Neutron analysis device

The neutron analyzer, connected by a polygonal column shield and fasteners, solves the installation problem of neutron analyzers for large equipment, improves assembly efficiency and stability, reduces transportation and installation difficulty, and enhances the versatility and flexibility of the device.

CN224189929UActive Publication Date: 2026-05-01SHENZHEN KEERDA INTELLIGENT EQUIP CO LTD
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Patent Information

Authority / Receiving Office
CN · China
Patent Type
Utility models(China)
Current Assignee / Owner
SHENZHEN KEERDA INTELLIGENT EQUIP CO LTD
Filing Date
2026-03-11
Publication Date
2026-05-01

AI Technical Summary

Technical Problem

Existing neutron analysis devices are difficult to install, transport, and maintain on large equipment, and lack convenient shielding structures.

Method used

A neutron analysis device was designed, including a support, a shielding assembly, a detector, and a neutron generator. The shielding assembly consists of multiple shielding bodies and fasteners. The design of the positioning part, mating part, and connecting part enables rapid positioning and locking connection. The shielding body adopts a polygonal column structure to improve assembly efficiency and connection stability.

Benefits of technology

It improves the assembly efficiency and connection stability of shielding components, avoids the decline in shielding effect due to assembly deviation, enhances the versatility and flexibility of the device, adapts to the needs of different radiation protection levels, and reduces material usage and environmental risks.

✦ Generated by Eureka AI based on patent content.

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Abstract

The utility model discloses a neutron analysis device, which relates to the technical field of radiation detection equipment, and comprises a support, a shielding assembly, a detector and a neutron generator, the shielding assembly and the support form a first shielding cavity, a second shielding cavity and a channel for a conveyor belt to pass through, the detector is arranged in the first shielding cavity, and the neutron generator is arranged in the second shielding cavity. The neutron generator is arranged in the second shielding cavity, the shielding assembly comprises a plurality of shielding bodies and a plurality of fasteners, each shielding body is provided with at least one of a positioning part and a matching part and a connecting part arranged at intervals with the positioning part and the matching part, and three of the plurality of shielding bodies are respectively a first shielding body, a second shielding body and a third shielding body; the positioning part of the first shielding body is in positioning connection with the matching part of the second shielding body; and the fastener is configured to lock and fix the connecting part of the first shielding body or the second shielding body and the corresponding connecting part of the third shielding body, so that the neutron analysis device is convenient to install.
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Description

Technical Field

[0001] This utility model relates to the field of radiation detection equipment technology, and in particular to a neutron analysis device. Background Technology

[0002] In the field of industrial material composition monitoring (such as cement), neutron activation analyzers have been widely used to achieve non-destructive, non-contact, and rapid component detection. Their working principle involves generating neutrons through a built-in Cf252 neutron source or neutron generator. These neutrons react with the analyte nuclides in the industrial material, generating gamma rays. A detector then captures and analyzes these gamma rays to obtain material composition information. Existing neutron shielding structures are mostly integrated, installation-free structures, which are convenient and practical for small-scale applications. However, for some large-scale equipment, integrated shielding structures present significant challenges in transportation, installation, and maintenance. Utility Model Content

[0003] The main purpose of this invention is to propose a neutron analysis device, which aims to solve the problem that existing neutron analysis devices are inconvenient to install.

[0004] To achieve the above objectives, the neutron analysis device proposed in this utility model includes a support, a shielding assembly, a detector, and a neutron generator. The shielding assembly and the support form a first shielding cavity, a second shielding cavity, and a channel between the first shielding cavity and the second shielding cavity for a conveyor belt to pass through. The detector is located in the first shielding cavity, and the neutron generator is located in the second shielding cavity.

[0005] The shielding assembly includes multiple shielding bodies and multiple fasteners. Each shielding body is provided with at least one of a positioning part and a mating part, as well as a connecting part spaced apart from the positioning part and the mating part. Three of the multiple shielding bodies are a first shielding body, a second shielding body, and a third shielding body. The positioning part of the first shielding body is positioned and connected to the mating part of the second shielding body. The fasteners are configured to lock and fix the connecting part of the first shielding body or the second shielding body to the connecting part corresponding to the third shielding body.

