CN217133392U - Detection device for special nuclear materials - Google Patents
Detection device for special nuclear materials Download PDFInfo
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- CN217133392U CN217133392U CN202220430097.XU CN202220430097U CN217133392U CN 217133392 U CN217133392 U CN 217133392U CN 202220430097 U CN202220430097 U CN 202220430097U CN 217133392 U CN217133392 U CN 217133392U
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Abstract
The embodiment of the application provides a detection device for a special nuclear material, which comprises a neutron source system, a detection system and a calculation analysis system, wherein the neutron source system comprises a neutron source, and the neutron source is used for emitting a neutron beam to irradiate a sample to be detected; the detection system comprises a detector, a detector and a control unit, wherein the detector is arranged at the downstream of the neutron source along the transmission direction of the neutron beam and is used for receiving a particle beam generated after the neutron beam irradiates a sample to be detected; the computational analysis system is electrically connected with the detection system and is used for receiving detection signals of the detection system, and therefore the detection device for the special nuclear materials can improve the detection reliability.
Description
Technical Field
The application relates to the technical field of nuclear material detection, in particular to a detection device for special nuclear materials.
Background
The Special Nuclear Material (SNM) is a core material for manufacturing the simple nuclear device (IND), if a terrorist uses the simple nuclear device manufactured by the special nuclear material to carry out low-power ground nuclear explosion, instantaneous composite damage and serious radioactive contamination can be caused, so that casualties can be caused, the national infrastructure and economy can be damaged, and the society can be panic, therefore, the illegal transfer of the nuclear material can be prevented by enhancing the monitoring and detection of the special nuclear material, and the occurrence of nuclear terrorist attack can be prevented.
In the related art, the detection device for the special nuclear material has the problem of low detection reliability.
SUMMERY OF THE UTILITY MODEL
In view of the above, it is desirable to provide a detection apparatus for a special nuclear material, which can improve detection reliability.
An embodiment of the present application provides a detection device for a special nuclear material, which is characterized by including:
the neutron source system comprises a neutron source, and the neutron source is used for emitting a neutron beam to irradiate a sample to be measured;
the detection system comprises a detector, the detector is arranged at the downstream of the neutron source along the transmission direction of the neutron beam and is used for receiving a particle beam generated after the neutron beam irradiates the sample to be detected;
and the computational analysis system is electrically connected with the detection system and is used for receiving detection signals of the detection system.
In one embodiment, the neutron source is a pulsed neutron source.
In one embodiment, the detection device comprises a shield defining the transmission path of the neutron beam.
In one embodiment, the number of said shields is two, two of said shields defining a transmission path for said neutron beam, said neutron source system being located at least partially in said transmission path.
In one embodiment, the number of the detectors is two, and the two detectors are respectively disposed on two sides of the sample to be measured and are used for receiving particle beams generated after the sample to be measured is irradiated by the neutron beams.
In one embodiment, the detector is one or more of a plastic scintillator detector, a liquid detector, and a He-3 neutron detector.
In one embodiment, the detector is the He-3 neutron detector, the diameter of the He-3 neutron detector is D, and D is more than or equal to 40mm and less than or equal to 60 mm.
In one embodiment, the length of the He-3 neutron detector is L, wherein L is more than or equal to 1000mm and less than or equal to 1200 mm.
In one embodiment, the charging pressure of the He-3 neutron detector is A, wherein A is more than or equal to 0.8atm and less than or equal to 1.2 atm.
In one embodiment, the detection system includes a moderator through which the particle beam passes before being transmitted to the detector.
In one embodiment, the moderator is a polyethylene structure.
In one embodiment, the moderator has a thickness H, wherein H is 25mm or less and 35mm or less.
In one embodiment, the detection system includes an amplifier module electrically connected to the detector, and the amplifier module is configured to perform a shaping and amplification process on the detection signal.
