CN116908226B - Material component detection device based on neutron activation analysis technology - Google Patents

Material component detection device based on neutron activation analysis technology Download PDF

Info

Publication number
CN116908226B
CN116908226B CN202311162998.0A CN202311162998A CN116908226B CN 116908226 B CN116908226 B CN 116908226B CN 202311162998 A CN202311162998 A CN 202311162998A CN 116908226 B CN116908226 B CN 116908226B
Authority
CN
China
Prior art keywords
shielding
channel
neutron
detector
assembly
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN202311162998.0A
Other languages
Chinese (zh)
Other versions
CN116908226A (en
Inventor
刘世胜
左金城
杏兴彪
孙浩
徐春生
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hefei Gstar Intelligent Control Technical Co Ltd
Original Assignee
Hefei Gstar Intelligent Control Technical Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Hefei Gstar Intelligent Control Technical Co Ltd filed Critical Hefei Gstar Intelligent Control Technical Co Ltd
Priority to CN202311162998.0A priority Critical patent/CN116908226B/en
Publication of CN116908226A publication Critical patent/CN116908226A/en
Application granted granted Critical
Publication of CN116908226B publication Critical patent/CN116908226B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N23/00Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
    • G01N23/02Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material
    • G01N23/06Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material and measuring the absorption
    • G01N23/09Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material and measuring the absorption the radiation being neutrons
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00Measuring neutron radiation
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Health & Medical Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Physics & Mathematics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • Toxicology (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Molecular Biology (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Measurement Of Radiation (AREA)

Abstract

The invention discloses a material component detection device based on neutron activation analysis technology, which comprises: a mounting frame; the detector shielding assembly is arranged on the mounting frame and defines a detector shielding cavity; a conveyor belt channel assembly mounted to the mounting frame, the conveyor belt channel assembly defining a conveyor belt channel for receiving a conveyor belt; the neutron source shielding assembly is arranged on the mounting frame and defines a mounting channel; a neutron source mounting assembly mounted within the mounting channel and defining a neutron source shielding cavity for disposing a neutron generator; the material composition detection device is configured to cause neutrons emitted by the neutron generator to impinge on the material within the conveyor belt passageway. According to the material component detection device provided by the embodiment of the invention, the overall structural compactness can be improved, the radiation shielding effect of the material component detection device is improved, so that the radiation safety and controllability are realized, the components are convenient to maintain and overhaul in a laminated arrangement mode, and the service life of the device is prolonged.

