CN105467507A - Uranium doped fiber and neutron measurement method thereof - Google Patents
Uranium doped fiber and neutron measurement method thereof Download PDFInfo
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- CN105467507A CN105467507A CN201410458492.9A CN201410458492A CN105467507A CN 105467507 A CN105467507 A CN 105467507A CN 201410458492 A CN201410458492 A CN 201410458492A CN 105467507 A CN105467507 A CN 105467507A
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Abstract
The invention belongs to the field of radiation measurement, and particularly relates to a uranium doped fiber and a neutron measurement method thereof. The uranium doped fiber is arranged in a measurement environment. The uranium doped fiber is connected with a photomultiplier which is connected with a signal amplification circuit. Incident neutrons react with uranium-235 in the fiber. Reaction energy is transmitted to fiber material to excite the fiber material. Photons are emitted in deexcitation. The photons are transmitted to the photomultiplier through the fiber and converted into electric signals and then the electric signals are amplified by a signal amplification circuit and recorded. Measurement of neutron fluence is realized according to the principle that the number of the photons is in direct proportion to the number of the neutrons.
Description
Technical field
The invention belongs to actinometry field, be specifically related to a kind of method of mixing uranium optical fiber and measuring neutron.
Background technology
Light transmitting fiber is called for short optical fiber, and to conduct, distance, signal attenuation are little, message capacity is widely used in the communications industry greatly.Optical fiber can not only light conducting signal, under specific condition, also can launch photon, have that structure is simple, volume is little simultaneously, lightweight, lay convenient, with low cost advantage, the therefore attention of also extremely actinometry industry.
Along with the continuous popularization of Application of Nuclear Technology, the place of neutron monitoring is needed to get more and more, when needing the regional compare of monitoring unevenness that is large or radiation field more serious, during as used traditional neutron probe formula area monitoring technology, then need the probe quantity of laying more, will the cost of whole system be made very high, use neutron optical fiber technology to complete same work and then want much cheap, meanwhile, middle sub-optical fibre can also measure the neutron irradiation in narrow region.
The primary structure of optical fiber generally can be divided into fibre core, covering, coat, jacket layer, what wherein play the effect of transmission photon is sandwich layer, its constituent material has quartz, fluoride glass, chalcogenide glass, polymethylmethacrylate (PMMA), polystyrene (PSt), fluorine-containing transparent resin or deuterate PMMA etc., the reaction cross-section of these materials and neutron is all smaller, and therefore general optical fiber can not be directly used in measurement neutron.
Summary of the invention
The object of the invention is to for problems of the prior art, provide a kind of can be used for neutron measurement mix uranium optical fiber, and use the method for this optical fiber measurement neutron.
Technical scheme of the present invention is as follows: one mixes uranium optical fiber, comprises fibre core, covering, coat, jacket layer, and wherein, mix the raw material containing uranium-235 in the material of described fibre core, the incorporation of the raw material containing uranium-235 accounts for the 10%-15% of fibre core gross mass.
Further, mix uranium optical fiber as above, wherein, the described raw material containing uranium-235 can choose uranium dioxide or hex, mixes in core material, fully mix the raw material containing uranium-235 under molten condition by corresponding proportion.
Above-mentioned method of mixing uranium optical fiber measurement neutron, uranium optical fiber will be mixed and be placed in measurement environment, mix uranium optical fiber to be connected with photomultiplier, photomultiplier connection signal amplifying circuit and pulse recording circuit, uranium-235 in incident neutron and optical fiber reacts, reaction can pass to fiber optic materials makes it excite, photon is released during de excitation, photon through Optical Fiber Transmission to photomultiplier, to be amplified by signal amplification circuit after converting electric impulse signal to and by pulse recording circuit record, the quantity of electric pulse is proportional to the number of times that nuclear reaction occurs for neutron and uranium-235, also incident neutron quantity is just proportional to, the electric impulse signal amount of record unit time can calculate the fluence of neutron, realize the measurement of neutron fluence.
Beneficial effect of the present invention is as follows: neutron sensitive material uranium mixes in the core material of optical fiber by the present invention, and the material of uranium-bearing effectively can measure neutron.The method of this employing optical fiber measurement neutron is cheap, and applied range can measure the neutron irradiation of narrow zone easily.