In one embodiment, the detection system includes a signal acquisition module electrically connected to the computational analysis system and the amplifier module, and the signal acquisition module is configured to acquire and analyze the detection signal processed by the amplifier module and transmit the detection signal to the computational analysis system.
The embodiment of the application provides a detection device for special nuclear materials, which comprises a neutron source system, a detection system and a calculation analysis system, wherein a neutron beam emitted by a neutron source of the neutron source system irradiates on a sample to be detected; when the sample to be detected does not contain special nuclear materials, the neutron beam irradiates on the sample to be detected to generate no new neutrons, the detection signal of the detection system is received through the calculation and analysis system, whether the sample to be detected contains the special nuclear materials or not is calculated and judged according to the neutron number detected by the detector and the neutron attenuation characteristics, and due to the fact that the energy range of the neutron beam emitted by the neutron source is narrow, the influence of neutrons with other energies on the detection result can be reduced, the detection accuracy is improved, and the detection reliability is improved.
Drawings
Fig. 1 is a schematic structural diagram of a detection apparatus according to an embodiment of the present application;
fig. 2 is a schematic structural diagram of another view angle of the detecting device in fig. 1.
Description of the reference numerals
A neutron source system 10; a neutron source 11; a detection system 20; a detector 21; an amplifier module 22; a signal acquisition module 23; a power supply module 24; a computational analysis system 30; a shield 40; the sample to be tested 50.
Detailed Description
It should be noted that, in the present application, technical features in examples and embodiments may be combined with each other without conflict, and the detailed description in the specific embodiment should be understood as an explanation of the gist of the present application and should not be construed as an improper limitation to the present application.
The embodiment of the present application provides a detection apparatus for a special nuclear material, please refer to fig. 1 and fig. 2, including a neutron source system 10, a detection system 20, and a calculation analysis system 30, wherein the neutron source system 10 includes a neutron source 11, and the neutron source 11 is used for emitting a neutron beam to irradiate a sample 50 to be detected; the detection system 20 comprises a detector 21, the detector 21 is arranged downstream of the neutron source 11 along the transmission direction of the neutron beam and is used for receiving the particle beam generated after the sample 50 to be detected is irradiated by the neutron beam; the computational analysis system 30 is electrically connected to the detection system 20 for receiving the detection signals of the detection system 20.
It should be understood that, the neutron beam emitted by the neutron source 11 irradiates on the sample 50 to be detected, when the sample 50 to be detected does not contain special nuclear materials, the neutron beam irradiates on the sample 50 to be detected, new neutrons are not generated, the counting rate of the neutrons is reduced quickly, when the sample 50 to be detected contains special nuclear materials, the neutron beam irradiates on the special nuclear materials and causes the special nuclear materials to fission, new neutrons are generated, a particle beam is formed, and the particle beam is detected by the first detector 21, so that the counting rate of the neutrons is reduced slowly, and therefore, whether the sample 50 to be detected contains special nuclear materials can be judged according to the number of the neutrons detected by the detector 21 and the neutron attenuation characteristics.
In the related art, the neutron beam generated by the photoneutron conversion target irradiates the sample to be detected, and because the energy range of the neutron beam generated by the photoneutron conversion target is wider, and the neutrons with low energy more easily act with the special nuclear material, neutrons with other energy can influence the detection result, so that the detection accuracy of the detection device for the special nuclear material is reduced, and the detection reliability is further reduced.
The detection device provided by the embodiment of the application irradiates the sample to be detected 50 through the neutron beam emitted by the neutron source 11, the energy range of the neutron beam emitted by the neutron source 11 is narrow, the influence of neutrons with other energies on the detection result can be reduced, the detection device is electrically connected with the detection system 20 through the calculation analysis system 30 and is used for receiving the detection signal of the detection system 20, the calculation analysis system 30 can process complex operation and save data, the detection result can be analyzed more easily, and the detection accuracy is improved.