[0006] In one embodiment, the shield is configured as a polygonal column having multiple sides, with the positioning part, the mating part, and the connecting part disposed on different sides.

[0007] In one embodiment, the plurality of shields are in the shape of one or more of a quadrangular prism, a pentagonal prism, or a hexagonal prism.

[0008] In one embodiment, the positioning part is a limiting protrusion provided on the surface of the shield, the mating part is a slot provided on the surface of the shield, the connecting part is a mounting hole provided on the shield, the limiting protrusion is inserted into the slot, and the fastener passes through the mounting hole.

[0009] In one embodiment, the slot is a dovetail groove, and the shape of the limiting protrusion matches the shape of the dovetail groove.

[0010] In one embodiment, the limiting protrusion and slot extend along the length direction of the shield, and the mounting holes are located at both ends of the shield along its length direction.

[0011] In one embodiment, the channel is disposed through a first direction, and the shielding assembly includes a first shielding module formed by combining a plurality of shielding bodies. The plurality of shielding bodies of the first shielding module extend along a second direction intersecting the first direction to form the first shielding cavity. The thickness of the first shielding module decreases from the middle of the detector to both sides in the first direction.

[0012] In one embodiment, the number of shielding bodies located on both sides of the detector along the first direction decreases from the direction closer to the detector to the direction farther from the detector, so that the thickness of the first shielding module decreases along the third direction.

[0013] And / or, the first direction, the second direction, and the third direction are perpendicular to each other.

[0014] In one embodiment, the shielding assembly includes a second shielding module formed by combining a plurality of shielding bodies, wherein the plurality of shielding bodies of the second shielding module extend along the second direction to form the second shielding cavity, and the shielding assembly further includes a third shielding module disposed between the first shielding module and the second shielding module, wherein the third shielding module extends along the first direction and surrounds the first shielding module and the second shielding module to form the channel.

[0015] In one embodiment, the shielding body includes a shell and a shielding material disposed within the shell. The shell is made of fiberglass, and the shielding material is high-polyethylene powder and a boron-containing compound, wherein the boron content in the boron-containing compound is 3% to 20%.

[0016] The neutron analysis device proposed in this utility model includes a support, a shielding assembly, a detector, and a neutron generator. The shielding assembly and the support form a first shielding cavity, a second shielding cavity, and a channel between the first and second shielding cavities for a conveyor belt to pass through. The detector is located in the first shielding cavity, and the neutron generator is located in the second shielding cavity. The shielding assembly includes multiple shielding bodies and multiple fasteners. Each shielding body is provided with at least one of a positioning part and a mating part, as well as a connecting part spaced apart from the positioning part and the mating part. Three of the multiple shielding bodies are a first shielding body, a second shielding body, and a third shielding body. The positioning part of the first shielding body is positioned and connected to the mating part of the second shielding body. The fasteners are configured to lock and fix the connecting part of the first or second shielding body to the corresponding connecting part of the third shielding body.

[0017] This design allows for quick positioning and connection of multiple shielding elements within the shielding assembly via positioning and mating parts, followed by locking with fasteners. This effectively improves the assembly efficiency and connection stability of the shielding assembly. The positioning and mating parts ensure the relative positional accuracy between the shielding elements, preventing a decrease in shielding effectiveness due to assembly deviations. The fit between the connecting parts and fasteners further enhances the overall structural robustness, preventing loosening or displacement of the shielding assembly during long-term use. Furthermore, the modular design of multiple shielding elements facilitates replacement and assembly according to actual usage requirements, adapting to different radiation protection levels and enhancing the versatility and flexibility of the device. Attached Figure Description

[0018] To more clearly illustrate the technical solutions in the embodiments of this utility model or the prior art, the drawings used in the description of the embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are only some embodiments of this utility model. For those skilled in the art, other drawings can be obtained based on the structures shown in these drawings without creative effort.

