CN111060955A - Neutron energy spectrum measuring device based on multilayer neutron moderated fluorescence and optical fiber conduction - Google Patents
Neutron energy spectrum measuring device based on multilayer neutron moderated fluorescence and optical fiber conduction Download PDFInfo
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Abstract
The invention discloses a neutron energy spectrum measuring device based on multilayer neutron moderated fluorescence and optical fiber conduction, which comprises: multilayer detection piece, fluorescence receiving arrangement and data processing system, wherein: the multilayer detection sheets are stacked and used for moderating the vertically incident collimated neutron beam and sending the generated fluorescence to the fluorescence receiving device, and the multilayer detection sheets are all vertical to the incident direction of the collimated neutron beam; the fluorescence receiving device is tightly attached to one side of the multilayer detection sheets and used for collecting fluorescence transmitted by the multilayer detection sheets, recording the light emission quantity information of each layer of detection sheets and sending the information to the data processing system; and the data processing system calculates and obtains the energy spectrum information of the detected neutrons according to the luminescence quantity information of each layer of detection sheets and the neutron energy response of each layer of detection sheets. The measuring device has the advantages of simple structure, small volume, wide energy measuring range, high detection efficiency and better energy resolution, can realize online real-time or offline measurement, and can be used as a supplement for the conventional neutron spectrum measurement.
Description
Technical Field
The invention belongs to the technical field of neutron energy spectrum measurement, and particularly relates to a neutron energy spectrum measuring device based on multilayer neutron moderated fluorescence and optical fiber conduction.
Background
Neutron spectrum measurement is used as the basis of neutron physics basic research and technical application research, and has wide development requirements. Various neutron spectrum measuring methods have been established according to different neutron source types and application purposes, including a time-of-flight method, a Bonner sphere spectrometer method, a recoil proton method, a nuclear reaction method, a threshold detector method, a track etching method, and the like. The following describes the application fields and advantages and disadvantages of several main neutron spectrum measurement methods.
The flight time method carries out energy spectrum measurement according to the difference of the flight times of neutrons with different energies under the known distance, and the method has the advantages of simple principle, high resolution, long flight distance, large required space, and complicated operation because the interference on system calibration and photon background elimination is required. According to the Bonner sphere spectrometer method, a plurality of spherical moderators with different diameters and thermal neutron detectors placed in the centers of the moderators are utilized, and according to the characteristic that each neutron detector has different neutron energy response functions, reading of each detector is subjected to spectrum resolving operation, so that neutron energy spectrum information is obtained. The method has the advantages of independent equipment, flexible point distribution and wide energy measurement range, but needs a plurality of Bonner ball detectors, is long in measurement time consumption, has resolution depending on fluence measurement and mathematical processing, and is generally low.
The recoil proton method utilizes the relation between the energy of recoil hydrogen atomic nucleus and the energy of incident neutron when the neutron collides with the hydrogen atom in the hydrogen-containing substance, and the neutron energy is calculated by measuring the energy of the recoil proton. The neutron energy range measurable by the method is wide, but the energy resolution and the detection efficiency are not high.
The nuclear reaction method obtains neutron energy information by measuring the energy of charged particles released by the neutron-induced nuclear reaction, and the reaction of neutrons and Li-6 or He-3 is usually adopted. The method is independent of the incident direction of neutrons, does not require collimation of neutron beams, but has a narrow measurable neutron energy range and poor resolution particularly for low-energy neutrons.
The threshold detector method comprises a group of threshold detectors with effective threshold values uniformly distributed in an energy area to be detected, and a neutron energy spectrum is obtained according to the activity of a reaction product. The method is insensitive to gamma ray background and subthreshold neutrons, and the detector has small volume and has the defects of limitation of a metal activation sheet and poor resolution.
The track etching method utilizes a CR-39 detector to record the tracks of recoil protons generated by the action of neutrons and hydrogen-containing materials, and obtains the length and the number of the tracks under certain etching conditions, thereby obtaining neutron energy spectrum information. The method has simple structure and small volume, but has poor resolution, can not realize on-line measurement and has complex post-processing.
Disclosure of Invention
In order to solve the problems, the invention provides a neutron energy spectrum measuring device based on multilayer neutron moderated fluorescence and optical fiber conduction, which has the advantages of simple structure, small volume, wide energy measuring range, high detection efficiency and better energy resolution, can realize online real-time or offline measurement, and can be used as a supplement for the conventional neutron energy spectrum measurement.
The invention provides a neutron energy spectrum measuring device based on multilayer neutron moderated fluorescence and optical fiber conduction, which comprises: multilayer detection piece, fluorescence receiving arrangement and data processing system, wherein: the multi-layer detection sheets are formed by sequentially overlapping a plurality of single-layer detection sheets and aluminum foil and are used for slowing down vertically incident collimated neutron beams and sending generated fluorescence to the fluorescence receiving device, wherein the multi-layer detection sheets are all perpendicular to the incident direction of the collimated neutron beams;
the fluorescence receiving device is arranged on one side of the multilayer detection sheets and is used for collecting fluorescence transmitted by the multilayer detection sheets, recording the light-emitting amount information of each layer of detection sheets and sending the light-emitting amount information to the data processing system; and the data processing system calculates and obtains the energy spectrum information of the detected neutrons according to the luminescence quantity information of each layer of detection sheets and the neutron energy response of each layer of detection sheets.