Description

Material component detection device based on neutron activation analysis technology
Technical Field
The invention relates to the technical field of component detection, in particular to a material component detection device based on neutron activation analysis technology.
Background
In industries such as building materials, metallurgy, mines, coal, electric power and the like, the original detection of material components needs to be carried out after a sample is collected, so that the types and the contents of elements in the sample are obtained; in recent years, with the continuous intensive research on neutron activation technology, neutron activation analysis detection devices are also gradually applied to different scenes, for example, detection of element types and contents in samples.
In the related art, the neutron activation analysis detection equipment has poor structural compactness, is inconvenient to maintain, has poor radiation shielding effect, and is unfavorable for the safety and controllability of radiation.
Disclosure of Invention
The present invention aims to solve at least one of the technical problems existing in the prior art. Therefore, an object of the present invention is to provide a material component detecting device based on neutron activation analysis technology, where the material component detecting device based on neutron activation analysis technology has a good compactness, is convenient to maintain, has a good radiation shielding effect, and is beneficial to improving the safety and controllability of radiation.
According to an embodiment of the invention, a material component detection device based on neutron activation analysis technology comprises: a mounting frame; the detector shielding assembly is arranged on the mounting frame and defines a detector shielding cavity, and a detector is arranged in the detector shielding cavity; a conveyor belt channel assembly mounted to the mounting frame and located on one side of the detector shield assembly in a first direction, the conveyor belt channel assembly defining a conveyor belt channel extending in a second direction, the conveyor belt channel for receiving a conveyor belt conveying material in the second direction, the second direction intersecting the first direction; the neutron source shielding assembly is mounted on the mounting frame and located on one side, away from the detector shielding assembly, of the conveyor channel assembly in the first direction, and the neutron source shielding assembly defines a mounting channel; the neutron source installation assembly is installed in the installation channel and matched with the neutron source shielding assembly to define a neutron source shielding cavity, and a neutron generator is arranged in the neutron source shielding cavity; wherein the material composition detection device is configured to cause neutrons emitted by the neutron generator to irradiate material within the conveyor belt channel to emit characteristic rays, and the detector is configured to detect the characteristic rays.
According to the material component detection device based on the neutron activation analysis technology, the detector shielding assembly, the transmission channel assembly and the neutron source shielding assembly are sequentially stacked and arranged on the mounting frame along the first direction, the neutron source mounting assembly is used for mounting the neutron generator in the neutron source shielding assembly, the overall structural compactness can be improved, the radiation shielding effect of the material component detection device is improved, the safety and the controllability of radiation are facilitated, the working safety of the device is improved, the stacked and arranged mode is convenient for maintaining and overhauling all the assemblies, and the service life of the device is prolonged.
In addition, the material component detection device based on the neutron activation analysis technology according to the above embodiment of the present invention may further have the following additional technical features:
according to some embodiments of the invention, the detector shield assembly comprises: the detector channel access plates comprise a first end access plate and first side access plates which are respectively arranged at two sides of the first end access plate along the second direction, the detector channel access plates are arranged in a stacked mode along a third direction and detachably connected, and the third direction is intersected with the first direction and the second direction in pairs; the detector supporting plate is used for reflecting neutrons penetrating through the materials, is arranged between the two first side access plates and is spaced from the first end access plates so as to be matched with the detector channel access plates to define a first mounting channel, the first mounting channel penetrates through along the third direction, and the detector is mounted on the detector supporting plate; two first shielding matrix groups, two first shielding matrix groups are arranged in the first installation channel at intervals so as to define the detector shielding cavity between the two first shielding matrix groups, and the first shielding matrix groups comprise a plurality of first shielding matrixes which are arranged in a stacking mode.
According to some embodiments of the invention, the detector supporting plate is provided with a mounting groove with a notch facing the detector shielding cavity, a shielding cylinder is arranged in the mounting groove and used for shielding external rays, the detector is mounted in the shielding cylinder, and the shielding cylinder and the detector are separated from the groove bottom wall of the mounting groove by a preset gap.
According to some embodiments of the invention, a neutron absorbing plate is arranged between the detector and the detector supporting plate, and is used for absorbing neutrons penetrating through the material.
According to some embodiments of the invention, a passage lining plate is arranged between the first shielding matrix set and the first side access plate, and the passage lining plate is used for shielding a gap between the first shielding matrix set and the first side access plate.
According to some embodiments of the invention, the detector shield assembly further comprises a stop member, the stop member being stopped between two of the first shield base groups.
According to some embodiments of the invention, among the plurality of probe passage access plates, at least one side of the first end access plate opposite to the probe shielding cavity in the third direction is provided with a support protrusion, and the adjacent first end access plate is provided with a support mating portion, and the support protrusion is supported on a side of the support mating portion away from the probe shielding cavity.
According to some embodiments of the invention, the conveyor belt channel assembly comprises: the two channel brackets are spaced along a third direction, and the third direction is intersected with the first direction and the second direction in pairs; the bottom support piece comprises a channel slowing plate and channel support plates which are respectively arranged at two sides of the channel slowing plate along the second direction, and the bottom support piece is positioned between the two channel brackets and opposite to the neutron source shielding cavity along the first direction; the two inclined supporting pieces are respectively arranged between the bottom supporting pieces and the two channel brackets, each inclined supporting piece is provided with an inclined supporting surface, each inclined supporting surface faces upwards and inclines towards the direction away from the bottom supporting piece, and the two inclined supporting surfaces are matched with the bottom supporting pieces to define the channel of the conveying belt.
According to some embodiments of the invention, the tilt support comprises: a support body having a cavity extending along the second direction; and the inner supporting plate is arranged in the cavity and is connected with the cavity wall surface of the cavity.
According to some embodiments of the invention, the mounting comprises a plurality of posts, the posts comprising: the first column, the second column and the third column are sequentially arranged along the first direction, the second column is detachably connected with the first column and the third column respectively, and the two sides of the channel support along the second direction are connected with the first column of the upright column respectively.
According to some embodiments of the invention, at least one side of the conveyor belt channel in the second direction is provided with a conveyor belt idler for supporting the conveyor belt and the height of the conveyor belt idler in the first direction is adjustable.
According to some embodiments of the invention, two sides of the mounting frame along the second direction are respectively provided with a side shielding cover, and the material of the side shielding cover comprises boron-containing polyethylene material and includes: an end shield positioned on a side of the conveyor belt channel away from the neutron source shielding assembly in the first direction, and inclined away from the conveyor belt channel in the second direction and toward the neutron source shielding assembly in the first direction; and the two side shielding plates are respectively arranged at two sides of the transmission belt channel along the third direction.
According to some embodiments of the invention, the neutron source shielding assembly includes: the neutron source shielding butt straps comprise a second end butt strap and second side butt straps which are respectively arranged on two sides of the second end butt strap in the second direction, the neutron source shielding butt straps are arranged in a stacked mode in the third direction and are detachably connected to define an installation channel between the second side butt straps, the installation channel penetrates through in the third direction, and the third direction is intersected with the first direction and the second direction in a two-to-two mode.
According to some embodiments of the invention, a channel liner side plate is disposed between the neutron source mounting assembly and the second side access panel, the channel liner side plate being configured to conceal a gap between the neutron source mounting assembly and the second side access panel.
According to some embodiments of the invention, a channel liner end plate is disposed between the neutron source mounting assembly and the second end strap, the channel liner end plate being provided with a rail extending along the third direction, the neutron source mounting assembly being provided with rollers slidable along the rail.
According to some embodiments of the invention, the neutron source mounting assembly includes: the neutron source support plate is arranged in the mounting channel, and the neutron generator is mounted on one side of the neutron source support plate, which is opposite to the second end access plate; and two second shielding matrix groups, wherein the two second shielding matrix groups are arranged on the neutron source support plate at intervals so as to define the neutron source shielding cavity between the two second shielding matrix groups, and the second shielding matrix groups comprise a plurality of second shielding matrixes which are arranged in a stacking way.
According to some embodiments of the invention, the neutron source mounting assembly further comprises: a neutron reflector mounted to the neutron source support plate, the neutron reflector defining a receiving slot open to the conveyor channel assembly, the neutron reflector being configured to reflect neutrons within the receiving slot; the ray shielding piece is arranged on the accommodating groove and sleeved on the target source of the neutron generator so as to shield external gamma rays and self gamma rays of the neutron generator.
According to some embodiments of the invention, the neutron generator is a DD neutron generator.
According to some embodiments of the invention, the mounting comprises: the plurality of upright posts are arranged at intervals, and at least two upright posts are connected through upright post connecting pieces; the bearing framework is embedded and installed with at least part of the neutron source shielding component; the two ends of the first bearing cross beam are respectively connected with the two upright posts, and the detector shielding assembly is connected with the first bearing cross beam; the two ends of the second bearing cross beam are respectively connected with the two upright posts, and the conveying belt channel assembly is connected with the second bearing cross beam; and a support part is arranged between the detector shielding assembly and the upright post, between the neutron source shielding assembly and the upright post and between the transmission belt channel assembly and the upright post.
Additional aspects and advantages of the invention will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the invention.
Drawings
The foregoing and/or additional aspects and advantages of the invention will become apparent and may be better understood from the following description of embodiments taken in conjunction with the accompanying drawings in which:
FIG. 1 is a schematic view of a material composition detection apparatus according to an embodiment of the present invention;
FIG. 2 is a left side view of FIG. 1;
FIG. 3 is a top view of FIG. 1;
FIG. 4 is a cross-sectional view taken along line A-A of FIG. 3;
FIG. 5 is a partial enlarged view of FIG. 4 at circle B;
FIG. 6 is a schematic structural view of a mounting bracket according to an embodiment of the present invention;
FIG. 7 is a schematic view showing a part of the structure of a material component detecting apparatus according to an embodiment of the present invention;
FIG. 8 is a partial enlarged view of FIG. 7 at circle B;
FIG. 9 is a schematic structural view of a detector shield assembly according to an embodiment of the present invention;
FIG. 10 is a schematic view of a conveyor belt channel assembly according to an embodiment of the invention;
FIG. 11 is a schematic structural view of a neutron source shielding assembly according to an embodiment of the invention;
FIG. 12 is a schematic structural view of a neutron source mounting assembly according to an embodiment of the invention;
FIG. 13 is a left side view of FIG. 11;
fig. 14 is a cross-sectional view taken along line D-D of fig. 12.
Reference numerals:
a material component detecting device 100; a conveyor belt 200;
a mounting frame 10; a column 11; a first column 111; a second column 112; a third column 113; a side shield 12; an end shield plate 121; side shield plates 122; a column connector 13; a load-bearing framework 14; a first load beam 15; a second load beam 16; a support 17; a conveyor idler 18; a side shield mounting bracket 19;
a detector shield assembly 20; a detector shield cavity 21; a detector 22; a detector channel strap 23; a first end strap 231; a first side strap 232; a supporting protrusion 233; a support fitting portion 234; a detector support plate 24; a first mounting channel 241; a mounting groove 242; a shielding cylinder 243; a neutron absorbing plate 244; a first shielding matrix group 25; a first shield base 251; a passageway lining plate 26; a stopper 27;
a conveyor channel assembly 30; a conveyor path 31; a channel bracket 32; a bottom support 33; a passage slowing plate 331; a channel support plate 332; a tilt support 34; an inclined supporting surface 341; a support body 342; an inner support plate 343; a cavity 344;