[0019] Figure 1 A schematic diagram of an embodiment of the neutron analysis device provided by this utility model;

[0020] Figure 2 A schematic diagram showing the disassembled structure of an embodiment of the neutron analysis device provided by this utility model;

[0021] Figure 3 A schematic diagram of the structure of the first shielding module in one embodiment of the neutron analysis device provided by this utility model;

[0022] Figure 4 for Figure 3 A magnified view of the location indicated by arrow A in the middle;

[0023] Figure 5A schematic diagram of another embodiment of the neutron analysis device provided by this utility model;

[0024] Figure 6 A front view of the first shielding module in one embodiment of the neutron analysis device provided by this utility model;

[0025] Figure 7 A schematic diagram of the structure of the second shielding module in one embodiment of the neutron analysis device provided by this utility model;

[0026] Figure 8 A side view of an embodiment of the neutron analysis device provided by this utility model.

[0027] Explanation of icon numbers:

[0028] 100. Neutron analyzer; 100a. First shielding cavity; 100b. Second shielding cavity; 100c. Channel; 1. Support; 2. Shielding assembly; 21. Shielding body; 21a. First shielding body; 21b. Second shielding body; 21c. Third shielding body; 211. Positioning part; 2111. Limiting protrusion; 212. Fitting part; 2121. Slot; 213. Connecting part; 2131. Mounting hole; 22. First shielding module; 23. Second shielding module; 24. Third shielding module; 3. Detector; 4. Neutron generator.

[0029] The realization of the purpose, functional features and advantages of this utility model will be further explained in conjunction with the embodiments and with reference to the accompanying drawings. Detailed Implementation

[0030] The technical solutions of the present utility model will be clearly and completely described below with reference to the accompanying drawings of the embodiments. Obviously, the described embodiments are only some embodiments of the present utility model, and not all embodiments. Based on the embodiments of the present utility model, all other embodiments obtained by those of ordinary skill in the art without creative effort are within the protection scope of the present utility model.

[0031] It should be noted that if the embodiments of this utility model involve directional indicators (such as up, down, left, right, front, back, etc.), the directional indicators are only used to explain the relative positional relationship and movement of the components in a specific posture. If the specific posture changes, the directional indicators will also change accordingly.

[0032] Furthermore, if the embodiments of this utility model involve descriptions such as "first" or "second," these descriptions are for descriptive purposes only and should not be construed as indicating or implying their relative importance or implicitly specifying the number of technical features indicated. Therefore, a feature defined with "first" or "second" may explicitly or implicitly include at least one of those features. Additionally, the use of "and / or" or "and / or" throughout the text includes three parallel solutions. For example, "A and / or B" includes solution A, solution B, or a solution where both A and B are satisfied simultaneously. Furthermore, the technical solutions of the various embodiments can be combined with each other, but this must be based on the ability of those skilled in the art to implement them. When the combination of technical solutions is contradictory or impossible to implement, it should be considered that such a combination of technical solutions does not exist and is not within the scope of protection claimed by this utility model.

[0033] This utility model proposes a neutron analysis device 100.

[0034] Please see Figures 1 to 4 In one embodiment of this utility model, the neutron analysis device 100 includes a support 1, a shielding assembly 2, a detector 3, and a neutron generator 4. The shielding assembly 2 and the support 1 form a first shielding cavity 100a, a second shielding cavity 100b, and a channel 100c located between the first shielding cavity 100a and the second shielding cavity 100b for a conveyor belt to pass through. The detector 3 is disposed in the first shielding cavity 100a, and the neutron generator 4 is disposed in the second shielding cavity 100b. The shielding assembly 2 includes multiple shielding bodies 21 and multiple fasteners, each shielding body 21 having... The device includes at least one of a positioning part 211 and a mating part 212, and a connecting part 213 spaced apart from the positioning part 211 and the mating part 212. Three of the plurality of shields 21 are a first shield 21a, a second shield 21b, and a third shield 21c. The positioning part 211 of the first shield 21a is positioned and connected to the mating part 212 of the second shield 21b. Fasteners are configured to lock and fix the connecting part 213 of the first shield 21a or the second shield 21b to the corresponding connecting part 213 of the third shield 21c.