Accompanying drawing explanation
Fig. 1 is the principle schematic of mixing uranium optical fiber measurement neutron.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail.
Neutron can with a lot of material generation nuclear reaction, after mixing a certain proportion of neutron sensitive material in optical fiber, incident neutron and its reaction, reaction can pass to fiber optic materials makes it excite, photon is released during de excitation, photon through Optical Fiber Transmission to photomultiplier, convert to electric signal and amplify after by subsequent conditioning circuit record.The energy that photon numbers absorbs to material is directly proportional, and the reaction of nuclear reaction can be certain, and photon numbers is also just proportional to number of neutrons.
235u fissions under the bombardment of neutron, release the energy of about 170Mev, mainly distribute to two fission fragments, the material therefore containing uranium effectively can measure neutron, method mixes a certain proportion of uranium material, and concrete mixed ratio can be determined by experiment.Material containing uranium can choose any one of uranium dioxide or hex, or also can consider the composite material selecting two kinds.
The present invention mixes in the fibre core of optical fiber
235u, utilizes the material containing uranium effectively can measure neutron.The fission fragment that above-mentioned fission reaction generates can by energy loss in fiber optic materials, core material is made to be in excited state, photon will inevitably be released during de excitation, photon numbers is proportional to the energy of loss, the i.e. quantity of fission reaction, also incident neutron number is just proportional to, thus the measurement of the neutron fluence realized, be multiplied by fluence-dose conversion coefficient and can obtain the Radiation Protection Quantities such as neutron DE.
The number of pulses that neutron is finally formed with mix the ratio of uranium, photomultiplier model is relevant with photomultiplier duty, when mixing uranium ratio-dependent, photomultiplier model is when determining to complete with photomultiplier circuit design, can with the method analog computation of Monte Carlo and the method verified by experiment obtain.
Uranium is mixed in core material, weakening of core light transmissibility will inevitably be caused, but the object of the invention is neutron measurement, general application scenario can not be greater than the length of tens of meters, less demanding to the light transmissibility of optical fiber, as long as therefore the ratio of uranium is controlled just can meet request for utilization in the reasonable scope.
The incorporation of the raw material containing uranium-235 accounts for the 10%-15% of fibre core gross mass, and this concentration range both can ensure that in optical fiber measurement, the period of the day from 11 p.m. to 1 a.m had good detection efficiency, and optical fiber also can be made to also have certain light conductive performance.First mixed the optical fiber of uranium ratio by small-scale production difference, as in core material
235uO
2content is 10%, 11% ..., 15%, through experiment choose the highest boron-doping ratio of detection efficiency as the optimal proportion produced from now on.
Embodiment
Mix uranium optical fiber and comprise fibre core, covering, coat, jacket layer, concrete preparation method is will
235uO
2raw material (the mainly SiO producing preform is incorporated into by corresponding proportion
2) in, be heated to molten condition, fully make preform after mixing, the production technologies such as follow-up polishing, wire drawing, coating are identical with the production technology of general optical fiber with flow process.
As shown in Figure 1, above-mentioned method of mixing uranium optical fiber measurement neutron, uranium optical fiber will be mixed and be placed in measurement environment, mix uranium optical fiber to be connected with photomultiplier, photomultiplier connection signal amplifying circuit and pulse recording circuit, uranium-235 in incident neutron and optical fiber reacts, reaction can pass to fiber optic materials makes it excite, photon is released during de excitation, photon through Optical Fiber Transmission to photomultiplier, amplified and record by signal amplification circuit after converting electric impulse signal to, and the quantity of this electric pulse is proportional to neutron and the number of times of nuclear reaction occurs uranium-235, also incident neutron quantity is just proportional to, the electric impulse signal amount of record unit time can calculate the fluence of neutron, realize the measurement of neutron fluence.The number of pulses that neutron is finally formed with mix the ratio of uranium, photomultiplier model is relevant with photomultiplier duty, when mixing uranium ratio-dependent, photomultiplier model is when determining to complete with photomultiplier circuit design, can with the method analog computation of Monte Carlo and the method verified by experiment obtain.