a neutron source shielding assembly 40; a mounting channel 41; neutron source shielding straps 42; a second end strap 421; a second side strap 422; channel liner side panels 43; channel liner end plate 44;
A neutron source mounting assembly 50; a neutron source shielding cavity 51; a neutron generator 52; a neutron source support plate 53; a first plate 531; a second plate 532; a third plate 533; a base stopper 534; a component stopper 535; a second shielding matrix set 54; a second shielding base 541; neutron reflector 55; a receiving groove 551; a radiation shield 56; a guide rail 57; a roller 58; a channel-slowing plate support 59;
a housing 60.
Detailed Description
Embodiments of the present invention are described in detail below, examples of which are illustrated in the accompanying drawings, wherein like or similar reference numerals refer to like or similar elements or elements having like or similar functions throughout. The embodiments described below by referring to the drawings are illustrative only and are not to be construed as limiting the invention.
In the description of the present invention, it should be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", etc. indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings are merely for convenience of description and simplicity of description, and do not indicate or imply that the material component detection apparatus 100 or element referred to must have a specific orientation, be configured and operated in a specific orientation, and therefore should not be construed as limiting the present invention.
In the description of the invention, "a first feature" may include one or more such features, and "a plurality" may mean two or more, and that a first feature "above" or "below" a second feature may include both the first and second features being in direct contact, or may include both the first and second features not being in direct contact but being in contact with each other through additional features therebetween, with the first feature "above", "over" and "above" the second feature including both the first feature being directly above and obliquely above the second feature, or simply indicating that the first feature is higher in level than the second feature.
A material composition detecting apparatus 100 based on a neutron activation analysis technique according to an embodiment of the present invention is described below with reference to the accompanying drawings.
Referring to fig. 1 to 14, a material composition detection apparatus 100 based on a neutron activation analysis technique according to an embodiment of the present invention may include: the mounting frame 10, the detector shield assembly 20, the conveyor channel assembly 30, the neutron source shield assembly 40, and the neutron source mounting assembly 50.
Specifically, the probe shielding assembly 20 is mounted on the mounting frame 10, and the probe shielding assembly 20 defines a probe shielding cavity 21, and a probe 22 is disposed in the probe shielding cavity 21. The conveyor path assembly 30 is mounted to the mounting frame 10 and is positioned on one side of the detector shield assembly 20 in a first direction (e.g., the up-down direction as viewed in fig. 1), the conveyor path assembly 30 defining a conveyor path 31 extending in a second direction (e.g., the left-right direction as viewed in fig. 1), the conveyor path 31 being configured to receive a conveyor 200 for transporting material in the second direction, the second direction intersecting the first direction, e.g., the first direction and the second direction may be perpendicular. The neutron source shielding assembly 40 is mounted to the mounting frame 10 on a side of the conveyor path assembly 30 facing away from the detector shielding assembly 20 in a first direction, the neutron source shielding assembly 40 defining a mounting path 41.
The detector shielding assembly 20, the transmission belt channel assembly 30 and the neutron source shielding assembly 40 are sequentially arranged in a stacked mode along the first direction, so that the material component detection device 100 is compact in structure, the detector shielding assembly 20 and the neutron source shielding assembly 40 can achieve good shielding effect on radiation, the radiation quantity outwards diverging in the material component detection device 100 can be reduced, the shielding effect of the material component detection device 100 on the radiation is enhanced, and the working process of the material component detection device 100 is safer and more controllable.
When any component in the material component detecting device 100 has a problem and needs to be maintained or replaced, the components which are arranged in a stacked manner can be separated to maintain or replace any component independently, so that the whole material component detecting device 100 does not need to be maintained or replaced due to the problem of any component, the economy and the service life of the material component detecting device 100 are improved, and the material component detecting device 100 is more durable.
In addition, a neutron source mounting assembly 50 is mounted within the mounting channel 41 and cooperates with the neutron source shielding assembly 40 to define a neutron source shielding cavity 51, with a neutron generator 52 disposed within the neutron source shielding cavity 51. Wherein the material composition detection apparatus 100 is configured such that neutrons emitted by the neutron generator 52 irradiate the material in the conveyor channel 31 to emit characteristic rays, and the detector 22 is configured to detect the characteristic rays to detect the types and contents of elements contained in the material. The specific principles of material analysis based on neutron activation will be understood by those skilled in the art and will not be described in detail herein. In some embodiments, the characteristic ray may be a characteristic gamma ray.
The transmission belt channel assembly 30 is located between the detector shielding assembly 20 and the neutron source shielding assembly 40 in the first direction, so that neutrons emitted by the neutron generator 52 in the neutron source shielding assembly 40 are conveniently emitted to materials on the transmission belt 200 of the transmission belt channel assembly 30 to emit characteristic rays, then the characteristic rays are detected by the detector 22 in the detector shielding assembly 20, the detection flow of the material element by the material element detection device 100 can be completed relatively quickly, and the detection speed of the material element detection device 100 is improved.
According to the material component detection device 100 provided by the embodiment of the invention, the detector shielding assembly 20, the transmission channel assembly 30 and the neutron source shielding assembly 40 are sequentially stacked and arranged in the mounting frame 10 along the first direction, and the neutron source mounting assembly 50 mounts the neutron generator 52 in the neutron source shielding assembly 40, so that the overall structural compactness can be improved, the radiation shielding effect of the material component detection device 100 is improved, the safety and the controllability of radiation are facilitated, the working safety of the device are improved, and the stacked and arranged mode is convenient for maintaining and overhauling all the assemblies, so that the service life of the device is prolonged.
The specific structure of each component of the material composition detecting apparatus 100 according to some embodiments of the present invention will be described below with reference to the accompanying drawings.
In some embodiments of the present invention, as shown in fig. 2, 4, 7 and 9, the detector shield assembly 20 includes a plurality of detector channel straps 23, a detector support plate 24 and two first shield matrix sets 25. The probe channel strap 23 includes a first end strap 231 and first side straps 232 disposed on two sides of the first end strap 231 along a second direction (e.g., a left-right direction as shown in fig. 1), where the plurality of probe channel straps 23 are stacked along a third direction (e.g., a front-rear direction as shown in fig. 1) and detachably connected, and adjacent probe channel straps 23 may be connected by screws, bolts, or the like, where the third direction intersects with the first direction and the second direction in two pairs, and for example, the first direction, the second direction, and the third direction may be perpendicular to each other.
The detector support plate 24 is used to reflect neutrons penetrating the material. The detector support plate 24 is disposed between the two first side access plates 232 and spaced apart from the first end access plate 231, in other words, the plurality of detector channel access plates 23 in a stacked arrangement generally form a U-shaped structure, the detector support plate 24 is disposed in a U-shaped space enclosed by the U-shaped structure and covers an opening of the U-shaped space, so that the detector support plate 24 and the detector channel access plates 23 cooperate to define a first mounting channel 241, the first mounting channel 241 penetrates in a third direction, and the detector 22 is mounted on the detector support plate 24.
In some embodiments, the detector support plate 24 is made of a polyethylene-containing material that facilitates reflection of neutrons penetrating the material, thereby enhancing neutron flux at the material, and thus enhancing the characteristic ray intensity at the material, facilitating improved detection efficiency of the detector 22. And the detector supporting plate 24 is made of polyethylene-containing materials, so that strong supporting strength can be improved for the detector 22, and the installation stability of the detector 22 is enhanced.
The first mounting channel 241 is opposite the conveyor channel assembly 30 in a first direction such that the detector shield cavity 21 is opposite the conveyor channel 31 in the first direction. As shown in fig. 7, by increasing or decreasing the number of layers of the probe passage access plates 23, the lengths of the first mounting passage 241 and the probe shielding cavity 21 can be changed, so as to adapt to the situation that the widths of the conveyor belts 200 are different in different application scenarios, and improve the structural expansibility of the material component detection device 100. Wherein the conveyor belt 200 may be a belt.
The two first shielding matrix groups 25 are arranged in the first mounting channel 241 at a distance to define a detector shielding cavity 21 between the two first shielding matrix groups 25 for accommodating the detector 22, capable of functioning as shielding radiation in the third direction. The first shielding base group 25 includes a plurality of first shielding bases 251 arranged in a stacked manner, makes it easier for the plurality of first shielding bases 251 to be fitted into the first mounting channels 241, and facilitates flexible adjustment of the shape and size of the first shielding base 251 as required according to the shape and size of the first mounting channels 241.
The first shielding substrate 251 may have a block shape or a plate shape, that is, the shape of the first shielding substrate 251 is not limited; the plurality of first shielding substrates 251 may be stacked in the first direction, or may be stacked in the second direction or the third direction, that is, the stacking direction of the first shielding substrates 251 is not limited, and the first shielding substrates 251 may be stacked into the first shielding substrate group 25 and the detector shielding cavity 21 may be defined.
In some embodiments where the detector shielding assembly 20 includes a plurality of detector channel access plates 23, a detector support plate 24, and two first shielding base groups 25, as shown in fig. 2, 4, 7, and 9, the detector support plate 24 is provided with a mounting groove 242 notched toward the detector shielding cavity 21, a shielding cylinder 243 is provided in the mounting groove 242, the shielding cylinder 243 is used for shielding external radiation, the detector 22 is mounted in the shielding cylinder 243, and both the shielding cylinder 243 and the detector 22 are spaced apart from the bottom wall of the mounting groove 242 by a predetermined gap.
For example, as shown in fig. 4, the outer circumferential surface of the shielding cylinder 243 is provided with an outer protrusion, and the inner circumferential surface of the mounting groove 242 is provided with a supporting surface for supporting the outer protrusion of the shielding cylinder 243, thereby realizing the supporting and limiting of the shielding cylinder 243 in the mounting groove 242. Meanwhile, the outer protrusion of the shielding cylinder 243 is supported on the supporting surface of the mounting groove 242, so that the shielding cylinder 243 is separated from the bottom wall of the mounting groove 242 by a predetermined gap, and the detector 22 mounted on the shielding cylinder 243 can be separated from the bottom wall of the mounting groove 242 by a predetermined gap, thereby being beneficial to reducing the pressure of the shielding cylinder 243 and the detector 22 on the bottom wall of the mounting groove 242, reducing the deformation of the detector supporting plate 24 and improving the structural strength of the detector shielding assembly 20.
In some embodiments, the shielding cylinder 243 may be made of a material containing lead or bismuth to shield the detector 22 from interference of external rays, thereby improving the accuracy of the detection of the detector 22. The shielding cylinder 243 may be a cylinder, a square cylinder, or the like, and the present invention is not limited thereto, and the shielding cylinder 243 may be configured to surround the detector 22 in the circumferential direction so as to shield external rays.
In some embodiments of the present invention, as shown in FIGS. 4-5, a neutron absorbing plate 244 is disposed between the detector 22 and the detector support plate 24, neutron absorbingThe plate 244 serves to absorb neutrons penetrating the material, reducing the likelihood of the neutrons striking the detector 22, and protecting the detector 22. For example, neutron absorber plate 244 may be boron carbide (B) 4 C)。
In some embodiments where the detector shield assembly 20 includes a plurality of detector channel straps 23 and two first shield matrix groups 25, as shown in fig. 2, 4, 7 and 9, a channel liner 26 is provided between the first shield matrix groups 25 and the first side straps 232 to ensure that the first mounting channels 241 are free of gaps and to enhance the shielding of the detector shield assembly 20 from radiation.
In some embodiments where the detector shielding assembly 20 includes two first shielding matrix groups 25, as shown in fig. 2-4 and 8, the detector shielding assembly 20 further includes a limiting member 27, where the limiting member 27 abuts between the two first shielding matrix groups 25, limiting the installation position of the first shielding matrix groups 25 in the first installation channel 241, so as to ensure that the two first shielding matrix groups 25 cannot be greatly moved in the third direction to press against the detector 22, thereby making the structural reliability of the detector shielding assembly 20 higher.