[0035] Understandably, in this embodiment, channel 100c is installed through the neutron analysis device 100, and a conveyor belt passes through channel 100c and is located between the neutron generator 4 and the detector 3 to transport industrial materials such as cement through channel 100c. After the conveyor belt delivers the industrial materials into channel 100c, the neutron generator 4 releases neutrons into channel 100c. The neutrons react with the nuclides to be tested in the industrial materials to generate gamma rays. The detector 3, which is positioned opposite to the neutron generator 4, captures the gamma rays and analyzes them to obtain the composition information of the materials. The first shielding cavity 100a and the second shielding cavity 100b, which are formed by the shielding assembly 2, respectively install the detector 3 and the neutron generator 4 to shield the radiation generated by the detector 3 and the neutron generator 4, preventing radiation leakage into the external environment, thereby effectively ensuring the personal safety of the operators and the normal operation of the surrounding equipment.

[0036] It should be noted that, in combination Figure 5 It can be seen that each shielding body 21 in the shielding assembly 2 has a connecting portion 213, and has at least one of a positioning portion 211 and a mating portion 212, that is, the shielding body 21 may have a positioning portion 211 or a mating portion 212, or the shielding body 21 may have a positioning portion 211 and a mating portion 212, such as Figure 3 and Figure 4 As shown, the three shielding bodies 21 in the shielding assembly 2 are defined as a first shielding body 21a, a second shielding body 21b, and a third shielding body 21c. The first shielding body 21a and the third shielding body 21c are each provided with a positioning part 211, a mating part 212, and a connecting part 213. The second shielding body 21b is provided with a positioning part 211 and a connecting part 213. The first shielding body 21a and the second shielding body 21b are positioned and connected via the positioning part 211 and the mating part 212. The connecting part 213 of the third shielding body 21c is connected to the connecting part 213 of the second shielding body 21b via fasteners, thereby fixing the three shielding bodies 21 together. Of course, the first shielding body 21a, the second shielding body 21b, and the third shielding body 21c can also be any three shielding bodies 21 in the shielding assembly 2 that have the aforementioned connection relationship; their positions and arrangement are not specifically limited here.

[0037] Furthermore, the positioning part 211 and the mating part 212 have various mating structures. For example, the positioning part 211 can be a protrusion, and the mating part 212 can be a groove adapted to the protrusion. When the first shield 21a and the second shield 21b are connected for positioning, the protrusion on the first shield 21a can be embedded in the groove on the second shield 21b, or the protrusion on the second shield 21b can be embedded in the groove on the first shield 21a. Through this concave-convex mating method, the initial positioning of the two shields 21 during the connection process is achieved, ensuring that the two can be quickly and accurately connected, avoiding positional deviations during installation, and laying a good foundation for subsequent fixed connection with fasteners. The positioning part 211 can also be a positioning pin, and the mating part 212 is a positioning hole adapted to the positioning pin. When the first shield 21a and the second shield 21b are connected, the positioning pin is inserted into the positioning hole, which can also achieve precise positioning.

[0038] Furthermore, the connecting part 213 and the fastener can have various structures. For example, the connecting part 213 can be set as a slot on the shield 21, and the two shields 21 can be fixedly connected by the cooperation of the fastener and the slot. Alternatively, the connecting part 213 can also be designed as a connecting lug formed by the outward extension of the edge of the shield 21. The lug has through holes for fasteners to pass through. After the two shields 21 are initially positioned by the positioning part 211 and the mating part 212, the fastener can be passed through the through holes on the corresponding lugs of the two shields 21 and tightened with nuts to achieve a stable connection between the two. The fastener can be in various forms such as bolts, screws, rivets or clips. In addition to connecting the shields 21, the fastener can also be used to connect the shields 21 to the bracket 1, the detector 3, and the neutron generator 4. Based on this, the specific structure of the positioning part 211, the mating part 212, the connecting part 213 and the fastener is not limited here, and can be adapted according to requirements.

[0039] This configuration allows for quick positioning and connection of the multiple shielding elements 21 of the shielding assembly 2 via the positioning part 211 and the mating part 212, and secure connection via fasteners, effectively improving the assembly efficiency and connection stability of the shielding assembly 2. The positioning part 211 and the mating part 212 ensure the relative positional accuracy between the shielding elements 21, preventing a decrease in shielding effectiveness due to assembly deviations. The mating of the connecting part 213 and the fasteners further enhances the overall structural robustness, making the shielding assembly 2 less prone to loosening or displacement during long-term use. Furthermore, the modular design of the multiple shielding elements 21 facilitates the replacement of shielding elements 21 of different thicknesses or materials according to actual usage requirements, adapting to different radiation protection levels and enhancing the versatility and flexibility of the device.