In addition, each spare part of the detection device that this application embodiment provided is adjustable, can detect large-scale freight train and box, also can detect small-size parcel, and simple structure is convenient, and it is more convenient to use. For example, the distance between the neutron source 11 and the detector 21 can be adjusted, and the distance between the neutron source 11 and the detector 21 can be adjusted according to the size of the sample 50 to be measured.
In an embodiment, the neutron source 11 is a pulse neutron source 11, and after the pulse neutron source 11 emits the neutron beam, the neutron may have an attenuation phenomenon, and it is more convenient to judge whether the special nuclear material exists in the sample 50 to be measured according to the attenuation characteristics of the number of neutrons in one period.
When the sample 50 to be tested does not contain special nuclear materials, the neutron beams enter the sample 50 to be tested during the period that the pulse neutron source 11 emits the neutron beams, the numbers of fast neutrons and epithermal neutrons are gradually increased and reach peak values; after the emission of the pulse neutron source 11 is finished, neutrons are accompanied by scattering and escape phenomena, the number of fast neutrons and epithermal neutrons is E exponential attenuation, meanwhile, the number of thermal neutrons in the sample 50 to be detected is rapidly increased within a certain time along with the phenomenon of fast neutron thermalization, when the thermal neutrons are absorbed or escape, the number of neutrons is obviously reduced, and after a certain time, the detector 21 cannot detect the fast neutrons and the epithermal neutrons. If the sample 50 to be tested contains a certain amount of special nuclear materials, the number of thermal neutrons still decays, but the thermal neutrons further react with the special nuclear materials to cause the special nuclear materials to have fission reaction and generate new fast neutrons, and the number of the fast neutrons generated in the fission process is in direct proportion to the number of the thermal neutrons reacted with the special nuclear materials. Fast neutrons generated by fission reaction of the special nuclear materials are thermalized to form thermal neutrons, so that the number of the thermal neutrons is increased, and the attenuation speed of the thermal neutrons in the neutron beam is reduced. Therefore, after the pulsed neutron source 11 emits the neutron beam, the attenuation characteristic of the number of thermal neutrons detected by the detector 21 can be used for judging whether the special nuclear material exists in the sample 50 to be detected. When a special nuclear material is present in the sample 50 to be measured, the thermal neutron quantity decays relatively slowly.
In one embodiment, referring to fig. 1 and fig. 2, the detecting device includes a shielding body 40, the shielding body 40 can collimate the neutron source 11, and at the same time, the interference and influence of the neutron source 11 on the detector 21 can be reduced, so as to increase the sensitivity and accuracy of the detection.
The transmission path of the neutron beam is defined by the shield 40 for enabling the transmission path and the transmission direction of the neutron beam to be defined, so that uncertainty of the transmission direction of the neutron beam can be reduced and the arrangement of the detector 21 is facilitated.
The specific shape of the shielding body 40 is not limited herein, and is, for example, a cylinder, a column, or a block, for example, the shielding body 40 is a cylinder with a receiving cavity with one open end, the neutron source system 10 extends into the receiving cavity from the open end of the shielding body 40 and transmits along the extending direction of the receiving cavity, a delivery port is opened at an end opposite to the open end of the shielding body 40, and the neutron beam is emitted through the delivery port to irradiate the sample 50 to be measured.
In one embodiment, referring to fig. 2, there are two shielding bodies 40, the two shielding bodies 40 are disposed opposite to each other and define a transmission path of the neutron beam, the two shielding bodies 40 are disposed opposite to each other at a certain distance, and a gap between the two shielding bodies 40 is the transmission path of the neutron beam defined by the two shielding bodies 40, that is, the neutron beam generated by the neutron source 11 is transmitted along the transmission path defined by the shielding bodies 40.
Wherein said "neutron source system 10 is at least partially located in the transmission path" means that the neutron source system 10 may be located entirely in the transmission path or partially in the transmission path.
