
US7608829B2 (en) * 2007-03-26 2009-10-27 General Electric Company Polymeric composite scintillators and method for making same
WO2009083852A2 (en) * 2007-12-21 2009-07-09 Koninklijke Philips Electronics N.V. Radiation-sensitive detector with a scintillator in a composite resin
CN101329404A (en) * 2008-07-11 2008-12-24 清华大学 Neutron gamma-ray detecting device
CN101661109B (en) * 2009-09-18 2012-10-03 中国科学院等离子体物理研究所 Novel signal-ion micro-beam detector based on plastic scintillating fiber
WO2012135140A2 (en) * 2011-03-25 2012-10-04 Nanoptics, Incorporated Materials, method, and apparatus for detecting neutrons and ionizing radiation
US8878135B2 (en) * 2012-01-26 2014-11-04 General Electric Company Lithium based scintillators for neutron detection
CN203595812U (en) * 2013-11-21 2014-05-14 湖北方圆环保科技有限公司 Plastic scintillator detector

Also Published As

Publication number Publication date
CN106324656A (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
US7582880B2 (en) Neutron detector using lithiated glass-scintillating particle composite
CN106324659A (en) Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof
CN106324655B (en) The method adulterated the plastic scintillant of neutron-sensitive substance uranium and its measure thermal neutron
US20160266263A1 (en) Apparatus and method for radiation detection
CA2528177A1 (en) Neutron and gamma ray monitor
US9939538B2 (en) Accurate light-weight broad-energy neutron remmeter and use thereof
US3566118A (en) An axially aligned gamma ray-neutron detector
CN106324658B (en) The method adulterated the plastic scintillant of neutron-sensitive substance cadmium and its measure thermal neutron
US5352040A (en) Dual neutron flux/temperature measurement sensor
WO2019109813A1 (en) Method for measuring neutron dose rate by means of cerium bromide detector, and neutron dose rate meter
Wilhelm et al. Development and operation of a 6LiF: ZnS (Ag)—scintillating plastic capture-gated detector
McCormack et al. Characterization and operational stability of EJ276 plastic scintillator-based detector for neutron spectroscopy
CN106324656B (en) The method adulterated the plastic scintillant of neutron-sensitive substance plutonium and its measure thermal neutron
CN111736201B (en) Nuclear fuel rod active detection system and method
JP2017161378A (en) Radiation monitor and radiation measuring method
US3728544A (en) Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel
RU2189057C2 (en) Scintillation detector of neutron and gamma radiation
CN108535769B (en) Probe for testing and calibrating optical fiber neutron detection system and testing and calibrating method thereof
RU2663683C1 (en) Method for registration of neutrons and device for its implementation
Fallot The detection of reactor antineutrinos for reactor core monitoring: an overview
JP2015010837A (en) Radiation-ray measurement device
CN204044030U (en) The heat insulation calibrating installation of β rays method flue gas monitoring instrument
JP2012242369A (en) Radiation detector
Miller et al. Effects of detector cell size on dose rate measurements using organic scintillators

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