[0040] In one implementation, such as Figure 4 and Figure 5 As shown, the shielding body 21 is configured as a polygonal prism with multiple sides. The positioning part 211, the mating part 212, and the connecting part 213 are disposed on different sides. It is understood that making the shielding body 21 a polygon increases the number of its sides, thereby providing more space for the positioning part 211, the mating part 212, and the connecting part 213, and avoiding structural interference between components on the same side. In this embodiment, the shape of the shielding body 21 is not specifically limited. For example, when the shielding body 21 is a hexagonal prism, the positioning part 211 can be disposed on one side, the mating part 212 on the opposite side, and the connecting part 213 on an adjacent side. This layout allows each component to work independently during assembly without affecting each other. Besides a hexagonal prism, the shielding body 21 can also be configured as a triangular prism, a pentagonal prism, etc., and can be adapted according to requirements.

[0041] Furthermore, compared to traditional cylindrical or cubic shielding bodies, the polygonal column structure allows for a tighter fit when multiple shielding bodies 21 are joined together, reducing gaps and further enhancing the overall shielding effect. In addition, the polygonal side design facilitates the machining of positioning reference surfaces. During manufacturing, specialized fixtures can be used to precisely machine each side, ensuring the dimensional and positional accuracy of the positioning part 211, the mating part 212, and the connecting part 213, thereby guaranteeing the assembly consistency among multiple shielding bodies 21.

[0042] In one implementation, such as Figure 4 and Figure 5 As shown, the multiple shielding bodies 21 are shaped as one or more of square prisms, pentagonal prisms, or hexagonal prisms. It is understood that the shielding assembly 2 has multiple shielding bodies 21, and any shielding body 21 can be configured as a square prism, pentagonal prism, or hexagonal prism. The shapes of different shielding bodies 21 can also be flexibly combined according to actual assembly requirements and spatial layout. For example, in this embodiment, the multiple shielding bodies 21 include square prisms, pentagonal prisms, and hexagonal prisms. Some square prisms and pentagonal prisms 21 can achieve compact right-angle splicing, while some adopt hexagonal prism structures to increase the number and stability of splicing surfaces, better adapting to the complex internal spatial structure of the neutron analyzer 100. While achieving a stable connection between each shielding body 21, the gaps inside the shielding assembly 2 are minimized to effectively block radiation leakage.

[0043] Of course, in some other embodiments, the multiple shielding bodies 21 can be set as a single polygonal column, or they can be a combination of two or more polygonal columns. Whether it is a square prism, a pentagonal prism or a hexagonal prism, its planar side surface provides a stable installation foundation for the positioning part 211, the mating part 212 and the connecting part 213, making the processing and assembly of each functional component more convenient, which is conducive to ensuring the accuracy and reliability of the connection between the shielding bodies 21, thereby improving the shielding effectiveness and structural stability of the entire shielding assembly 2.

[0044] In one implementation, such as Figure 4 and Figure 5 As shown, the positioning part 211 is a limiting protrusion 2111 provided on the surface of the shield 21, the mating part 212 is a slot 2121 provided on the surface of the shield 21, and the connecting part 213 is a mounting hole 2131 provided on the shield 21. The limiting protrusion 2111 is inserted into the slot 2121, and the fastener passes through the mounting hole 2131. It can be understood that the shields 21 can be initially positioned by inserting the limiting protrusion 2111 into the slot 2121 to ensure the accurate relative position of adjacent shields 21, while the mounting hole 2131 provides a stable mounting channel 100c for fasteners (such as bolts, screws, etc.). During assembly, multiple shields 21 can be sequentially spliced ​​into a combined structure through the limiting protrusion 2111 and the slot 2121, and then the multiple combined structures can be connected by fasteners, thereby further improving the overall structural strength and stability. By first inserting and positioning multiple shielding bodies 21 and then connecting them with fasteners, the assembly process is simplified, the amount of fasteners used is reduced, and the problem of loose connection between shielding bodies 21 due to assembly errors can be effectively avoided.