Preferably, the end face of the multilayer detection piece is coated with an aluminum foil for reflecting fluorescence except for the end face facing the fluorescence receiving device, thereby increasing detection efficiency.
Preferably, the single-layer detection segment comprises a neutron moderating fluorescent material and one or more optical fibers inserted therein in parallel arrangement.
Furthermore, the neutron moderation fluorescent material is prepared by uniformly doping a hydrogen-rich material with a thermal neutron detection fluorescent material.
Preferably, the number of layers of the multilayer detection segment may be set according to the energy of the incident neutron.
Preferably, the fluorescence receiving device is a CCD camera. The CCD camera is connected with the data processing system, the fluorescence light quantity of each layer of detection sheets is sent to the data processing system, and the data processing system calculates and displays the energy spectrum information of the measured neutrons through mathematical processing according to the fluorescence light quantity of different detection sheets and the neutron energy response of each layer of detection sheets.
Preferably, the fluorescence receiving means is a film. The film is tightly attached to the emergent end face of the optical fiber, and the data processing system calculates and displays the energy spectrum information of the measured neutron through mathematical processing according to the exposure of the film and the neutron energy response of each layer of detection film.
The invention combines neutron moderation fluorescence and optical fiber conduction to be applied to neutron energy spectrum measurement, and has the following advantages:
1) by recording the fluorescence luminescence quantity generated by different moderation layers, a plurality of thermal neutron detectors are avoided, so that the measuring device has the advantages of simple structure, small volume and low cost;
2) the neutron moderating fluorescent layer has high neutron detection efficiency, and high efficiency, wide energy measurement range and better resolution can be realized by optimizing the number and the thickness of the detection layers;
3) the fluorescence light quantity of the detection sheet is recorded by a CCD camera or a film, so that online real-time and offline energy spectrum measurement can be realized, particularly for offline measurement, a power supply device is not needed, and the distribution of spots can be facilitated.
Drawings
FIG. 1 is a schematic view of the construction of the neutron spectrum measuring device of the present invention;
FIG. 2 is a schematic diagram of a single-layer probe tile according to an embodiment of the present invention;
fig. 3 is a schematic diagram of neutron spectrum measurement principle based on CCD imaging.
Description of reference numerals:
1-an optical fiber; 2-neutron moderated fluorescent material; 3-single layer detection slice; 4-aluminum foil; 5-multilayer detection patches; 6-collimation of neutrons; 7-a fluorescence receiving device; 8-a data processing system; 9-film.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to specific embodiments and the accompanying drawings.
Fig. 1 is a schematic structural diagram of a neutron spectrum measuring device of the present invention, and as shown in fig. 1, the neutron spectrum measuring device based on multi-layer moderated fluorescence and optical fiber conduction provided by the present invention includes: multilayer detection piece, fluorescence receiving arrangement and data processing system, wherein:
the multilayer detection piece 5 is detected piece 3 and aluminium foil 4 by a plurality of individual layers and is superposed in proper order and constitute, is equipped with aluminium foil 4 between each layer detection piece 3 for reflection fluorescence, in order to prevent each layer fluorescence and produce interference each other, in addition, the multilayer detection piece superposes and becomes a whole back, except by the terminal surface that fluorescence receiving arrangement 7 corresponds, other several terminal surfaces all coat has aluminium foil 4, is used for reflection fluorescence, increases detection efficiency.
The single-layer detection segment 3 is formed by inserting one or more optical fibers 1 in parallel to the neutron moderating fluorescent material 2, and is used for moderating and absorbing neutrons as shown in fig. 2. The neutron moderation fluorescent material 2 is made of a material which is rich in hydrogen and is uniformly doped with a thermal neutron detection fluorescent material, is used for moderating incident neutrons, and reacts with the neutrons to generate fluorescence.
The collimated neutron beam 6 perpendicularly enters the multi-layer detection slices 5, and the fluorescence intensity generated by each single-layer detection slice 3 is recorded by the fluorescence receiving device 7. And setting the number of layers of the multilayer detection sheets according to the energy of incident neutrons.
The fluorescence receiving device 7 is arranged on one side of the multilayer detection sheet 5, as shown in fig. 1, and is used for collecting fluorescence transmitted by the multilayer detection sheet 5, recording the luminescence amount information of each layer of detection sheet, and sending the luminescence amount information to the data processing system 8; an aluminum foil 4 is attached (e.g., pasted) to one end of the optical fiber away from the fluorescence receiving device, and is used for reflecting the fluorescence transmitted to the end to the other end of the optical fiber, so that the fluorescence is collected and recorded in a centralized manner by the fluorescence receiving device 7 at the other end of the optical fiber.