Referring to fig. 2, the sample 50 to be detected is disposed at an end of the shielding body 40, that is, the sample 50 to be detected is located at an end of the neutron beam transmission path, so that the neutron beam directly irradiates the sample 50 to be detected after passing through the transmission path, thereby ensuring the reliability and accuracy of detection.
Referring to fig. 1 and 2, two detectors 21 are provided, the two detectors 21 are respectively disposed on two sides of the sample 50 to be detected and are used for receiving particle beams generated after the neutron beam irradiates the sample 50 to be detected, and the two detectors 21 simultaneously receive particle beams generated after the neutron beam irradiates the sample 50 to be detected, so as to increase the detection range and improve the detection efficiency and the detection accuracy.
The detector 21 is one or more of a plastic scintillator detector, a liquid detector and a He-3 neutron detector, exemplarily, the two detectors 21 are selected to be consistent in type and are He-3 neutron detectors, the two detectors are consistent in type, comparison of detection results is facilitated, and the He-3 neutron detectors are not sensitive to gamma rays and are beneficial to accurate detection of neutrons.
In one embodiment, the diameter of the He-3 neutron detector is D, wherein D is more than or equal to 40mm and less than or equal to 60mm, and the diameter of the He-3 neutron detector is 50 mm.
In one embodiment, the length of the He-3 neutron detector is L, wherein L is more than or equal to 1000mm and less than or equal to 1200mm, and the length of the He-3 neutron detector is 1100 mm.
The diameter and length of the He-3 neutron detector can determine the volume of the He-3 neutron detector, and the volume of the He-3 neutron detector can affect the detection efficiency of the He-3 neutron detector.
In one embodiment, the charging pressure of the He-3 neutron detector is A, wherein A is more than or equal to 0.8atm and less than or equal to 1.2atm, and the charging pressure of the He-3 neutron detector is 1atm exemplarily.
The inflation pressure of the He-3 neutron detector can also influence the detection efficiency of the He-3 neutron detector, and the higher the inflation pressure is, the higher the cost is, so that the inflation pressure is reduced as much as possible on the premise of meeting the detection sensitivity, that is, the inflation pressure is reduced on the premise of ensuring the detection efficiency, and the cost can be reduced.
The detection system 20 includes a moderator (not shown) which can moderate neutrons into thermal neutrons and form uniform distribution in a certain area, and the particle beam is transmitted to the detector 21 through the moderator, that is, design parameters and materials of the moderator can be determined according to detection requirements, such as source intensity, energy, and the like, so as to improve reliability and detection accuracy of the detection device.
The material of the moderator needs to have excellent neutron moderating capability, good heat-conducting property and radiation-resistant stability, better structural strength and convenient processing and forming.
The material of the moderator is not limited herein, and is, for example, polyethylene, and the moderator is of a polyethylene structure.
In one embodiment, the moderator has a thickness H, where H is 25mm ≦ 35mm, and illustratively has a thickness of 30 mm.
The moderator can determine the design parameters and material of the moderator according to the detection requirements, such as the source intensity, the energy and the like, for example, the thickness of the moderator, if the moderator is too thin, when the neutron energy is high, the moderator can easily pass through the detector 21, if the moderator is too thick, the neutron can be easily moderated and absorbed, and can not reach the detector 21, therefore, if the moderator is too thin or too thick, the detection accuracy can be affected, and for example, the moderator of the embodiment has a thickness of 30mm, and can meet the detection requirement.
In one embodiment, the neutron source system 10 includes a neutron source 11, a main control module and a high voltage multiplication circuit, wherein the neutron source 11, the main control module and the high voltage multiplication circuit are integrated into a whole, so that the structure is simplified and the installation space is saved.
In one embodiment, referring to fig. 1 and fig. 2, the detection system 20 includes an amplifier module 22 electrically connected to the detector 21, and the amplifier module 22 is configured to perform a shaping and amplifying process on the detection signal, so that the signal acquisition module 23 can acquire the signal more quickly and accurately.