[0045] In one implementation, such as Figure 4 As shown, slot 2121 is a dovetail groove, and the shape of the limiting protrusion 2111 matches the shape of the dovetail groove. It is understood that the dovetail groove structure has good guiding and self-locking properties. When the limiting protrusion 2111 is inserted into the dovetail groove, it can effectively constrain the adjacent shielding body 21, preventing lateral displacement or vertical misalignment during the splicing process. This shape-matching design makes the insertion fit between the shielding bodies 21 tighter, thereby further improving the accuracy and stability of the initial positioning.

[0046] In one implementation, such as Figure 5As shown, the limiting protrusion 2111 and the slot 2121 extend along the length direction of the shield 21, and the mounting holes 2131 are located at both ends of the shield 21 along its length direction. It can be understood that in this embodiment, the limiting protrusion 2111 and the slot 2121 extend along the length direction (i.e., the second direction) of the shield 21, enabling guidance and positioning on a longer contact surface. This significantly increases the mating area between adjacent shields 21, thereby significantly improving the overall rigidity of the plug-in structure. During the splicing operation, the operator can smoothly slide the limiting protrusion 2111 into the slot 2121 along the length direction. The entire process is smooth and the positioning is precise, effectively avoiding jamming or misalignment caused by uneven local force.

[0047] The mounting holes 2131 are located at both ends of the shield 21 along its length, allowing the fasteners to act on the ends of the shield 21. This not only facilitates fixing by applying force from both ends of the shield 21, ensuring a uniform distribution of the connection force along its length, but also effectively avoids the potential impact of setting the mounting holes 2131 in the middle of the shield 21 on its internal structure or shielding performance, thereby ensuring the long-term stability and reliability of the shielding structure of the entire neutron analyzer 100.

[0048] In one implementation, such as Figure 1 , Figure 2 , Figure 8 As shown, the channel 100c is arranged through the first direction, and the shielding component 2 includes a first shielding module 22 formed by combining multiple shielding bodies 21. The multiple shielding bodies 21 of the first shielding module 22 extend along a second direction intersecting the first direction to form a first shielding cavity 100a. The thickness of the first shielding module 22 decreases from the middle of the detector 3 to both sides in the first direction.

[0049] It should be noted that in this embodiment, the first direction is the conveying direction of the conveyor belt, the second direction is the extending direction of the detector 3 and the neutron generator 4, and the third direction is the height direction of the neutron analysis device 100. For ease of description, please refer to... Figure 1 In the following text, the first direction is set along the X-axis, the second direction along the Y-axis, and the third direction along the Z-axis by default. However, in some other embodiments of this utility model, the specific orientation (vertical or horizontal) of the first, second, and third directions, as well as whether the included angles between them are perpendicular, are not specifically limited.

[0050] The thickness direction of the first shielding module 22 is the third direction (Z-axis). Due to the divergent distribution of gamma rays within the first shielding module 22, if the analytical device adopts a square structure, the corners contribute very little to the actual shielding protection, but result in a large overall size and increased weight of the analyzer. Furthermore, excess shielding material may generate additional radioactive activated solid waste, leading to resource waste and safety risks. Therefore, the thickness of the first shielding module 22 is set to decrease gradually from the center of the detector 3 towards both sides in the first direction. This eliminates redundant corner portions that have no substantial effect on shielding protection, significantly reducing the amount of shielding material used and substantially lowering the size and weight of the analyzer, facilitating equipment installation and on-site deployment. On the other hand, precise control of the amount of shielding material used effectively avoids the generation of additional radioactive activated solid waste due to radiation, reducing subsequent treatment costs and environmental risks, thus balancing practicality and safety.

[0051] Since the thickness of the first shielding module 22 gradually decreases from the middle of the detector 3 to both sides in the first direction, the projection of the module in the second direction can present various shapes such as trapezoidal, arc, or triangle, or other smoothly transitioning or stepped decreasing shapes can also be adopted. The specific design can be optimized and adjusted according to the actual divergence angle and intensity distribution of gamma rays, and no specific restrictions are imposed here.