The fluorescence receiving device 7 is a CCD camera, and the CCD camera is connected to the data processing system 8 so as to perform mathematical processing on the fluorescence light emission quantity of each layer of the multilayer detection sheets to obtain corresponding detected neutron energy spectrum information and realize the online real-time measurement of the neutron energy spectrum;
specifically, the neutron beam to be detected vertically irradiates the multiple layers of detection sheets after being collimated, neutrons with different energies are moderated by the detection sheets with different thicknesses to become thermal neutrons, the thermal neutrons react with neutron moderated fluorescent materials on a certain layer of detection sheets and excite fluorescence, and the fluorescence is transmitted to an emergent end face through the optical fiber and is recorded by the CCD camera. The luminescence amount of each detection slice fiber represents the neutron fluence recorded by the detection slice of the layer, and the CCD camera transmits the recorded luminescence amount information to the data processing system 8.
The data processing system 8 calculates and draws a neutron energy spectrum through mathematical processing according to the fluorescence luminescence amount information of each single-layer detection sheet 3 and the neutron energy response difference of each single-layer detection sheet 3, and displays the neutron energy spectrum on a display of the data processing system so as to realize real-time online measurement.
In another embodiment of the present invention, the fluorescence receiving device 7 can also use a film 9 for off-line measurement, as shown in fig. 3. The moderated fluorescence of the neutrons and the conduction of the optical fibers are the same as the conditions of neutron energy spectrum measurement of CCD imaging, and only after the film 6 is adopted to replace a CCD camera, the film 9 is tightly attached to the end face of the optical fibers which is not covered by the aluminum foil 3, namely the emergent end face of the optical fibers. When neutron spectrum measurement is performed, fluorescence generated by vertically irradiated measured neutrons is transmitted by an optical fiber and then exposed on a film 9. After exposure is finished, the exposure of the film is read in a darkroom, and the exposure is mathematically processed by combining neutron energy response of each layer of detection piece, so that neutron energy spectrum information is obtained. That is, the film can be used for off-line measurement, so that the measuring device has small volume and simple structure, does not need a power supply system, and can be flexibly distributed.
Other devices that can receive and record fluorescence can be used with the present invention and are not intended to be limiting.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are only exemplary embodiments of the present invention, and are not intended to limit the present invention, and any modifications, equivalents, improvements and the like made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (9)
1. A neutron spectroscopy measurement device based on multi-layer neutron moderated fluorescence and fiber optic conduction, the device comprising: multilayer detection piece, fluorescence receiving arrangement and data processing system, wherein:
the multilayer detection sheets are formed by sequentially overlapping a plurality of single-layer detection sheets and an aluminum foil and are used for slowing down vertically incident collimated neutron beams and sending generated fluorescence to the fluorescence receiving device, wherein the multilayer detection sheets are all perpendicular to the incident direction of the collimated neutron beams;
the fluorescence receiving device is placed on one side of the multilayer detection sheets and is used for collecting fluorescence transmitted by the multilayer detection sheets, recording the light-emitting amount information of each layer of detection sheets and sending the light-emitting amount information to the data processing system;
and the data processing system calculates and obtains the energy spectrum information of the detected neutrons according to the luminescence quantity information of each layer of detection sheets and the neutron energy response of each layer of detection sheets.
2. The apparatus of claim 1, wherein the end faces of the multi-layered detection sheets are coated with aluminum foil for reflecting fluorescence except for the end faces toward the fluorescence receiving means, thereby increasing detection efficiency.
3. The apparatus of claim 1, wherein the single slice detection segments comprise a neutron moderating fluorescent material and one or more optical fibers inserted therein in parallel arrangement.
4. The apparatus of claim 3, wherein the neutron moderating fluorescent material is made of a thermal neutron detecting fluorescent material uniformly doped with a hydrogen-rich material.
5. The apparatus of claim 1, wherein the number of layers of the multilayer detection segment is set according to the energy of incident neutrons.
6. The apparatus of claim 1, wherein the fluorescence receiving device is a CCD camera.
7. The device of claim 1, wherein the fluorescence receiving device is a film.
8. The device as claimed in claim 6, wherein the CCD camera is connected with a data processing system, the fluorescence light quantity of each layer of detection sheets is sent to the data processing system, and the data processing system calculates and displays the energy spectrum information of the detected neutrons through mathematical processing according to the fluorescence light quantity of different detection sheets and the neutron energy response of each layer of detection sheets.
9. The apparatus of claim 7, wherein the film is tightly attached to the exit end face of the optical fiber, and the data processing system calculates and displays the energy spectrum information of the measured neutrons through mathematical processing according to the exposure of the film and the neutron energy response of each layer of detection film.
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Application publication date: 20200424 |