CN106324659A - Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof - Google Patents
Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof Download PDFInfo
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- CN106324659A CN106324659A CN201510388436.7A CN201510388436A CN106324659A CN 106324659 A CN106324659 A CN 106324659A CN 201510388436 A CN201510388436 A CN 201510388436A CN 106324659 A CN106324659 A CN 106324659A
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Abstract
The invention belongs to the radiation measurement field and relates to a neutron-sensitive substance boron-doped plastic scintillator and a thermal neutron measurement method thereof. According to the neutron-sensitive substance boron-doped plastic scintillator and the thermal neutron measurement method thereof of the invention, a plastic scintillator is doped with a boron-containing raw material; the boron-doped plastic scintillator is connected with a photomultiplier tube, and the boron-doped plastic scintillator and the photomultiplier tube are sealed in an opaque shell, so that a probe can be formed; the probe is arranged in a measurement environment; incoming neutrons and the boron-containing raw material in the plastic scintillator are subjected to a nuclear reaction, so that the material is in an excited state; after the material is de-excited, photons are released; the number of the photons is proportional to the number of the incoming neutrons; the quantity of the electric pulse signals of the photomultiplier tube in unit time is recorded, so that the fluence of the neutrons can be obtained, and therefore, the measurement of the fluence of the neutrons can be realized; and the fluence of the neutrons is multiplied by a fluence-dose conversion coefficient, so that the equivalence of the dose of the neutrons can be obtained. The neutron-sensitive substance boron-doped plastic scintillator of the invention has the advantages of low cost, wide application range and high detection efficiency.
Description
Technical field
The invention belongs to actinometry field, the plastics being specifically related to a kind of neutron-sensitive material boron that adulterates dodge
Bright body and the method measuring thermal neutron thereof.
Background technology
Plastic scintillant is typically done substrate by polystyrene, is blended into other organic additive and makees scitillating material, then
Making plus Wavelength shifter, it has, and detection efficient is high, photoyield is high, and signal pulse width is narrow, machinability
Can good, adaptive capacity to environment is strong, stable mechanical performance, the advantage such as with low cost and be widely used in radiation and survey
In amount work, but owing to the main component of plastic scintillant is C, H, O, they cut with neutron interaction
Face is relatively low, typically cannot be directly used to the monitoring field of neutron, to this end, the period of the day from 11 p.m. to 1 a.m also needs doping or embedding in Tan Ce
Enter other materials and export to increase optical signal, just can be used for soon as embedded one layer of ZnS:Ag film at plastic scintillant
Neutron measurement.
Owing to ZnS:Ag film is light tight, the method therefore embedding ZnS:Ag film in plastic scintillant can be lost
A lot of photons, causes detection efficient and sensitivity to decline.
Summary of the invention
Present invention aims to problems of the prior art, it is provided that one can be used for thermal neutron
The plastic scintillant of the doping neutron-sensitive material boron measured, and use this boron-doping Plastic scintillation bulk measurement
The method of thermal neutron.
Technical scheme is as follows: the plastic scintillant of a kind of neutron-sensitive material boron that adulterates, by polyphenyl
Substrate made by ethylene, is blended into scitillating material and Wavelength shifter, wherein, mixes and contain in described polystyrene substrate
The raw material of boron, the incorporation of the raw material containing boron accounts for the 5%-10% of plastic scintillant gross mass.
Further, the plastic scintillant of the neutron-sensitive material boron that adulterates as above, wherein, described contains
Organoboron compound chosen by the raw material having boron, during preparing plastic scintillant by organoboron compound by
Corresponding proportion mixes in polystyrene substrate and is sufficiently mixed.
Boron-doping plastics are dodged by the method for the Plastic scintillation bulk measurement thermal neutron of above-mentioned doping neutron-sensitive material boron
Bright body is connected with photomultiplier tube, and is sealed in opaque shell, forms probe；Probe is placed in
Measure in environment, incident neutron and the raw material generation nuclear reaction containing boron in plastic scintillant, nuclear reaction
Whole energy losses in boron-doping plastic scintillant, are made material be in excited state, de excitation by the alpha-particle released
Time release photon, photon numbers be proportional to alpha-particle loss energy, i.e. the quantity of nuclear reaction, also with regard to direct ratio
In incident neutron number, the record photomultiplier tube electric impulse signal amount in the unit interval can calculate neutron
Fluence, thus realize the measurement of neutron fluence, it is multiplied by fluence-dose conversion coefficient and can get neutron DE.
Beneficial effects of the present invention is as follows: neutron sensitive material boron is mixed in plastic scintillant by the present invention,
Neutron can effectively be measured by the material of boracic.The side of this employing boron-doping Plastic scintillation bulk measurement thermal neutron
Method is cheap, applied range, and its detection efficient is far above embedding ZnS:Ag film in plastic scintillant
Method.