[0052] In one implementation, such as Figure 6 As shown, the number of shielding bodies 21 located on both sides of the detector 3 along the first direction decreases from the direction closer to the detector 3 to the direction farther away from the detector 3, so that the thickness of the first shielding module 22 decreases along the third direction. It can be understood that, in this embodiment, multiple shielding bodies 21 of the first shielding module 22 are stacked around the detector 3, and the number of shielding bodies 21 decreases the farther away from the detector 3 in the first direction. The shielding capability of the entire first shielding module 22 against diverging γ-rays exhibits a gradient decreasing distribution.

[0053] The core of this structure lies in precisely matching the attenuation characteristics of gamma rays: the intensity of gamma rays radiating outward from the vicinity of detector 3 usually decreases naturally with increasing distance. The energy and density of rays closer to detector 3 are higher, so a larger number of first shielding bodies 21a are needed to form a shielding layer with greater thickness to achieve efficient blocking. In the area far from detector 3, the intensity of rays has been significantly reduced, so the number of shielding bodies 21 and the shielding thickness are reduced accordingly. This can meet the basic shielding requirements, avoid excessive material consumption and unnecessary increase in the overall weight of the device, and further improve the compactness and economy of the device structure.

[0054] In one implementation, such as Figure 1As shown, the first direction, the second direction, and the third direction are perpendicular to each other. It can be understood that channel 100c is positioned along the first direction, the conveyor belt transports materials along the first direction, and detector 3 and neutron generator 4 extend along the second direction and are located on either side of channel 100c in the third direction; the third direction is the height direction of the device. This arrangement allows channel 100c, the conveyor belt, detector 3, and the shielding module to form an orderly structural cooperation. By adjusting the number of shielding bodies 21 in the first shielding module 22 in the first direction, the gradient change in radiation intensity is adapted. In the second direction, the symmetrical arrangement of detector 3 and neutron generator 4 improves detection accuracy. In the third direction, thickness control balances the shielding effect with the need for lightweighting the device, resulting in high space utilization and strong functional synergy of the entire neutron analysis device 100.

[0055] In one implementation, such as Figure 2 and Figure 7 As shown, the shielding assembly 2 includes a second shielding module 23 formed by combining multiple shielding bodies 21. The multiple shielding bodies 21 of the second shielding module 23 extend along a second direction to form a second shielding cavity 100b. The shielding assembly 2 also includes a third shielding module 24 disposed between the first shielding module 22 and the second shielding module 23. The third shielding module 24 extends along a first direction and surrounds the first shielding module 22 and the second shielding module 23 to form a channel 100c.

[0056] Understandably, the second shielding module 23 also includes multiple shielding bodies 21, which are connected by positioning parts 211, mating parts 212, and fasteners. The third shielding module 24, as a transitional structure connecting the first shielding module 22 and the second shielding module 23, extends along the first direction, allowing the three shielding modules to enclose and form a channel 100c for material passage. This multi-module collaborative enclosure structure design not only provides all-round shielding protection for the channel 100c from different directions, but also allows for flexible adjustment of the number, size, and arrangement of shielding bodies 21 in each shielding module according to the risk level of radiation leakage and spatial layout requirements in each direction. This further optimizes the spatial structure and material cost of the device while ensuring the overall shielding effect.

[0057] In addition, there are two third shielding modules 24, which are respectively located on both sides of the channel 100c along the second direction. The third shielding module 24 can be a single shielding block, or it can be spliced ​​together with the shielding body 21 and fasteners proposed in this solution. Its structure and shape are not specifically limited here, and can be adapted according to the requirements.

[0058] In one embodiment, the shielding body 21 includes a shell and a shielding material disposed within the shell. The shell is made of fiberglass, and the shielding material is high-polyethylene powder and a boron-containing compound, wherein the boron content in the boron-containing compound is 3% to 20%. It is understood that high-polyethylene powder, as the matrix material, has a high hydrogen content, which can effectively slow down fast neutrons; the boron-containing compound utilizes the strong absorption characteristics of boron for neutrons to further capture the slowed thermal neutrons. The synergistic effect of the two can significantly improve the overall shielding effect.