In an embodiment, referring to fig. 1 and fig. 2, the detection system 20 includes a signal acquisition module 23 electrically connected to the computational analysis system 30 and the amplifier module 22, and the signal acquisition module 23 is configured to acquire and analyze the detection signal processed by the amplifier module 22 and transmit the acquired detection signal to the computational analysis system 30.
In one embodiment, referring to fig. 1 and 2, the detection system 20 includes a power module 24, and the power module 24 is responsible for supplying power and distributing voltage to the entire detection device.
The various embodiments/implementations provided herein may be combined with each other without contradiction.
The above description is only a preferred embodiment of the present application and is not intended to limit the present application, and various modifications and changes may be made by those skilled in the art. Any modification, equivalent replacement, improvement and the like made within the spirit and principle of the present application are included in the protection scope of the present application.
Claims (11)
1. A special nuclear material detection device, comprising:
a neutron source system (10), said neutron source system (10) comprising a neutron source (11), said neutron source (11) being adapted to emit a neutron beam to irradiate a sample (50) to be measured;
a detection system (20), the detection system (20) comprising a detector (21), the detector (21) being arranged downstream of the neutron source (11) along the transport direction of the neutron beam for receiving a particle beam generated after the sample (50) to be measured is irradiated by the neutron beam;
a computational analysis system (30), the computational analysis system (30) being electrically connected with the detection system (20) for receiving detection signals of the detection system (20).
2. A detection apparatus according to claim 1, wherein the neutron source (11) is a pulsed neutron source.
3. The detection apparatus according to claim 1, wherein the detection apparatus comprises a shield (40), the shield (40) defining a transmission path for the neutron beam.
4. A detection apparatus according to claim 3, wherein there are two shields (40), the two shields (40) being arranged opposite each other and defining a transmission path for the neutron beam, the neutron source system (10) being at least partially located in the transmission path.
5. The detection apparatus according to claim 1, wherein the number of the detectors (21) is two, and the two detectors (21) are respectively disposed at two sides of the sample (50) to be detected for receiving the particle beam generated by the neutron beam after irradiating the sample (50) to be detected.
6. A detection arrangement according to claim 1, characterized in that the detector (21) is one or more of a plastic scintillator detector, a liquid detector and a He-3 neutron detector.
7. The detection device according to claim 6, wherein the detector (21) is the He-3 neutron detector, the He-3 neutron detector having a diameter D, wherein D is greater than or equal to 40mm and less than or equal to 60 mm; and/or the presence of a gas in the gas,
the length of the He-3 neutron detector is L, wherein L is more than or equal to 1000mm and less than or equal to 1200 mm; and/or the presence of a gas in the gas,
the charging pressure of the He-3 neutron detector is A, wherein A is more than or equal to 0.8atm and less than or equal to 1.2 atm.
8. A detection apparatus according to claim 1, wherein the detection system (20) comprises a moderator through which the particle beam is transported to the detector (21).
9. The probe apparatus of claim 8, wherein the moderator is a polyethylene structure; and/or the presence of a gas in the gas,
the thickness of the moderator is H, wherein H is more than or equal to 25mm and less than or equal to 35 mm.
10. The detection apparatus according to claim 1, wherein the detection system (20) comprises an amplifier module (22) electrically connected to the detector (21), the amplifier module (22) being configured to perform a shaping amplification process on the detection signal.
11. The detection apparatus according to claim 10, wherein the detection system (20) comprises a signal acquisition module (23) electrically connected to the computational analysis system (30) and the amplifier module (22), and the signal acquisition module (23) is configured to perform acquisition and analysis on the detection signal processed by the amplifier module (22) and transmit the detection signal to the computational analysis system (30).
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| Application Number | Priority Date | Filing Date | Title |
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| CN202220430097.XU CN217133392U (en) | 2022-03-01 | 2022-03-01 | Detection device for special nuclear materials |
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| CN202220430097.XU CN217133392U (en) | 2022-03-01 | 2022-03-01 | Detection device for special nuclear materials |
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