It should be noted that, when the number of the probe passage bonding plates 23 is adaptively adjusted according to the width of the conveyor belt 200 to adjust the size of the probe shielding cavity 21 along the third direction, the size of the limiting member 27 along the third direction may be adaptively adjusted to satisfy the limiting effect on the two first shielding matrix groups 25.
In some embodiments where the detector shield assembly 20 includes a plurality of detector channel access plates 23, as shown in fig. 2, 4, 7, and 9, at least one side of the plurality of detector channel access plates 23, opposite the detector shield cavity 21, of the first end access plates 231 in the third direction is provided with a support protrusion 233, the first end access plate 231 adjacent to the first end access plate 231 is provided with a support engagement portion 234, and the support protrusion 233 is supported on a side of the support engagement portion 234 remote from the detector shield cavity 21. When the detector 22 needs to be installed or overhauled, the first end access plate 231 opposite to the detector shielding cavity 21 can be taken out along the direction away from the detector 22 along the third direction, so that the detector 22 is directly exposed to the outside, the detector 22 is conveniently taken out or put in, and the detector 22 is more convenient to overhaul.
In some embodiments of the present invention, as shown in fig. 2, 4, 7 and 10, the conveyor belt channel assembly 30 includes two channel brackets 32, a bottom support 33 and two inclined supports 34. Wherein the two channel brackets 32 are spaced apart along a third direction that intersects both the first direction and the second direction. The bottom support 33 is located between the two channel brackets 32 and opposite the neutron source shielding cavity 51 in the first direction, and the two inclined supports 34 are respectively located between the bottom support 33 and the two channel brackets 32, so that the two inclined supports 34 and the bottom support 33 cooperate to define the conveyor channel 31. While the height of the channel holder 32 in the first direction influences the overall height of the conveyor channel 31. Therefore, the channel brackets 32 with different heights can be selected according to the different heights of the matched conveyor belts 200, so that the height of the conveyor belt channel 31 can be adjusted to adapt to the situation that the conveyor belts 200 and materials have different heights under different application scenes.
Further, the bottom support 33 includes a passage moderating plate 331 and passage supporting plates 332 provided at both sides of the passage moderating plate 331 in the second direction, respectively. The channel supporting plate 332 is used for supporting the conveying belt 200 and the material, and the channel slowing plate 331 can slow fast neutrons emitted by the neutron generator 52 into thermal neutrons, so that the neutron irradiates the material to emit characteristic rays, and further the detection work of the detector 22 on the characteristic rays is realized to detect the types and the contents of the material elements. The channel support plate 332 and the channel slowing plate 331 cooperate to realize bottom support of the conveyor belt 200, which is beneficial to improving the support strength and reducing the wear of the conveyor belt 200.
For example, the channel slowing plate 331 may be made of graphite, so as to slow down the wear speed of the conveyor belt 200, and different materials and thicknesses of the channel slowing plate 331 may be selected according to the measured materials, so as to achieve a better slowing effect. For example, the channel bracket 32, the channel supporting plate 332 and the inclined supporting member 34 may be made of polyethylene, so that the strength is high, the main supporting function is provided for the conveyor belt 200, the conveyor belt 200 is prevented from falling down, and the working reliability of the material component detecting device 100 is improved. Meanwhile, the channel support 32, the channel support plate 332 and the inclined support 34 are made of polyethylene materials, so that fast neutrons can be slowed down into thermal neutrons, the neutron slowing efficiency is further improved, neutrons penetrating through materials can be reflected, neutron flux in the transmission belt channel assembly 30 is improved, the characteristic ray intensity of the materials is further improved, and the detection efficiency of the detector 22 is improved.
The inclined support 34 has inclined support surfaces 341, the inclined support surfaces 341 being inclined upward and in a direction away from the bottom support 33, the two inclined support surfaces 341 defining the conveyor belt channel 31 in cooperation with the bottom support 33 to effect the conveyance of the conveyor belt 200. The two inclined supporting surfaces 341 and the bottom supporting piece 33 are in direct contact with the conveying belt 200, so that the limiting effect on the conveying belt 200 is improved, and replacement of worn contact surface parts of the conveying belt 200 is facilitated.
In some embodiments where the conveyor belt channel assembly 30 includes a diagonal support member 34, the diagonal support member 34 may include a support member body 342 and at least one internal support plate 343, as shown in fig. 2, 4, 7, and 10. The support body 342 has a cavity 344 extending along the second direction, and the cavity 344 can reduce the moderating effect on neutrons to a certain extent, so that the moderated neutrons can retain energy capable of penetrating the material, so that the material emits characteristic rays capable of being detected by the detector 22, and the detection capability of the material component detection device 100 on the material is enhanced. The inner support plate 343 is disposed in the cavity 344 and connected with the wall surface of the cavity 344, which plays a role of inner reinforcing support and improves the stability of the inclined support surface 341.
In some embodiments in which the height of the conveyor belt channel 31 is adjustable, as shown in fig. 1-3 and 6-8, the mounting frame 10 may include a plurality of columns 11, where the columns 11 include a first column 111, a second column 112, and a third column 113 sequentially arranged along a first direction, and the second column 112 is detachably connected to the first column 111 and the third column 113, respectively, and both sides of the channel bracket 32 along a second direction are connected to the first column 111, respectively, by means including, but not limited to, screws, bolts, and the like. Through the second post 112 can dismantle, be convenient for change along the different second post 112 of first direction length to change the space that the mounting bracket 10 was used for holding the transmission band passageway subassembly 30 on the first direction, and then can change the space along first direction of the transmission band passageway 31 that defines, the condition of the material height difference under the adaptation different application scenes of being convenient for improves the structure expansibility of material composition detection device 100. In addition, the channel bracket 32 is not required to be detached from the first column 111 in the adjustment process, and only the second column 112 is required to be replaced, so that the operation is more convenient.
In some embodiments of the present invention, as shown in fig. 2 and fig. 6-7, at least one side of the conveyor channel 31 along the second direction is provided with a conveyor idler 18, where the conveyor idler 18 is used to support the conveyor 200, and the height of the conveyor idler 18 along the first direction is adjustable, so as to adapt to the situation of different heights of materials in different application scenarios.
In some embodiments provided with the conveyor idler 18, as shown in fig. 1-3 and fig. 6-7, two sides of the mounting frame 10 along the second direction are respectively provided with a side shielding cover 12, and the material of the side shielding cover 12 comprises a boron-containing polyethylene material to reflect neutrons leaking outwards from the end opening of the conveyor channel 31, so as to enhance the effect of neutron leakage prevention, reduce the radiation dose around the material component detection device 100, and improve the use safety of the material component detection device 100.
The side shield 12 includes an end shield plate 121 and two side shield plates 122. Wherein the end shield 121 is located on a side of the conveyor belt tunnel 31 remote from the neutron source shielding assembly 40 in a first direction and the end shield 121 is inclined away from the conveyor belt tunnel 31 and near the neutron source shielding assembly 40 in the first direction so as to reflect more neutrons to enhance protection against neutron leakage, specifically, at an angle greater than 0 ° and less than or equal to 30 °, for example, an angle of 15 ° may be selected. For example, as shown in fig. 6, the end shield plate 121 provided on the left side of the mount frame 10 is inclined leftward and downward by an angle of 15 °. The two side shield plates 122 are provided on both sides of the conveyor path 31 in the third direction, respectively.
When the material composition detecting apparatus 100 is operated, there is a risk that the radiation at the conveyor belt path 31 diverges outward through the openings on both sides in the second direction, but the design of the side shield 12 shields the area near the opening of the conveyor belt path 31, effectively reducing the amount of outward radiation. And further, the opening size of the side shielding cover 12 is reduced by the inclined arrangement of the end shielding plate 121, so that the outward radiation quantity of the transmission belt channel 31 is further reduced, and the working process is safer and more reliable.
In some embodiments of the present invention, as shown in fig. 2, 4, 7 and 11, the neutron source shielding assembly 40 includes a plurality of neutron source shielding straps 42, the neutron source shielding straps 42 include second end straps 421 and second side straps 422 respectively provided at both sides of the second end straps 421 in a second direction, the plurality of neutron source shielding straps 42 are arranged in a third direction in a stacked and detachable manner to define a mounting channel 41 between the second side straps 422 at both sides, the mounting channel 41 is perforated in the third direction, and the third direction intersects the first direction and the second direction two by two, for example, the first direction, the second direction and the third direction may be perpendicular to each other. Wherein adjacent neutron source shielding straps 42 may be connected by screws, bolts, or the like.
The mounting channel 41 is opposite the conveyor channel assembly 30 in a first direction such that the neutron source mounting assembly 50 is opposite the conveyor channel 31 in the first direction. As shown in fig. 7, by increasing or decreasing the number of laminations of the neutron source shielding butt strap 42, the lengths of the installation channel 41 and the neutron source shielding cavity 51 can be changed, so as to adapt to the situation that the widths of the transmission belts 200 are different in different application scenarios, improve the structural expansibility of the material component detection device 100, and better adapt to the requirements of different application scenarios.
In some embodiments where the neutron source shielding assembly 40 includes a plurality of neutron source shielding access panels 42, as shown in fig. 2, 4, 7 and 11-14, a channel liner side panel 43 is disposed between the neutron source mounting assembly 50 and the second side access panel 422 to ensure that no gaps are present on the sides of the mounting channel 41 and to enhance the shielding effect of the neutron source shielding assembly 40 on radiation.
In some embodiments, as shown in fig. 2, 4, 7 and 11, a channel liner end plate 44 is provided between the neutron source mounting assembly 50 and the second end strap 421 to ensure that the end of the mounting channel 41 facing the second end strap 421 is free of gaps, thereby improving the radiation shielding effect of the neutron source shielding assembly 40.
In addition, the channel liner end plate 44 may be provided with rails 57 extending in a third direction, and the neutron source mounting assembly 50 may be provided with rollers 58 slidable along the rails 57 to enable the neutron source mounting assembly 50 to be retractably mounted within the mounting channel 41. When the neutron generator 52 is required to be installed or overhauled, the neutron source installation assembly 50 can be pushed into the neutron source shielding assembly 40 through the cooperation of the guide rail 57 and the roller 58, or the neutron source installation assembly 50 can be pulled out of the neutron source shielding assembly 40, so that the neutron source installation assembly 50 is convenient to install or overhaul, the neutron source installation assembly 50 is smooth to pull, and the operation is convenient. Of course, the manner of the drawing and matching of the neutron source mounting assembly 50 and the mounting channel 41 includes, but is not limited to, only the drawing and matching effect is required.
In some embodiments where the neutron source shielding assembly 40 includes a plurality of neutron source shielding straps 42, as shown in fig. 2, 4, 7, and 11-14, the neutron source mounting assembly 50 includes a neutron source support plate 53 and two second shielding matrix sets 54. Wherein, neutron source support plate 53 locates in installing channel 41, neutron generator 52 installs in the side of neutron source support plate 53 facing away from second end access plate 421. When the shape and size of the mounting channel 41 are changed, for example, by increasing or decreasing the number of stacks of the neutron source shielding butt straps 42 to change the length of the mounting channel 41, the size and shape of the neutron source support plates 53 can be adjusted to accommodate the change of the mounting channel 41, which is beneficial to improving the fit of the neutron source shielding assembly 40 and the neutron source mounting assembly 50, so that the material component detection device 100 is improved to better accommodate the requirements of different application scenarios. The neutron source support plate 53 may include a plate body or a plurality of plate bodies to provide support for other components of the neutron source mounting assembly 50.
The two second shielding matrix groups 54 are arranged at intervals on the neutron source support plate 53 to define a neutron source shielding cavity 51 between the two second shielding matrix groups 54 to accommodate the neutron generator 52, capable of functioning to shield radiation in a third direction. The second shielding base group 54 includes a plurality of second shielding bases 541 arranged in a stacked manner. The plurality of second shielding bases 541 are made easier to mount to the neutron source support plate 53, and the shape and size of the second shielding bases 541 required are flexibly adjusted according to the shape and size of the neutron source support plate 53.
The second shielding substrate 541 may have a block shape or a plate shape, that is, the shape of the second shielding substrate 541 is not limited; the plurality of second shielding substrates 541 may be stacked in the first direction, or may be stacked in the second direction or the third direction, that is, the stacking direction of the first shielding substrates 251 is not limited, and the first shielding substrates 251 may be stacked into the first shielding substrate group 25 and the neutron source shielding cavity 51 may be defined.