[0059] The boron content of the boron-containing compound can be 3%, 5%, 9%, 16%, or 20%, or any value within the aforementioned range of 3% to 20%. The appropriate boron content can be selected based on the intensity of different neutron radiation fields and shielding requirements. The shell is made of fiberglass, which is lightweight, high-strength, and corrosion-resistant, effectively protecting the internal shielding material and preventing damage or scattering during transportation, installation, and use. Furthermore, the insulating properties of fiberglass prevent interference with other electronic components inside the device.

[0060] The above description is merely an exemplary embodiment of the present utility model and does not limit the scope of protection of the present utility model. Any equivalent structural transformations made based on the technical concept of the present utility model and the contents of the present utility model specification and drawings, or direct / indirect applications in other related technical fields, are included within the scope of protection of the present utility model.

Claims

1. A neutron analysis device, characterized in that, The device includes a support frame, a shielding assembly, a detector, and a neutron generator. The shielding assembly and the support frame form a first shielding cavity, a second shielding cavity, and a channel between the first and second shielding cavities for a conveyor belt to pass through. The detector is located in the first shielding cavity, and the neutron generator is located in the second shielding cavity. The shielding assembly includes multiple shielding bodies and multiple fasteners. Each shielding body is provided with at least one of a positioning part and a mating part, as well as a connecting part spaced apart from the positioning part and the mating part. Three of the multiple shielding bodies are a first shielding body, a second shielding body, and a third shielding body. The positioning part of the first shielding body is positioned and connected to the mating part of the second shielding body. The fasteners are configured to lock and fix the connecting part of the first shielding body or the second shielding body to the connecting part corresponding to the third shielding body.

2. The neutron analysis apparatus as described in claim 1, characterized in that, The shield is configured as a polygonal column with multiple sides, and the positioning part, the mating part and the connecting part are disposed on different sides.

3. The neutron analysis apparatus as described in claim 2, characterized in that, The shapes of the plurality of shielding bodies are one or more of the following: square prism, pentagonal prism, or hexagonal prism.

4. The neutron analysis apparatus as described in claim 1, characterized in that, The positioning part is a limiting protrusion provided on the surface of the shield, the mating part is a slot provided on the surface of the shield, the connecting part is a mounting hole provided on the shield, the limiting protrusion is inserted into the slot, and the fastener passes through the mounting hole.

5. The neutron analysis apparatus as described in claim 4, characterized in that, The slot is a dovetail groove, and the shape of the limiting protrusion matches the shape of the dovetail groove.

6. The neutron analysis apparatus as described in claim 4, characterized in that, The limiting protrusion and slot extend along the length of the shield, and the mounting holes are located at both ends of the shield along its length.

7. The neutron analysis apparatus according to any one of claims 1 to 6, characterized in that, The channel is arranged to extend through the first direction, and the shielding assembly includes a first shielding module formed by combining multiple shielding bodies. The multiple shielding bodies of the first shielding module extend along a second direction intersecting the first direction to form the first shielding cavity. The thickness of the first shielding module decreases from the middle of the detector to both sides in the first direction.

8. The neutron analysis apparatus as described in claim 7, characterized in that, The number of shielding bodies located on both sides of the detector along the first direction decreases from the direction closer to the detector to the direction farther away from the detector, so that the thickness of the first shielding module decreases along the third direction. And / or, the first direction, the second direction, and the third direction are perpendicular to each other.

9. The neutron analysis apparatus as described in claim 7, characterized in that, The shielding assembly includes a second shielding module formed by combining a plurality of shielding bodies. The plurality of shielding bodies of the second shielding module extend along the second direction to form the second shielding cavity. The shielding assembly also includes a third shielding module disposed between the first shielding module and the second shielding module. The third shielding module extends along the first direction and surrounds the first shielding module and the second shielding module to form the channel.

10. The neutron analysis apparatus as described in claim 1, characterized in that, The shielding body includes a shell and a shielding material disposed within the shell. The shell is made of fiberglass, and the shielding material is high polyethylene powder and a boron-containing compound, wherein the boron content in the boron-containing compound is 3% to 20%.