CN106324655B - The method adulterated the plastic scintillant of neutron-sensitive substance uranium and its measure thermal neutron - Google Patents
The method adulterated the plastic scintillant of neutron-sensitive substance uranium and its measure thermal neutron Download PDFInfo
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- CN106324655B CN106324655B CN201510386656.6A CN201510386656A CN106324655B CN 106324655 B CN106324655 B CN 106324655B CN 201510386656 A CN201510386656 A CN 201510386656A CN 106324655 B CN106324655 B CN 106324655B
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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 uranium.The present invention mixes the raw material containing uranium in plastic scintillant, will mix uranium 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 uranium 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
Technical field
The invention belongs to actinometry fields, and in particular to it is a kind of adulterate neutron-sensitive substance uranium 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 uranium, and use this method for mixing uranium Plastic scintillation bulk measurement thermal neutron.
Technical scheme is as follows: a kind of plastic scintillant adulterating neutron-sensitive substance uranium is made by polystyrene
Matrix is blended into scitillating material and Wavelength shifter, wherein mixes the raw material containing uranium in the polystyrene substrate, contains uranium
The incorporation of raw material accounts for the 5%-10% of plastic scintillant gross mass.
Further, the plastic scintillant of neutron-sensitive substance uranium is adulterated as described above, wherein the original containing uranium
Material includes triuranium octoxide, uanate, and during preparing plastic scintillant, the raw material containing uranium 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 uranium, will mix uranium 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 uranium in plastic scintillant, whole energy losses are being mixed uranium 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 uranium in plastic scintillant, the material of uranium-bearing
Material can effectively measure neutron.It is this cheap using the method for mixing uranium 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 uranium 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 1,235U fissions under the bombardment of neutron, releases the energy of about 170Mev, mainly distributes to two
A fission fragment131I and137Cs, therefore contain235The material of U can effectively measure neutron, and method is to prepare former plastic scintillant
While, the particle of uranium-bearing is added.The present invention mixes the raw material containing uranium in the polystyrene substrate of plastic scintillant, contains
The incorporation of the raw material of uranium accounts for the 5%-10% of plastic scintillant gross mass.The raw material containing uranium can choose eight oxidations three
Raw material containing uranium is mixed in polystyrene substrate by corresponding proportion and is sufficiently mixed by uranium, uanate etc..
It connect, is then connect again with photomultiplier tube, and sealed with light guide 2 as shown in Fig. 2, uranium 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 uranium in incident neutron and plastic scintillant, and uranium 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 uranium plastic scintillant and matrix is made by the polystyrene for mixing the raw material containing uranium, be blended into scitillating material and Wavelength shifter
It forms, specific preparation method is to make matrix with the polystyrene of the triuranium octoxide containing corresponding proportion the first solute is added to three
Polymerization, which is made, after ditolyl and the second solute PoPo mixes uranium plastic scintillant block, then mixes uranium Plastic scintillation through excision forming acquisition
Body.
As shown in Figure 1, being incident on the reaction mixed and occurred in uranium plastic scintillant by neutron；To mix uranium 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 uranium mixed in uranium 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 uranium, 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 uranium
It closes, it, can be special with covering in the case where mixing determining uranium 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 uranium, plastic scintillant is by polystyrene
Make matrix, is blended into scitillating material and Wavelength shifter, it is characterised in that: the raw material containing uranium is mixed in the polystyrene substrate,
The incorporation of raw material containing uranium accounts for the 5%-10% of plastic scintillant gross mass, will mix uranium plastic scintillant and photomultiplier tube
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 uranium in body, and whole energy losses are being mixed uranium plastic scintillant by the α particle that nuclear reaction is released
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.
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| CN201510386656.6A CN106324655B (en) | 2015-06-30 | 2015-06-30 | The method adulterated the plastic scintillant of neutron-sensitive substance uranium and its measure thermal neutron |
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| CN201510386656.6A CN106324655B (en) | 2015-06-30 | 2015-06-30 | The method adulterated the plastic scintillant of neutron-sensitive substance uranium and its measure thermal neutron |
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| CN106324655B true CN106324655B (en) | 2019-11-22 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN108384532B (en) * | 2018-03-28 | 2020-05-22 | 苏州大学 | Use of uranium-containing compounds as scintillators |
| US11072740B2 (en) | 2018-03-28 | 2021-07-27 | Soochow University | Use of uranium-containing compound as scintillator |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| US7105832B2 (en) * | 2004-04-07 | 2006-09-12 | Ut-Battelle, Llc | Composite solid-state scintillators for neutron detection |
| US7372041B1 (en) * | 2007-01-17 | 2008-05-13 | Radiation Monitoring Devices, Inc. | Neutron detectors and related methods |
| US7999236B2 (en) * | 2007-02-09 | 2011-08-16 | Mropho Detection, Inc. | Dual modality detection system of nuclear materials concealed in containers |
| WO2012135140A2 (en) * | 2011-03-25 | 2012-10-04 | Nanoptics, Incorporated | Materials, method, and apparatus for detecting neutrons and ionizing radiation |
| CN103163550A (en) * | 2011-12-12 | 2013-06-19 | 中国辐射防护研究院 | Optical fiber coupled radiation detector used for fast neutron measurement |
| CN103163551A (en) * | 2011-12-12 | 2013-06-19 | 中国辐射防护研究院 | Optical fiber coupled radiation detector used for slow neutron measurement |
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