As shown in fig. 12 to 14, for example, the second shield base 541 on the front side is plate-shaped and laminated in the front-rear direction to form the second shield base group 54; the rear second shielding base 541 is block-shaped and laminated in the up-down direction to form a second shielding base group 54, and a neutron source shielding cavity 51 is defined between the two second shielding base groups 54. The second shielding matrix set 54 is used for shielding neutrons, so that the radiation quantity of neutrons along the front-rear direction can be reduced, and the working process is safer and more reliable.
In some embodiments where the neutron source shielding assembly 40 includes a plurality of neutron source shielding straps 42, as shown in fig. 2, 4, 7, and 12-14, the neutron source mounting assembly 50 further includes a neutron reflector 55 and a radiation shield 56. Wherein a neutron reflector 55 is mounted to the neutron source support plate 53, the neutron reflector 55 defining a receiving slot 551 open toward the conveyor channel assembly 30, the neutron reflector 55 being configured to reflect neutrons within the receiving slot 551 to reduce neutron leakage; the ray shielding member 56 is disposed on the neutron reflection member 55 and sleeved on the target source of the neutron generator 52, so as to shield external gamma rays and self gamma rays of the neutron generator 52, and enable a gamma ray detection result generated by the neutron bombarding material to be more accurate. For example, the neutron reflector 55 is made of a graphite-containing material, and the radiation shield 56 is made of a lead-containing material.
In some embodiments of the present invention, as shown in fig. 4 and 12-14, neutron generator 52 is a deuterium-deuterium fusion reaction neutron generator (DD neutron generator). The radiation source of the DD neutron generator can be controlled to be shut down to control whether neutrons are emitted or not, resource waste and radiation injury caused by continuous neutrons emitted due to incapability of shutting down are avoided, the neutron loss risk is effectively reduced to improve the neutron utilization rate, the radiation is safe and controllable, the retired program of the DD neutron generator is simpler, and the material component detection device 100 is convenient to maintain and overhaul in the use field.
In some embodiments of the present invention, as shown in fig. 1-8, the mounting frame 10 includes a plurality of uprights 11, a load-bearing skeleton 14, a first load-bearing beam 15, a second load-bearing beam 16, and a support 17. Wherein, a plurality of stands 11 are spaced apart and are arranged and at least two stands 11 are connected through stand connecting piece 13, can make between the stands 11 relatively fixed, guarantee the overall structure stability of mounting bracket 10. For example, in some embodiments including four columns 11 and six column connectors 13, as shown in fig. 6 to 7, four columns 11 are arranged at four vertices of a rectangle, two column connectors 13 are above the other four column connectors 13, two columns 11 are respectively connected to two ends of the upper two column connectors 13 along the front-rear direction, four column connectors 13 below are arranged in a rectangle to connect the four columns 11, and the connection manner is a bolt connection, so that shaking can be reduced to ensure structural stability of the mounting frame 10.
In some embodiments, the load-bearing framework 14 may be coupled to at least one of the uprights 11 and the upright connectors 13 to improve the structural stability of the load-bearing framework 14 and to improve the load-bearing capacity of the load-bearing framework 14.
And the bearing skeleton 14 and at least part of the neutron source shielding assembly 40 are embedded and installed, for example, in some embodiments, as shown in fig. 8, the cross section of the bearing skeleton 14 perpendicular to the second direction is in an inverted T shape, the vertical part along the first direction in the inverted T shape is embedded between two adjacent neutron source shielding butt straps 42 of the neutron source shielding assembly 40, and the horizontal part along the third direction in the inverted T shape is supported at the lower side of the neutron source shielding assembly 40, so that the deformation degree of the material component detection device 100 due to self gravity during long-term use can be reduced, and the structural stability of the material component detection device 100 is ensured.
As shown in fig. 6, two ends of the first bearing beam 15 are respectively connected with two upright posts 11, and the detector shielding assembly 20 is connected with the first bearing beam 15, so that the supporting effect of the first bearing beam 15 on the detector shielding assembly 20 is realized, the possibility of falling of the detector shielding assembly 20 in the working process is reduced, and the structural stability of the detector shielding assembly 20 on the mounting frame 10 is ensured.
As shown in fig. 6, two ends of the second bearing beam 16 are respectively connected with the two upright posts 11, and the transmission belt channel assembly 30 is connected with the second bearing beam 16, so that the supporting effect of the second bearing beam 16 on the transmission belt channel assembly 30 is realized, the possibility that the transmission belt channel assembly 30 falls down in the working process is reduced, and the structural stability of the transmission belt channel assembly 30 on the mounting frame 10 is ensured. Further, the above connection means include, but are not limited to, screw, bolt, and the like.
In some embodiments, as shown in fig. 7, at least one of the positions between the detector shielding assembly 20 and the upright 11, between the neutron source shielding assembly 40 and the upright 11, and between the conveyor channel assembly 30 and the upright 11 is provided with a supporting portion 17, so that no relative displacement along the second direction occurs between the mounting frame 10 and the detector shielding assembly 20, between the mounting frame 10 and the neutron source shielding assembly 40, and between the mounting frame 10 and the conveyor channel assembly 30, thereby ensuring a radiation shielding effect, improving the structural stability of the material component detection device 100, and ensuring safer and more reliable working processes.
The following detailed description of the material composition detection apparatus 100 based on neutron activation analysis technology according to one embodiment of the present invention refers to the accompanying drawings, it being understood that the following description is illustrative only and is not to be construed as limiting the invention.
As shown in fig. 1 to 14, a material component detection device 100 based on neutron activation analysis technology according to an embodiment of the present invention includes a mounting frame 10, a detector shielding assembly 20, a transmission belt channel assembly 30, a neutron source shielding assembly 40, a neutron source installation assembly 50, and a housing 60, where the housing 60 may be a sheet metal housing with high strength, which is beneficial for protecting the material component detection device 100.
The mounting frame 10 includes uprights 11, side shields 12, upright connectors 13, a load-bearing skeleton 14, a first load-bearing beam 15, a second load-bearing beam 16, supports 17, conveyor idlers 18, and side shield mounting brackets 19. The upright 11 includes a first column 111, a second column 112, and a third column 113 sequentially arranged from bottom to top, and the side shielding cover 12 includes an end shielding plate 121 and a side shielding plate 122.
The detector shield assembly 20 includes a detector shield cavity 21, a detector 22, a detector channel strap 23, a detector support plate 24, a first shield matrix set 25, a channel liner 26, and a stop 27. Wherein the detector 22 is arranged in the detector shielding cavity 21. The probe passage access plate 23 includes a first end access plate 231 and a first side access plate 232, the first end access plate 231 corresponding to the probe shielding chamber 21 in the up-down direction is longer in the front-rear direction, the longer first end access plate 231 includes a support protrusion 233, support fitting portions 234 are provided on two first end access plates 231 adjacent to the longer first end access plate 231, the support protrusion 233 is supported above the support fitting portions 234, the longer first end access plate 231 is conveniently taken out upward, and convenience is provided for installation and maintenance of the probe 22. The detector support plate 24 and the detector channel access plate 23 cooperate to define a first mounting channel 241, the detector support plate 24 is provided with a mounting slot 242, and a shielding cylinder 243 and a neutron absorbing plate 244 are disposed within the mounting slot 242. The first shielding base group 25 is formed by stacking a plurality of first shielding bases 251.
The conveyor belt channel assembly 30 includes a conveyor belt channel 31, a channel bracket 32, a bottom support 33, and a diagonal support 34. Wherein the bottom support 33 includes a channel slowing plate 331 and a channel supporting plate 332. The inclined support 34 includes an inclined support surface 341, a support body 342, and an inner support plate 343, the support body 342 having a cavity 344.
Neutron source shielding assembly 40 includes a mounting channel 41, a neutron source shielding access panel 42, a channel liner side panel 43, and a channel liner end panel 44. Wherein the neutron source shielding access panel 42 includes a second end access panel 421 and a second side access panel 422.
The neutron source mounting assembly 50 includes a neutron source shielding chamber 51, a neutron generator 52, a neutron source support plate 53, a second shielding matrix set 54, a neutron reflector 55, a radiation shield 56, a rail 57, rollers 58, and a channel moderator plate support 59. The neutron generator 52 is a DD neutron generator, the neutron source supporting plate 53 includes a first plate 531, a second plate 532, and a third plate 533, and a base limiting block 534 and a component limiting block 535 are disposed at the third plate 533. The second shielding base group 54 is laminated by a second shielding base 541, and the neutron reflector 55 defines a receiving groove 551 that can receive the radiation shield 56.
The detector shielding assembly 20, the transmission band channel assembly 30 and the neutron source shielding assembly 40 are arranged in a stacked manner along the up-down direction, so that the material component detection device 100 is compact in structure and beneficial to improving the shielding effect on radiation. The detector shielding assembly 20 is located at the uppermost layer, the transmission belt channel assembly 30 is located at the middle layer, the neutron source shielding assembly is located at the lowermost layer, and the neutron source installation assembly 50 is located in the neutron source shielding assembly 40, so that neutrons emitted by the neutron generator 52 can bombard materials on the transmission belt 200 upwards, and then characteristic rays are emitted to be detected by the detector 22 at the upper layer, which is beneficial to realizing detection of the types and contents of the material components by the material component detection device 100, and achieving the detection purpose.
In the detector shielding assembly 20, a plurality of detector channel straps 23 are arranged in order in the front-rear direction and are connected by bolting to ensure the connection stability of the plurality of detector 22 straps. Under the condition that the widths of the transmission belts 200 are different in different application scenes, the number of the detector channel access plates 23 is changed, so that the detector shielding assembly 20 is favorable for adapting to the condition that the widths of the transmission belts 200 are different, and the structural expansibility of the detector shielding assembly 20 is high. The detector support plate 24 is made of polyethylene-containing material, can provide support strength for the shielding cylinder 243, and is beneficial to reflecting neutrons penetrating through the material, so that neutron flux of the conveyor belt channel assembly 30 is enhanced, and further, the characteristic ray intensity of the material is improved, and the detection efficiency of the detector 22 for detecting characteristic rays is improved. The two passageway lining plates 26 are respectively provided at the left and right sides of the first mounting passageway 241 to ensure that the first mounting passageway 241 has no gap in the left and right directions so as to achieve a better shielding effect.
Shielding cylinder 243The detector 22 is arranged in the shielding cylinder 243 in a suspending manner in the mounting groove 242, which is beneficial to reducing the deformation degree of the detector supporting plate 4 and prolonging the service life. Meanwhile, the shielding cylinder 243 is made of a material containing lead, and the shielding cylinder 243 is provided with the detector 22 and surrounds the detector 22 in the circumferential direction, so that the interference of external rays on the detector 22 can be reduced. Neutron absorber plate 244 is boron carbide (B) with a thickness of 8mm 4 C) And is disposed between the detector 22 and the detector support plate 24 to absorb neutrons penetrating the material to reduce neutrons striking the detector 22 and protect the detector 22.
The first shielding base 251 is stacked on the front end and the rear end of the first mounting channel 241 and forms two first shielding base groups 25, and the two first shielding base groups 25 are stopped by the limiting piece 27 to limit the space between the two first shielding base groups 25, so that the two first shielding base groups 25 are prevented from moving in the front-rear direction in opposite directions to squeeze the detector 22, and the safety of the detector 22 is ensured.
In the conveyor path assembly 30, the path support 32, the path support plate 332 and the inclined support 34 are made of polyethylene, so that the support strength of the conveyor path assembly 30 can be improved, fast neutrons emitted by the moderating neutron generator 52 are thermal neutrons to improve the moderating efficiency of neutrons, and neutrons penetrating through materials can be reflected to facilitate improvement of the detection efficiency of the detector 22. The channel supports 32 are designed to have different height gradients, so that the channel supports 32 with different heights for the material component detection device 100 can be replaced, the situation that the heights of materials are different in different application scenes can be conveniently adapted, and the structural expansibility of the conveyor channel assembly 30 is high. The cross section of the supporting member body 342 perpendicular to the second direction is a hollow triangle, and is supported by the inner supporting plate 343, which is beneficial to improving the stability of the inclined supporting member 34, and further enhancing the supporting effect on the conveyor belt 200. The design of the cavity 344 in the support body 342 retains energy capable of penetrating the material to emit characteristic rays for detection by the detector 22, which is beneficial for improving the working efficiency. The two inclined supporting surfaces 341 and the bottom supporting member 33 cooperate to define the conveyor belt channel 31, i.e. the two inclined supporting surfaces 341, the channel slowing plate 331 and the channel supporting plate 332 are all in contact with the conveyor belt 200, so that the parts after the contact surfaces are worn can be replaced. The channel slowing plate 331 is made of graphite and designed with a thickness gradient, and can be selected with different thicknesses according to different materials, so as to achieve a good slowing effect on the medium and reduce the abrasion of the transmission belt 200 to the channel slowing plate 331.