Accompanying drawing explanation
Fig. 1 is boron-doping plastic scintillant structure and nuclear reaction schematic diagram；
Fig. 2 is the schematic diagram of plastic scintillator detector.
Detailed description of the invention
With embodiment, the present invention is described in detail below in conjunction with the accompanying drawings.
The key component of scintillator detector has scintillator, collection optical system, the phototube of detection light
Part (such as photomultiplier tube), and give the potentiometer of each electrode power supply of photomultiplier tube, they are closed in one
In individual opaque shell, being referred to as probe, this belongs to the known features of this area.Wherein plastic scintillant
Primary structure is typically done substrate by polystyrene, is blended into other organic additive and makees scitillating material, adds shifting
Ripple agent is made, and these materials are not had an effect with thermal neutron containing C, H, O, and the most general plastics dodge
Bright body cannot be directly used to measure thermal neutron.
Neutron can will embed a certain proportion of neutron-sensitive with a lot of material generation nuclear reactions in plastic scintillant
After material, incident neutron reacts, and reaction can pass to plastic scintillant material makes it excite, during de excitation
Releasing photon, photon is transferred to photomultiplier tube through Wavelength shifter, by follow-up electricity after being converted into the signal of telecommunication and amplifying
Road record.Photon numbers is directly proportional to the energy of absorbed, and the reaction of nuclear reaction can be certain, number of photons
Amount is the most just proportional to number of neutrons.
As it is shown in figure 1,10N+ is there is in B with neutron10B=α+7The nuclear reaction of Li+2.792Mev,10B and neutron
Reaction cross-section is higher, and the cross section of thermal neutron is 3840 targets, therefore contains10During the material of B can effectively be measured
Son, method is while preparing former plastic scintillant, adds the microgranule of boracic.The present invention is at Plastic scintillation
Mixing the raw material containing boron in the polystyrene substrate of body, the incorporation of the raw material containing boron accounts for plastic scintillant
The 5%-10% of gross mass.The described raw material containing boron can choose organoboron compound, such as trialkylborane,
Hydroxyl borine etc., is mixed the raw material containing boron in polystyrene substrate by corresponding proportion and is sufficiently mixed.
As in figure 2 it is shown, boron-doping plastic scintillant 1 is connected with photoconduction 2, the most again with photomultiplier tube
Connecting, and be sealed in opaque shell, form probe, in figure, K is photocathode, and F is for focusing on
Pole, D1～D10For dynode, A is anode.Probe is placed in measurement environment, incident neutron and plastics
The raw material generation nuclear reaction containing boron in scintillator, due to the extremely short range of alpha-particle, nuclear reaction is released
Alpha-particle can make material be in excited state by whole energy losses in plastic scintillant, will necessarily during de excitation
Releasing photon, photon numbers is proportional to the energy of alpha-particle loss, and i.e. the quantity of nuclear reaction, is the most just proportional to
Incident neutron number, thus realize the measurement of neutron fluence, it is multiplied by fluence-dose conversion coefficient and can get neutron agent
The Radiation Protection Quantities such as amount equivalent.
Embodiment
Boron-doping plastic scintillant is made substrate by the polystyrene mixing the raw material containing boron, be blended into scitillating material and
Wavelength shifter forms, and concrete preparation method is to make substrate with the polystyrene of the trialkylborane containing corresponding proportion
Add the first solute and three ditolyls and the second solute PoPo post polymerization are made boron-doping plastic scintillant block, then
Cleaved molding obtains boron-doping plastic scintillant.
As it is shown in figure 1, incide the reaction occurred in boron-doping plastic scintillant by neutron；By boron-doping plastics
Scintillator and collection optical system, the photoelectric device (such as photomultiplier tube) of detection light, and give photomultiplier transit
The potentiometer managing each electrode power supply is enclosed in an opaque shell, forms probe, internal structure of popping one's head in
As shown in Figure 2.Being placed in by probe in measurement environment, incident neutron occurs with the boron in boron-doping plastic scintillant
Reaction, nuclear reaction release alpha-particle by whole energy losses in boron-doping plastic scintillant, extreme portions energy
Passing to the first solute makes it excite three ditolyls, launches the fluorescence of wavelength 350-400nm during its de excitation,
Second solute PoPo absorbs the light that this fluorescence emission wavelengths is longer, and main peak position wavelength is at 423nm, and photon is through light
Lead and be transferred to photomultiplier tube, amplified by signal amplification circuit and record after being converted into electric impulse signal, and this
The quantity of individual electric pulse is proportional to the neutron number of times with boron generation nuclear reaction, is the most just proportional to incident neutron
Quantity, the electric impulse signal amount of record unit time can calculate the fluence of neutron, it is achieved neutron fluence
Measure.The number of pulses that one neutron ultimately forms and the ratio of boron-doping, photomultiplier tube model and photoelectricity times
Increase pipe duty relevant, determine and photomultiplier tube circuit in boron-doping ratio-dependent, photomultiplier tube model
In the case of having designed, can simulate by the method for Monte Carlo and calculate and come by the method for experimental verification
Arrive.