Obviously, those skilled in the art can carry out various change and modification to the present invention and not depart from the spirit and scope of the present invention.Like this, if these amendments of the present invention and modification belong within the scope of the claims in the present invention and equivalent technology thereof, then the present invention is also intended to comprise these change and modification.
Claims (3)
1. mix a uranium optical fiber, comprise fibre core, covering, coat, jacket layer, it is characterized in that: in the material of described fibre core, mix the raw material containing uranium-235, the incorporation of the raw material containing uranium-235 accounts for the 10%-15% of fibre core gross mass.
2. mix uranium optical fiber as claimed in claim 1, it is characterized in that: the described raw material containing uranium-235 can choose uranium dioxide or hex, mixes in core material, fully mix the raw material containing uranium-235 under molten condition by corresponding proportion.
3. adopt the method for mixing uranium optical fiber measurement neutron described in claim 1 or 2, it is characterized in that: uranium optical fiber will be mixed and be placed in measurement environment, mix uranium optical fiber to be connected with photomultiplier, photomultiplier connection signal amplifying circuit and pulse recording circuit, uranium-235 in incident neutron and optical fiber reacts, reaction can pass to fiber optic materials makes it excite, photon is released during de excitation, photon through Optical Fiber Transmission to photomultiplier, to be amplified by signal amplification circuit after converting electric impulse signal to and by pulse recording circuit record, the quantity of electric pulse is proportional to the number of times that nuclear reaction occurs for neutron and uranium-235, also incident neutron quantity is just proportional to, the electric impulse signal amount of record unit time can calculate the fluence of neutron, realize the measurement of neutron fluence.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410458492.9A CN105467507A (en) | 2014-09-10 | 2014-09-10 | Uranium doped fiber and neutron measurement method thereof |
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|---|---|---|---|
| CN201410458492.9A CN105467507A (en) | 2014-09-10 | 2014-09-10 | Uranium doped fiber and neutron measurement method thereof |
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Citations (4)
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| US7105832B2 (en) * | 2004-04-07 | 2006-09-12 | Ut-Battelle, Llc | Composite solid-state scintillators for neutron detection |
| US20100111487A1 (en) * | 2008-10-31 | 2010-05-06 | Bruce Gardiner Aitken | Phosphate Glasses Suitable for Neutron Detection and Fibers Utilizing Such Glasses |
| US7791046B2 (en) * | 2008-05-20 | 2010-09-07 | The Charles Stark Draper Laboratory, Inc. | High efficiency fiber-optic scintillator radiation detector |
| CN103748482A (en) * | 2011-06-30 | 2014-04-23 | 圣戈本陶瓷及塑料股份有限公司 | Optical fiber having scintillation quencher, radiation sensor and radiation detection apparatus including the optical fiber and method of making and using the same |
-
2014
- 2014-09-10 CN CN201410458492.9A patent/CN105467507A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7105832B2 (en) * | 2004-04-07 | 2006-09-12 | Ut-Battelle, Llc | Composite solid-state scintillators for neutron detection |
| US7791046B2 (en) * | 2008-05-20 | 2010-09-07 | The Charles Stark Draper Laboratory, Inc. | High efficiency fiber-optic scintillator radiation detector |
| US20100111487A1 (en) * | 2008-10-31 | 2010-05-06 | Bruce Gardiner Aitken | Phosphate Glasses Suitable for Neutron Detection and Fibers Utilizing Such Glasses |
| CN103748482A (en) * | 2011-06-30 | 2014-04-23 | 圣戈本陶瓷及塑料股份有限公司 | Optical fiber having scintillation quencher, radiation sensor and radiation detection apparatus including the optical fiber and method of making and using the same |
Non-Patent Citations (7)
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|---|
| 《中国医学百科全书》编辑委员会: "《中国医学百科全书 8 毒理学》", 31 August 1982 * |
| MICHAEL F. L"ANNUNZIATA: "《放射性分析手册》", 30 December 2006 * |
| 丁大钊等: "《中子物理学：原理、方法与应用 上 第2版》", 30 September 2005 * |
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| 国务院: "《中华人民共和国核材料管理条例》", 15 June 1987 * |
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Application publication date: 20160406 |