In the neutron source shielding assembly 40, a plurality of neutron source shielding straps 42 are orderly arranged in the front-rear direction and are connected by bolting so as to ensure the connection stability of the plurality of neutron source shielding straps 42. Under the condition that the widths of the transmission belts 200 are different in different application scenes, the neutron source shielding assembly 40 is high in structural expansibility by changing the number of the neutron source shielding butt straps 42, and is beneficial to adapting to the condition that the widths of the transmission belts 200 are different. The two channel lining side plates 43 are respectively arranged at the left and right sides of the installation channel 41 to ensure that the installation channel 41 has no gap along the left and right directions so as to achieve better shielding effect.
The channel lining end plate 44 is fixed at the bottom of the installation channel 41 by bolts, and the guide rail 57 and the component limiting block 535 are installed on the channel lining end plate 44, so that the bottom of the installation channel 41 is ensured to have no gap, and a better installation plane is provided for installing the guide rail 57 in the neutron source installation component 50, so that the neutron source shielding component 40 has better shielding effect and is easy to be matched with other components. Wherein the assembly stopper 535 restricts movement of the neutron source mounting assembly 50 on the rail 57 to prevent the neutron source mounting assembly 50 from sliding back and forth after being pushed into the neutron source shielding assembly 40 to affect the structural stability of the material composition detection device 100.
In the neutron source installation assembly 50, the guide rail 57 is fixed on the channel lining end plate 44 of the neutron source shielding assembly 40 through bolting and is manufactured through square steel cutting rather than angle steel welding, so that the accuracy of the guide rail 57 is guaranteed, and the guide rail 57 is not easy to bend and deform.
The neutron source support plate 53 comprises a first plate 531, a second plate 532 and a third plate 533, wherein the first plate 531 supports a second shielding matrix group 54 and the neutron generator 52 at the rear side and is connected with the bottom plate of the neutron generator 52 through bolts; the second plate 532 supports the first plate 531 and neutron reflector 55 and is mounted in a staggered snap fit with the third plate 533; the third plate 533 supports the front side of one second shielding base group 54 and the base stopper 534.
On the first plate 531, the neutron generator 52 is used for generating neutrons, and the second shielding matrix group 54 on the rear side is formed by laminating two block-shaped second shielding matrixes 541, so as to shield neutrons, reduce the radiation quantity on the rear side of the installation channel 41, and improve the safety of equipment. On the second plate 532, the radiation shielding member 56 is disposed in the accommodating groove 551 of the neutron reflector 55, and the radiation shielding member 56 is sleeved on the target source of the neutron generator 52, and the neutron reflector 55 is made of graphite-containing material, so that the effect of reflecting neutrons can be achieved, neutrons emitted by the neutron generator 52 can be controlled conveniently, leakage of neutrons is reduced, neutron utilization rate is improved, and working efficiency is improved. The radiation shield 56 is made of a material containing lead, and can reduce the influence of gamma rays from the outside and the neutron generator 52 itself on the measurement, so that the detection result of gamma rays generated by the detector 22 on the neutron bombarded material is more accurate. A channel slowing plate support 59 is arranged above the lead shielding cavity and is used for supporting a channel slowing plate 331 in the transmission channel assembly 30, so that the structural stability of the material component detection device 100 is improved.
On the third plate 533, one second shielding base group 54 on the front side is laminated by a plurality of plate-like second shielding bases 541 for shielding neutrons, reducing the radiation amount on the front side of the mounting passage 41, and improving the safety of the apparatus. The matrix limiting block 534 is located at the front side of the second shielding matrix set 54 at the front side and is fixedly connected with the third plate 533 through a bolt so as to limit the second shielding matrix set 54, prevent the second shielding matrix set 54 from being stressed and falling to the neutron reflector 55, and improve the structural stability of the neutron source installation assembly 50.
Rollers 58 are mounted at the bottoms of the second plate 532 and the third plate 533, the neutron source mounting assembly 50 slides in the neutron source shielding assembly 40 in cooperation with the guide rails 57, and when the neutron generator 52 needs to be mounted and maintained, the neutron source support plate 53 can be pulled by using relatively small force so that parts on the neutron source support plate 53 can enter and exit the mounting channel 41 without barriers, and the operation is simple, and the maintenance and the overhaul are convenient. The second plate 532 and the third plate 533 are mounted in a staggered and meshed manner to mutually borrow force, so that the second plate 532 and the third plate 533 are ensured to have the same movement direction when the neutron source support plate 53 receives horizontal force, namely, the neutron source mounting assembly 50 is pulled, and the movement stability of the neutron source support plate 53 is improved.
In the mounting frame 10, the ten bearing frameworks 14 and the neutron source shielding assembly 40 are installed in an embedded mode, as shown in fig. 11, the section of the bearing framework 14 is in an inverted T shape, the vertical portion in the up-down direction is embedded between the two second end butt straps 421, two ends in the left-right direction are connected with the upright post connecting pieces 13, the deformation degree of the material component detection device 100 caused by self gravity during long-term use can be reduced, and the structural stability of the material component detection device 100 is guaranteed.
The mounting frame 10 includes six column connectors 13 for connecting the columns 11, wherein two column connectors 13 located at the upper side are fixed to the plurality of first columns 111 by bolting, for example, as shown in fig. 6, two ends of the column connector 13 located at the left side of the upper side are respectively connected to the two first columns 111 along the front-rear direction of the corresponding side, and two ends of the column connector 13 located at the right side of the upper side are respectively connected to the two first columns 111 along the front-rear direction of the corresponding side, so as to prevent the two first columns 111 along the front-rear direction from moving relatively; the four upright post connecting pieces 13 located below are connected to the four third upright posts in a rectangular shape, as shown in fig. 8, the upright post connecting pieces 13 are respectively connected and fixed with the two adjacent third post bodies 113 through bolts, so that the two adjacent third post bodies 113 are prevented from moving relatively along the front-back direction or the left-right direction, the possibility of shaking of the installation frame 10 is reduced, and the stability of the installation structure of the installation frame 10 is guaranteed.
The first cylinder 111 and the third cylinder 113 are detachably connected through the second cylinder 112, the upper end of the second cylinder 112 is fixedly connected with the lower end of the first cylinder 111 through bolts, the lower end of the second cylinder 112 is fixedly connected with the upper end of the third cylinder 113 through bolts, and under the condition that materials are different in height in different application scenes, the space of the conveying belt channel 31 can be enlarged in height by changing the second cylinders 112 with different heights, so that the material component detection device 100 can adapt to materials with different heights, and the structural expansibility of the material component detection device 100 is improved.
The two first bearing beams 15 are arranged at intervals along the left-right direction, two ends of each first bearing beam 15 are respectively connected and fixed with two first columns 111 of the corresponding side along the front-rear direction through bolts, and the first bearing beams 15 are connected with the detector shielding assembly 20, so that the supporting effect on the detector shielding assembly 20 is realized, the possibility of shaking between the detector shielding assembly 20 and the mounting frame 10 is reduced, and the structural stability of the material component detection device 100 is improved.
The two second load-bearing beams 16 are connected with the plurality of upright posts 11, specifically, as shown in fig. 6, two ends of one second load-bearing beam 16 are respectively fixed with two third columns 113 arranged at intervals along the front-rear direction through bolting, and the second load-bearing beam 16 is connected with the conveyor belt channel assembly 30, which is beneficial to supporting the two channel brackets 32, reduces the possibility of shaking between the conveyor belt channel assembly 30 and the mounting frame 10, and improves the structural stability of the material component detection device 100.
The supporting parts 17 are arranged between the detector shielding assembly 20 and the four first columns 111, between the neutron source shielding assembly 40 and the four third columns 113 and between the transmission belt channel assembly 30 and the four third columns 113, so that relative movement can not occur along the left-right direction between the mounting frame 10 and the detector shielding assembly 20, between the mounting frame 10 and the neutron source shielding assembly 40 and between the mounting frame 10 and the transmission belt channel assembly 30, the structural stability of the material component detection device 100 is improved, and the material component detection device 100 is not easy to shake in the working process.
A conveying belt carrier roller 18 is fixed between the two third columns 113 which are spaced apart along the front-rear direction through bolt connection, namely, the two conveying belt carrier rollers 18 are respectively connected between the two third columns 113 and used for conveying the conveying belt 200 into the conveying belt channel 31, the height of the conveying belt carrier roller 18 is adjustable, the height of the conveying belt 200 into the conveying belt channel 31 is convenient to adjust, so that the condition of different heights of materials is adapted, the application range of the material component detection device 100 is improved, and the structural expansibility of the material component detection device 100 is improved.
The left and right sides of the mounting frame 10 are respectively provided with a side shielding mounting bracket 19, the side shielding mounting brackets 19 are mounted on the upright post connecting pieces 13 connecting the two first posts 111 so as to mount the side shielding cover 12, and the side shielding cover 12 comprises an end shielding plate 121 and two side shielding plates 122, wherein the position of the end shielding plate 121 is 15 degrees downwards and horizontally so as to reduce the radiation amount of the left and right areas of the transmission belt channel 31 and improve the safety of the material component detection device 100 in the working process. The side shielding cover 12 is made of a material containing boron-containing polyethylene, and can reflect neutrons to enhance the protection of the conveyor channel assembly 30 against neutron leakage, reduce radiation dose around the material component detection device 100, and improve the use safety of operators.
In addition, the outer shells 60 having high strength are provided above, in front of, and behind the detector shielding assembly 20, outside the side shields 12, in front of, and behind the neutron source shielding assembly 40, etc., so that the installation strength of the material component detecting device 100 can be improved to protect the entire material component detecting device 100. An openable sheet metal door is arranged on the front side of the neutron source shielding assembly 40, and a supporting plate is arranged on the front side of the sheet metal door, so that the neutron source installation assembly 50 can be conveniently pulled out or pushed into the neutron source shielding assembly 40, and the work of installation, overhaul and the like of the neutron generator 52 can be realized.
In the working process of the material component detecting device 100, the conveyor belt 200 is firstly passed through the conveyor belt channel 31 of the material component detecting device 100 along the left-right direction, the conveyor belt 200 is used for conveying materials into the conveyor belt channel 31, then the neutron generator 52 below is started to emit neutrons, the neutrons bombard the materials upwards and emit characteristic rays, the characteristic rays are emitted upwards and detected by the detector 22, and therefore the types and the contents of material elements are detected, and the detection work of the material component detecting device 100 is completed. The mode of matching the conveyor belt 200 with the material component detection device 100 is also beneficial to realizing continuous detection and analysis of materials and improving detection efficiency.
Other configurations and operations of the neutron activation analysis-based material composition detection apparatus 100 according to embodiments of the present invention are known to those of ordinary skill in the art and will not be described in detail herein.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be either fixedly connected, detachably connected, or integrally connected, for example; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention will be understood in specific cases by those of ordinary skill in the art.
In the description herein, reference to the terms "embodiment," "specific embodiment," "example," and the like, means that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, schematic representations of the above terms do not necessarily refer to the same embodiments or examples. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples.
While embodiments of the present invention have been shown and described, it will be understood by those of ordinary skill in the art that: many changes, modifications, substitutions and variations may be made to the embodiments without departing from the spirit and principles of the invention, the scope of which is defined by the claims and their equivalents.