Obviously, those skilled in the art can carry out various change and modification without deviating from this to the present invention
Bright spirit and scope.So, if the present invention these amendment and modification belong to the claims in the present invention and
Within the scope of its equivalent technology, then the present invention is also intended to comprise these change and modification.
Claims (3)
1. a plastic scintillant for neutron-sensitive of adulterating material boron, is made substrate by polystyrene, is blended into flicker
Material and Wavelength shifter, it is characterised in that: in described polystyrene substrate, mix the raw material containing boron, contain
The incorporation of the raw material of boron accounts for the 5%-10% of plastic scintillant gross mass.
2. the plastic scintillant of the neutron-sensitive material boron that adulterates as claimed in claim 1, it is characterised in that:
Organoboron compound chosen by the described raw material containing boron, by organic boron during preparing plastic scintillant
Compound is mixed in polystyrene substrate by corresponding proportion and is sufficiently mixed.
3. the Plastic scintillation bulk measurement using the neutron-sensitive material boron that adulterates described in claim 1 or 2 is hankered
The method of son, it is characterised in that: boron-doping plastic scintillant is connected with photomultiplier tube, and is sealed in not
In transparent shell, form probe；Probe is placed in measurement environment, incident neutron and plastic scintillant
In the raw material generation nuclear reaction containing boron, nuclear reaction release alpha-particle whole energy losses are moulded in boron-doping
In material scintillator, making material be in excited state, release photon during de excitation, photon numbers is proportional to alpha-particle and damages
The energy lost, i.e. the quantity of nuclear reaction, the most just it is proportional to incident neutron number, record photomultiplier tube is in unit
The electric impulse signal amount of time can calculate the fluence of neutron, thus realizes the measurement of neutron fluence, is multiplied by
Fluence-dose conversion coefficient can get neutron DE.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201510388436.7A CN106324659A (en) | 2015-06-30 | 2015-06-30 | Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof |
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| CN201510388436.7A CN106324659A (en) | 2015-06-30 | 2015-06-30 | Neutron-sensitive substance boron-doped plastic scintillator and thermal neutron measurement method thereof |
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Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109613599A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A kind of method of boron-doped glass measurement neutron |
| CN109613604A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing mercury glass measurement neutron |
| CN109613601A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A kind of method of Au-doped glass measurement neutron |
| CN109613602A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A kind of method of indium-doped glass measurement neutron |
| CN109613598A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing silver-colored glass measurement neutron |
| CN109613600A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing gallium glass measurement neutron |
| CN109613603A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing rubidium glass measurement neutron |
| CN113970780A (en) * | 2020-07-23 | 2022-01-25 | 固安县朝阳生物科技有限公司 | Novel plastic scintillator for nuclear detection |
| CN114942469A (en) * | 2022-05-23 | 2022-08-26 | 西北核技术研究所 | Neutron detection method and device based on flexible gallium nitride two-dimensional electron gas |
| CN114994742A (en) * | 2022-06-14 | 2022-09-02 | 西北核技术研究所 | Thermal neutron or fast neutron detection method and device based on MOF |
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Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109613599A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A kind of method of boron-doped glass measurement neutron |
| CN109613604A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing mercury glass measurement neutron |
| CN109613601A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A kind of method of Au-doped glass measurement neutron |
| CN109613602A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A kind of method of indium-doped glass measurement neutron |
| CN109613598A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing silver-colored glass measurement neutron |
| CN109613600A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing gallium glass measurement neutron |
| CN109613603A (en) * | 2018-12-25 | 2019-04-12 | 中国辐射防护研究院 | A method of mixing rubidium glass measurement neutron |
| 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 |
| CN109613600B (en) * | 2018-12-25 | 2024-02-23 | 中国辐射防护研究院 | Method for measuring neutrons by gallium-doped glass |
| CN113970780A (en) * | 2020-07-23 | 2022-01-25 | 固安县朝阳生物科技有限公司 | Novel plastic scintillator for nuclear detection |
| CN114942469A (en) * | 2022-05-23 | 2022-08-26 | 西北核技术研究所 | Neutron detection method and device based on flexible gallium nitride two-dimensional electron gas |
| CN114994742A (en) * | 2022-06-14 | 2022-09-02 | 西北核技术研究所 | Thermal neutron or fast neutron detection method and device based on MOF |
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