Claims (17)

1. A neutron activation analysis technology-based material component detection device, comprising:
a mounting frame;
the detector shielding assembly is arranged on the mounting frame and defines a detector shielding cavity, and a detector is arranged in the detector shielding cavity;
a conveyor belt channel assembly mounted to the mounting frame and located on one side of the detector shield assembly in a first direction, the conveyor belt channel assembly defining a conveyor belt channel extending in a second direction, the conveyor belt channel for receiving a conveyor belt conveying material in the second direction, the second direction intersecting the first direction;
the neutron source shielding assembly is mounted on the mounting frame and located on one side, away from the detector shielding assembly, of the conveyor channel assembly in the first direction, and the neutron source shielding assembly defines a mounting channel;
The neutron source installation assembly is installed in the installation channel and matched with the neutron source shielding assembly to define a neutron source shielding cavity, and a neutron generator is arranged in the neutron source shielding cavity; wherein,
the material component detection device is configured to enable neutrons emitted by the neutron generator to irradiate the material in the transmission belt channel so as to emit characteristic rays, and the detector is used for detecting the characteristic rays;
the detector shield assembly includes:
the detector channel access plates comprise a first end access plate and first side access plates which are respectively arranged at two sides of the first end access plate along the second direction, the detector channel access plates are arranged in a stacked mode along a third direction and detachably connected, and the third direction is intersected with the first direction and the second direction in pairs;
the detector support plates are used for reflecting neutrons penetrating through materials, the detector support plates are arranged between the two first side access plates and are spaced apart from the first end access plates, a plurality of detector channel access plates which are arranged in a stacked mode form a U-shaped structure, the detector support plates are located in U-shaped spaces surrounded by the U-shaped structure and cover openings of the U-shaped spaces, so that the detector support plates and the detector channel access plates are matched to define a first installation channel, the first installation channel is communicated along the third direction, and the detector is installed on the detector support plates;
The two first shielding matrix groups are arranged in the first installation channel at intervals to define the detector shielding cavity between the two first shielding matrix groups, the first shielding matrix groups comprise a plurality of first shielding matrixes which are arranged in a stacked mode, a channel lining plate is arranged between the first shielding matrix groups and the first side access plates, and the channel lining plate is used for shielding gaps between the first shielding matrix groups and the first side access plates.
2. The neutron activation analysis technology-based material component detection device according to claim 1, wherein the detector support plate is provided with a mounting groove with a notch facing the detector shielding cavity, a shielding cylinder is arranged in the mounting groove and used for shielding external rays, the detector is arranged in the shielding cylinder, and the shielding cylinder and the detector are both spaced apart from the groove bottom wall of the mounting groove by a preset gap.
3. The neutron activation analysis technology-based material component detection device according to claim 1, wherein a neutron absorbing plate is arranged between the detector and the detector supporting plate, and the neutron absorbing plate is used for absorbing neutrons penetrating through the material.
4. The neutron activation analysis technology-based material composition detection device of claim 1, wherein the detector shielding assembly further comprises a stop member that is stopped between two of the first shielding matrix sets.
5. The neutron activation analysis technology-based material component detection device according to claim 1, wherein at least one side of the first end access panel, which is opposite to the detector shielding cavity, among the plurality of detector channel access panels is provided with a support protrusion, and the adjacent first end access panel is provided with a support mating portion, and the support protrusion is supported on a side of the support mating portion, which is away from the detector shielding cavity.
6. The neutron activation analysis technology-based material composition detection device of any one of claims 1-5, wherein the conveyor belt channel assembly includes:
the two channel brackets are spaced along a third direction, and the third direction is intersected with the first direction and the second direction in pairs;
the bottom support piece comprises a channel slowing plate and channel support plates which are respectively arranged at two sides of the channel slowing plate along the second direction, and the bottom support piece is positioned between the two channel brackets and opposite to the neutron source shielding cavity along the first direction;
The two inclined supporting pieces are respectively arranged between the bottom supporting pieces and the two channel brackets, each inclined supporting piece is provided with an inclined supporting surface, each inclined supporting surface faces upwards and inclines towards the direction away from the bottom supporting piece, and the two inclined supporting surfaces are matched with the bottom supporting pieces to define the channel of the conveying belt.
7. The neutron activation analysis technology-based material composition detection device of claim 6, wherein the inclined support comprises:
a support body having a cavity extending along the second direction;
and the inner supporting plate is arranged in the cavity and is connected with the cavity wall surface of the cavity.
8. The neutron activation analysis technology-based material composition detection device of claim 6, wherein the mounting frame comprises a plurality of posts, the posts comprising:
the first column, the second column and the third column are sequentially arranged along the first direction, the second column is detachably connected with the first column and the third column respectively, and the two sides of the channel support along the second direction are connected with the first column of the upright column respectively.
9. The neutron activation analysis technology-based material component detection device according to claim 1, wherein at least one side of the conveyor belt channel along the second direction is provided with a conveyor belt idler, the conveyor belt idler is used for supporting the conveyor belt, and the height of the conveyor belt idler along the first direction is adjustable.
10. The neutron activation analysis technology-based material component detection device of claim 9, wherein two sides of the mounting frame along the second direction are respectively provided with a side shielding case, and the material of the side shielding case comprises a boron-containing polyethylene material and includes:
an end shield positioned on a side of the conveyor belt channel away from the neutron source shielding assembly in the first direction, and inclined away from the conveyor belt channel in the second direction and toward the neutron source shielding assembly in the first direction;
and the two side shielding plates are respectively arranged at two sides of the transmission belt channel along the third direction.
11. The neutron activation analysis technology-based material composition detection device of claim 1, wherein the neutron source shielding assembly comprises:
The neutron source shielding butt straps comprise a second end butt strap and second side butt straps which are respectively arranged on two sides of the second end butt strap in the second direction, the neutron source shielding butt straps are arranged in a stacked mode in the third direction and are detachably connected to define an installation channel between the second side butt straps, the installation channel penetrates through in the third direction, and the third direction is intersected with the first direction and the second direction in a two-to-two mode.
12. The neutron activation analysis technology-based material composition detection device of claim 11, wherein a channel lining side plate is disposed between the neutron source mounting assembly and the second side access panel, the channel lining side plate being configured to block a gap between the neutron source mounting assembly and the second side access panel.
13. The neutron activation analysis technology-based material composition detection device of claim 11, wherein a channel liner end plate is disposed between the neutron source mounting assembly and the second end strap, the channel liner end plate being provided with a rail extending along the third direction, the neutron source mounting assembly being provided with rollers slidable along the rail.
14. The neutron activation analysis technology-based material composition detection device of claim 11, wherein the neutron source mounting assembly comprises:
the neutron source support plate is arranged in the mounting channel, and the neutron generator is mounted on one side of the neutron source support plate, which is opposite to the second end access plate;
and two second shielding matrix groups, wherein the two second shielding matrix groups are arranged on the neutron source support plate at intervals so as to define the neutron source shielding cavity between the two second shielding matrix groups, and the second shielding matrix groups comprise a plurality of second shielding matrixes which are arranged in a stacking way.
15. The neutron activation analysis technology-based material composition detection device of claim 14, wherein the neutron source mounting assembly further comprises:
a neutron reflector mounted to the neutron source support plate, the neutron reflector defining a receiving slot open to the conveyor channel assembly, the neutron reflector being configured to reflect neutrons within the receiving slot;
the ray shielding piece is arranged in the accommodating groove and sleeved on the target source of the neutron generator so as to shield external gamma rays and self gamma rays of the neutron generator.
16. The neutron activation analysis technology-based material composition detection device of any one of claims 1-5 and 7-15, wherein the neutron generator is a DD neutron generator.
17. The neutron activation analysis technology-based material composition detection device of claim 1, wherein the mounting frame comprises:
the plurality of upright posts are arranged at intervals, and at least two upright posts are connected through upright post connecting pieces;
the bearing framework is connected with the upright posts and/or the upright post connecting pieces, and at least part of the bearing framework and the neutron source shielding assembly are embedded and installed;
the two ends of the first bearing cross beam are respectively connected with the two upright posts, and the detector shielding assembly is connected with the first bearing cross beam;
the two ends of the second bearing cross beam are respectively connected with the two upright posts, and the conveying belt channel assembly is connected with the second bearing cross beam;
and a support part is arranged between the detector shielding assembly and the upright post, between the neutron source shielding assembly and the upright post and between the transmission belt channel assembly and the upright post.
CN202311162998.0A 2023-09-11 2023-09-11 Material component detection device based on neutron activation analysis technology Active CN116908226B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202311162998.0A CN116908226B (en) 2023-09-11 2023-09-11 Material component detection device based on neutron activation analysis technology

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202311162998.0A CN116908226B (en) 2023-09-11 2023-09-11 Material component detection device based on neutron activation analysis technology

Publications (2)

Publication Number Publication Date
CN116908226A CN116908226A (en) 2023-10-20
CN116908226B true CN116908226B (en) 2023-12-22

Family

ID=88365363

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202311162998.0A Active CN116908226B (en) 2023-09-11 2023-09-11 Material component detection device based on neutron activation analysis technology

Country Status (1)

Country Link
CN (1) CN116908226B (en)

Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0969280A2 (en) * 1998-07-02 2000-01-05 Gamma-Metrics Flexible multi-purpose modular assembly for a family of PGNAA bulk material analyzers
JP2008298574A (en) * 2007-05-31 2008-12-11 Nihon Medi Physics Co Ltd Radiation shield apparatus
CN101548160A (en) * 2006-08-11 2009-09-30 赛默飞世尔科技有限公司 Bulk material analyzer assembly including structural beams containing radiation shielding material
CN111141763A (en) * 2020-01-16 2020-05-12 散裂中子源科学中心 Multi-station switching high-precision second neutron beam switch
CN111870823A (en) * 2020-07-21 2020-11-03 广州医科大学附属肿瘤医院 Radiotherapy is with multi-functional organ protective equipment
CN113687408A (en) * 2021-08-25 2021-11-23 浙江省农业科学院 Collimator and device for constructing uniform irradiation field of rod-shaped radioactive source
CN114324430A (en) * 2022-03-07 2022-04-12 合肥金星智控科技股份有限公司 Detection device based on neutron activation
CN115798777A (en) * 2022-10-20 2023-03-14 中国原子能科学研究院 Gamma irradiation test device for simulating total dose effect of chip
CN116052918A (en) * 2023-01-06 2023-05-02 中科超睿(青岛)技术有限公司 Neutron source shielding system and neutron photographing equipment
CN116124812A (en) * 2022-12-09 2023-05-16 合肥金星智控科技股份有限公司 Material composition on-line detection system based on neutron generator
CN116203051A (en) * 2023-05-06 2023-06-02 无锡日联科技股份有限公司 Product internal defect detection equipment and detection method based on X-rays

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP6753659B2 (en) * 2015-09-18 2020-09-09 キヤノンメディカルシステムズ株式会社 Radiation detector and medical diagnostic imaging equipment
KR102187572B1 (en) * 2019-01-24 2020-12-07 한국원자력연구원 A security inspection device of detecting hazardous materials using radiation

Patent Citations (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0969280A2 (en) * 1998-07-02 2000-01-05 Gamma-Metrics Flexible multi-purpose modular assembly for a family of PGNAA bulk material analyzers
CN101548160A (en) * 2006-08-11 2009-09-30 赛默飞世尔科技有限公司 Bulk material analyzer assembly including structural beams containing radiation shielding material
JP2008298574A (en) * 2007-05-31 2008-12-11 Nihon Medi Physics Co Ltd Radiation shield apparatus
CN111141763A (en) * 2020-01-16 2020-05-12 散裂中子源科学中心 Multi-station switching high-precision second neutron beam switch
CN111870823A (en) * 2020-07-21 2020-11-03 广州医科大学附属肿瘤医院 Radiotherapy is with multi-functional organ protective equipment
CN113687408A (en) * 2021-08-25 2021-11-23 浙江省农业科学院 Collimator and device for constructing uniform irradiation field of rod-shaped radioactive source
CN114324430A (en) * 2022-03-07 2022-04-12 合肥金星智控科技股份有限公司 Detection device based on neutron activation
CN115798777A (en) * 2022-10-20 2023-03-14 中国原子能科学研究院 Gamma irradiation test device for simulating total dose effect of chip
CN116124812A (en) * 2022-12-09 2023-05-16 合肥金星智控科技股份有限公司 Material composition on-line detection system based on neutron generator
CN116052918A (en) * 2023-01-06 2023-05-02 中科超睿(青岛)技术有限公司 Neutron source shielding system and neutron photographing equipment
CN116203051A (en) * 2023-05-06 2023-06-02 无锡日联科技股份有限公司 Product internal defect detection equipment and detection method based on X-rays

Also Published As

Publication number Publication date
CN116908226A (en) 2023-10-20

Similar Documents

Publication Publication Date Title
CN101548160B (en) Bulk material analyzer assembly including structural beams containing radiation shielding material
US4243889A (en) Storage rack for elongated fuel assemblies
CN102089674A (en) Device for measuring physical quantities of nuclear materials and method of employing such a device
CN108417743A (en) Battery carrier module and its battery frame module
US8345813B2 (en) Apparatus, system and method for low profile translation of high level radioactive waste containment structure
CN116908226B (en) Material component detection device based on neutron activation analysis technology
CN102655029A (en) Ri manufacturing apparatus
US20130193328A1 (en) On-belt analyser system
WO2021031611A1 (en) Method for retrofitting in-line security inspection system
CN101335061B (en) Fuel Damage Delayed Neutron Detection Device
CN111627575A (en) Shielding assembly for reactor and shielding structure thereof
CN105460560B (en) For the positioner being positioned at horizontal bag A type frame on panoramic table
CN213368209U (en) Ray shielding structure
CN220709061U (en) X-ray inspection device radiation protection structure
CN220357820U (en) Transfer device and check out test set of radiation source
JP4473770B2 (en) Radioactive material storage facility
CN221303182U (en) Belt nondestructive inspection radiation protection device for belt conveyor
CN215198961U (en) Interception equipment and interception system
CN219017255U (en) Shielding structure of hot chamber and hot chamber
CN217999420U (en) Electric radiation protection door control device
CN211033971U (en) Single-row drum type wire body
CN220399661U (en) Safety inspection device
CN217994784U (en) High-efficient forest density measurement device
CN211348004U (en) Movable flaw detection radiation protection device and radiographic inspection equipment
CN103606388B (en) A kind of quick fixation structure of radiation-proof shield through-wall pipe insert and fast-assembling method

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant