Neutron Analysis Facility

Abstract

This utility model discloses a neutron analysis device, relating to the field of radiation detection equipment technology. The neutron analysis device includes a support frame and a detection device and a radiation source mounted on the support frame. A channel is formed between the detection device and the radiation source along a first direction. The detection device includes a first shielding module and a detector. The first shielding module has a first shielding cavity extending along a second direction on one side facing the channel, and the detector is located in the first shielding cavity. The radiation source includes a second shielding module and a neutron generator. The second shielding module has a second shielding cavity extending along a second direction on one side facing the channel, and the neutron generator is located in the second shielding cavity and is positioned opposite to the detector. The thickness of the first shielding module decreases from the middle of the detector to both sides in the first direction. The second direction intersects the first direction. This arrangement can significantly reduce the amount of shielding material used, thereby significantly reducing the volume and weight of the neutron analysis device.

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 Cf-252 neutron source or neutron generator. These neutrons react with the analyte nuclides in the industrial material to produce gamma rays, which are then captured and analyzed to obtain information about the material's composition. However, existing neutron analyzers are bulky and heavy, potentially leading to resource waste and safety risks. Utility Model Content

[0003] The main purpose of this invention is to propose a neutron analysis device, which aims to solve the problem of the large size of existing neutron analyzers and the resulting waste of resources.

[0004] To achieve the above objectives, the neutron analysis device proposed in this utility model includes a support frame and a detection device and a radiation source disposed on the support frame, wherein a channel is formed between the detection device and the radiation source along a first direction for a conveyor belt to pass through.

[0005] The detection device includes a first shielding module and a detector. The first shielding module has a first shielding cavity extending along a second direction on one side facing the channel, and the detector is disposed in the first shielding cavity along the second direction. The radiation source includes a second shielding module and a neutron generator. The second shielding module has a second shielding cavity extending along the second direction on one side facing the channel, and the neutron generator is disposed in the second shielding cavity along the second direction and is disposed opposite to the detector.

[0006] The thickness of the first shielding module decreases from the middle of the detector to both sides in the first direction, and the second direction intersects the first direction.

[0007] In one embodiment, the first shielding module includes a plurality of first shielding bodies, which enclose the first shielding cavity, and any two adjacent first shielding bodies are detachably connected.

[0008] In one embodiment, a plurality of first shielding bodies are respectively arranged to extend along the second direction, and the number of first shielding bodies along the first direction and located on both sides of the detector 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.

[0009] In one embodiment, the first shield is in the shape of a quadrangular prism, and the detector has a top surface, a bottom surface, and two side surfaces connecting the top surface and the bottom surface. A plurality of the first shields respectively abut against the top surface and the two side surfaces of the detector.

[0010] In one embodiment, the second shielding module includes a plurality of second shielding bodies, which enclose the second shielding cavity, and any two adjacent second shielding bodies are detachably connected.

[0011] In one embodiment, the system further includes two third shielding modules disposed within the channel. The third shielding modules extend along the first direction and are respectively connected to the first shielding module and the second shielding module. The two third shielding modules are disposed on opposite sides of the channel along the second direction.

[0012] In one embodiment, the third shielding module includes a plurality of third shielding bodies, which are respectively extended along the first direction, and any two adjacent third shielding bodies are detachably connected.

[0013] In one embodiment, a fixing seat is provided on the side of the second shielding module facing the first shielding module. The fixing seat, the first shielding module, and the third shielding module enclose the channel. The second shielding module is also provided with a limiting member, and the third shielding module is limited and installed between the limiting member and the fixing seat.

[0014] In one embodiment, a fastener is also included. The first shield, the second shield, and the third shield are all provided with a connecting portion. The connecting portion has a plurality of mounting holes along its circumferential direction. The fastener passes through the mounting holes for connection with other components.

[0015] In one embodiment, the first shield, the second shield, and the third shield each include 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 invention includes a support frame and a detection device and a radiation source mounted on the support frame. A channel is formed between the detection device and the radiation source, extending along a first direction and used for a conveyor belt to pass through. The detection device includes a first shielding module and a detector. The first shielding module has a first shielding cavity extending along a second direction on one side facing the channel, and the detector is located in the first shielding cavity along the second direction. The radiation source includes a second shielding module and a neutron generator. The second shielding module has a second shielding cavity extending along a second direction on one side facing the channel, and the neutron generator is located in the second shielding cavity along the second direction and is positioned opposite to the detector. The thickness of the first shielding module decreases from the center of the detector to both sides in the first direction, and the second direction intersects the first direction. The neutron analysis device proposed in this invention eliminates redundant corner parts that have no substantial effect on shielding protection, significantly reduces the amount of shielding material used, and significantly reduces the size and weight of the analysis device. Attached Figure Description

[0017] 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.

[0018] Figure 1 A schematic diagram of an embodiment of the neutron analysis device provided by this utility model;

[0019] Figure 2 A schematic diagram showing the disassembled structure of an embodiment of the neutron analysis device provided by this utility model;

[0020] Figure 3 A schematic diagram of the detector device in one embodiment of the neutron analysis apparatus provided by this utility model;

[0021] Figure 4 A schematic diagram showing the disassembled structure of the support, detector, and neutron generator in one embodiment of the neutron analysis device provided by this utility model;

[0022] Figure 5 A side view of an embodiment of the neutron analysis device provided by this utility model;

[0023] Figure 6 A schematic diagram of the shielding structure in one embodiment of the neutron analysis device provided by this utility model.

[0024] Explanation of icon numbers:

[0025] 100. Neutron analysis device; 1. Support; 2. Detection device; 21. First shielding module; 21a. First shielding cavity; 211. First shielding body; 212. Housing; 213. Connecting part; 213a. Mounting hole; 22. Detector; 3. Radioactive source; 31. Second shielding module; 31a. Second shielding cavity; 311. Second shielding body; 32. Neutron generator; 4. Channel; 5. Third shielding module; 51. Third shielding body; 6. Fixing base; 7. Limiting component.

[0026] 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

[0027] 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 scope of protection of the present utility model.

[0028] 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.

[0029] 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 that simultaneously satisfies A and B. 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.

[0030] Currently, neutron activation analyzers used in industrial applications are mainly divided into two types: bypass type and crossband type. Among them, the detector and neutron generator (or Cf252 neutron source) of the crossband type neutron analyzer are usually arranged in a vertically distributed structure. In order to effectively shield neutrons and ambient radiation, large-volume square shielding modules are usually stacked on both sides of the generator and detector. However, this square stacking structure has obvious defects in practical applications: after the particles interact with the matter, they are distributed in a divergent manner within the moderator. The corners of the square structure contribute very little to the actual shielding protection, but lead to a large overall size and increased weight of the analyzer. It may also generate additional radioactive activation solid waste due to excess shielding material, resulting in resource waste and safety risks.

[0031] Based on this, the present invention proposes a neutron analysis device 100.

[0032] Please see Figures 1 to 3 In one embodiment of this utility model, the neutron analysis device 100 includes a support 1 and a detection device 2 and a radiation source 3 disposed on the support 1. A channel 4 is formed between the detection device 2 and the radiation source 3, which runs through the channel in a first direction and is used for a conveyor belt to pass through. The detection device 2 includes a first shielding module 21 and a detector 22. The first shielding module 21 has a first shielding cavity 21a extending in a second direction on one side facing the channel 4. The detector 22 is disposed in the first shielding cavity 21a in the second direction. The radiation source 3 includes a second shielding module 31 and a neutron generator 32. The second shielding module 31 has a second shielding cavity 31a extending in a second direction on one side facing the channel 4. The neutron generator 32 is disposed in the second shielding cavity 31a in the second direction and is disposed opposite to the detector 22. The thickness of the first shielding module 21 decreases from the middle of the detector 22 to both sides in the first direction. The second direction intersects the first direction.

[0033] It should be noted that in this embodiment, the first direction is the conveyor belt's transport direction, the second direction is the extension direction of the detector 22 and the neutron generator 32, 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 description, the first direction is set along the X-axis, the second direction is set along the Y-axis, and the third direction is set along the Z-axis, and the first, second, and third directions are described as being perpendicular to each other. However, in some other embodiments of this utility model, the specific orientation (vertical or horizontal) of the first, second, and third directions and whether the included angles between them are perpendicular are not specifically limited.

[0034] Understandably, in this embodiment, the conveyor belt runs along the first direction through the channel 4 and is located between the neutron generator 32 and the detector 22 to transport industrial materials such as cement through the channel 4. After the conveyor belt delivers the industrial materials into the channel 4, the neutron generator 32 releases neutrons into the channel 4. The neutrons react with the nuclides to be tested in the industrial materials to generate gamma rays. The detector 22, which is positioned opposite the neutron generator 32, captures the gamma rays and analyzes them to obtain the composition information of the materials.

[0035] Furthermore, the first shielding module 21 can be a single integrated structure or a combination of multiple separate structures. When using an integrated structure, it forms a complete enclosed shielding space, effectively reducing neutron and gamma-ray leakage, simplifying the overall installation process, and ensuring the integrity and reliability of the shielding. Using a combination of separate structures offers greater flexibility, facilitating adaptive adjustments based on different installation spaces, channel 4 dimensions, and the specific locations of the neutron generator 32 and detector 22. For example, the first shielding module 21 can be designed as a combination of several shielding plates connected by bolts or snap-fit ​​joints. During installation, each shielding plate can be positioned separately before assembly and fixation. This method is particularly suitable for installation scenarios with limited space or complex structures, facilitating transportation and on-site operation.

[0036] The second shielding module 31 can also be configured as an integrated structure, or as a combination of multiple separate structures. Alternatively, the first shielding module 21 can be a separate structure while the second shielding module 31 is an integrated structure, or vice versa. Various methods are possible, and will not be elaborated upon here. The specific structure can be designed according to requirements to meet the corresponding shielding and assembly needs. The materials used to manufacture the first shielding module 21 and the second shielding module 31 can be conventional shielding or moderating materials such as lead, polyethylene, and cement, and can be selected according to requirements. No specific limitations are made here.

[0037] Furthermore, in the thickness direction of the first shielding module 21, i.e., the third direction (Z-axis), due to the divergent distribution of gamma rays within the first shielding module 21, if the analytical device adopts a square structure, the actual contribution of its corners to shielding protection is minimal, yet it leads to a large overall size and increased weight of the analyzer. It may also generate additional radioactive activated solid waste due to excess shielding material, resulting in resource waste and safety risks. Therefore, this solution sets the thickness of the first shielding module 21 to decrease gradually from the center of the detector 22 to both sides in the first direction, eliminating redundant corner portions that have no substantial effect on shielding protection, significantly reducing the amount of shielding material used, and significantly reducing the size and weight of the analyzer, facilitating equipment installation and on-site deployment. On the other hand, because the amount of shielding material used is precisely controlled, it can effectively avoid the generation of additional radioactive activated solid waste due to radiation from excess material, reducing subsequent treatment costs and environmental risks, thus balancing practicality and safety.

[0038] It should be noted that, since the thickness of the first shielding module 21 gradually decreases from the middle of the detector 22 to both sides in the first direction, the projection of this module in the second direction can present various shapes such as trapezoidal, arc, or triangle, or other smoothly transitioning or stepped decreasing shapes. 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. In addition, the first shielding cavity 21a and the second shielding cavity 31a can be set as a slot structure, a hole structure, or other cavity shapes that can accommodate the detector 22 and the neutron source. The slot structure usually has an open side, which facilitates the installation and maintenance of the detector 22 and the neutron source, and is especially suitable for scenarios that require frequent debugging or component replacement; while the hole structure can achieve all-round enclosure, further improving the shielding effect, and is suitable for application environments with extremely high protection requirements. The specific structure of the shielding cavity can be set according to the requirements, and no specific restrictions are imposed here.

[0039] In one implementation, such as Figure 2 and Figure 3 As shown, the first shielding module 21 includes multiple first shielding bodies 211, which together form a first shielding cavity 21a. Any two adjacent first shielding bodies 211 can be detachably connected. It is understood that in this embodiment, the first shielding body 211 has a cuboid structure, and multiple first shielding bodies 211 can be spliced ​​together to form a first shielding cavity 21a that matches the shape of the detector 22. This modular design makes the assembly and disassembly of the first shielding module 21 more convenient. When the model or size of the detector 22 changes, only the corresponding first shielding body 211 needs to be replaced or adjusted to adapt to the new detector 22, without having to replace the entire shielding module, greatly improving the versatility and maintenance flexibility of the equipment.

[0040] Furthermore, the detachable connection method facilitates the production, transportation, and storage of individual first shielding bodies 211, reducing manufacturing costs and logistical difficulties. In practical applications, adjacent first shielding bodies 211 can be detachably fixed through bolt connections, snap-fit ​​connections, or mortise and tenon structures. The specific connection method can be selected based on the material and weight of the shielding body and on-site installation requirements to ensure the stability of the connection and the integrity of the shielding, effectively preventing gamma rays from leaking from the splicing gaps and ensuring the shielding effect. Of course, in addition to being set as a cuboid, the first shielding body 211 can also be designed as a cylinder, cube, polygonal prism, or other regular or irregular geometric structures, depending on the actual application scenario and the specific shape requirements of the detector 22. No specific limitations are made here.

[0041] In one implementation, such as Figure 1 As shown, the second direction is orthogonal to the first direction. It can be understood that the neutron generator 32 and detector 22 extend along the second direction, i.e., the width of the conveyor belt. This ensures that the neutron beam and the detection area of ​​detector 22 provide sufficient coverage along the width of the conveyor belt, allowing items to be detected at different lateral positions on the conveyor belt to be uniformly irradiated and effectively detected, avoiding blind spots caused by insufficient lateral coverage. Furthermore, the orthogonal orientation makes the layout of the neutron generator 32 and detector 22 more spatially regular, facilitating a compact design of the internal structure, reducing the space required for installation, and also benefiting subsequent maintenance and debugging of the device.

[0042] Of course, in some possible embodiments, the first direction and the second direction are inclined, that is, they form a certain angle between them. The specific degree of the angle can be flexibly adjusted according to the actual working conditions such as the size and specifications of the item to be detected, the running speed of the conveyor belt, and the detection sensitivity requirements.

[0043] In one implementation, such as Figure 3 and Figure 5 As shown, multiple first shielding bodies 211 extend along the second direction, and the number of first shielding bodies 211 located on both sides of the detector 22 along the first direction decreases from the direction closer to the detector 22 to the direction farther away from the detector 22, thereby reducing the thickness of the first shielding module 21. It can be understood that in this embodiment, multiple first shielding bodies 211 are stacked around the detector 22, and the number of first shielding bodies 211 decreases the further away from the detector 22 in the first direction. Therefore, the shielding capability of the entire first shielding module 21 against diverging gamma rays exhibits a gradient decreasing distribution.

[0044] 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 22 usually decreases naturally with increasing distance. The radiation energy and density are higher in the region closer to detector 22. Therefore, a larger number of first shielding bodies 211 are needed to form a shielding layer with greater thickness to achieve efficient blocking. In the region far from detector 22, the radiation intensity has been significantly reduced. Accordingly, the number of first shielding bodies 211 is reduced and the shielding thickness is thinned. This can meet the basic shielding requirements while avoiding excessive material consumption and unnecessary increase in the overall weight of the device, further improving the compactness and economy of the device structure.

[0045] In some other embodiments, the first shield 211 may extend along the first direction. For example, multiple first shields 211 may be stacked in the second direction. The first shield 211 is bent to fit the surface of the detector 22, and the outer side of the first shield 211 is inclined to save materials and optimize space utilization. While ensuring the shielding effect, it can also save materials. However, the structure is more complex than the cuboid structure extending along the second direction. Therefore, the stacking method of multiple first shields 211 is not specifically limited here, and the shape of the first shield 211 can be adapted according to the stacking method.

[0046] In one implementation, such as Figures 2 to 4 As shown, the first shield 211 is shaped like a quadrangular prism, and the detector 22 has a top surface, a bottom surface, and two side surfaces connecting the top and bottom surfaces. Multiple first shields 211 respectively abut against the top surface and two side surfaces of the detector 22. It can be understood that both the first shield 211 and the detector 22 are cuboid structures, forming a tightly fitted enclosure structure between the first shield 211 and the outer surface of the detector 22, thereby providing all-around shielding protection for the top surface and two side surfaces of the detector 22. Of course, in some other embodiments, the shape of the first shield 211 can also be set as a cylinder, a triangular prism, or other polyhedral structure, as long as it can adapt to the surface shape of the detector 22 and form an effective fit.

[0047] In one implementation, such as Figure 2 As shown, the second shielding module 31 includes multiple second shielding bodies 311, which together form a second shielding cavity 31a. Any two adjacent second shielding bodies 311 are detachably connected. It should be noted that in this embodiment, the second shielding bodies 311 and the first shielding body 211 have the same structure and are also designed as detachable connections, giving the second shielding module 31 convenient assembly and disassembly characteristics. Using the same structure for the first shielding body 211 and the second shielding body 311 also helps reduce the cost of production molds and improve the versatility and interchangeability of parts.

[0048] In one implementation, such as Figure 1 As shown, the device also includes two third shielding modules 5 disposed within the channel 4. The third shielding modules 5 extend along the first direction and are respectively connected to the first shielding module 21 and the second shielding module 31. The two third shielding modules 5 are disposed on opposite sides of the channel 4 along the second direction. It can be understood that the first shielding module 21 and the second shielding module 31 form the channel 4 at intervals along the third direction. To further improve the shielding effect against gamma rays, a third shielding module 5 is provided on each side of the channel 4 in the second direction. These two third shielding modules 5, together with the first shielding module 21 and the second shielding module 31, constitute a closed-loop shielding structure around the channel 4, further blocking gamma rays that may leak from the side of the channel 4, making the shielding system of the entire neutron analyzer 100 more complete and reliable.

[0049] In one implementation, such as Figure 4 and Figure 5 As shown, the third shielding module 5 includes multiple third shielding bodies 51, which extend along the first direction and are detachably connected to any two adjacent third shielding bodies 51. It is understood that the third shielding bodies 51 have the same structure as the first shielding body 211 and the second shielding body 311, and also adopt a modular design. During manufacturing, they can share molds with the first shielding body 211 and the second shielding body 311, further reducing overall production costs. Furthermore, disassembling the third shielding module 5 into multiple detachably connected third shielding bodies 51 makes installation, transportation, and subsequent maintenance of the device more convenient.

[0050] In one implementation, such as Figure 4 and Figure 5 As shown, a fixing seat 6 is provided on the side of the second shielding module 31 facing the first shielding module 21. The fixing seat 6, the first shielding module 21, and the third shielding module 5 enclose a channel 4. A limiting member 7 is also provided on the second shielding module 31, and the third shielding module 5 is limited and installed between the limiting member 7 and the fixing seat 6. It can be understood that the fixing seat 6 has an overall "V" shape structure to facilitate the conveyor belt to pass through the channel 4 and prevent the conveyor belt from causing wear to the second shielding body 311. The second shielding body 311 is provided with limiting members 7 on both sides of the fixing seat 6 in the second direction. The third shielding module 5 is located between the limiting member 7 and the fixing seat 6 to achieve precise positioning and stable installation, prevent the third shielding module 5 from displacement during device operation, ensure the shielding effect of the channel 4, and improve the safety of the entire neutron analysis device 100.

[0051] In one embodiment, fasteners are also included, such as Figure 6As shown, the first shield 211, the second shield 311, and the third shield 51 are all provided with connecting portions 213. Multiple mounting holes 213a are provided circumferentially on the connecting portions 213, and fasteners pass through the mounting holes 213a for connection with other components. It can be understood that the first shield 211, the second shield 311, and the third shield 51 are all rectangular parallelepipeds with identical structures, and each end has a protruding annular structure serving as a connecting portion 213. Mounting holes 213a are provided on the four sides of the connecting portions 213, and fasteners pass through the mounting holes 213a to connect adjacent shields or to connect the shields to the bracket 1, thereby achieving modular assembly and disassembly of the entire shielding structure.

[0052] Furthermore, multiple shielding bodies can be flexibly connected using cuboid, hexagonal, or grid splicing structures to adapt to the installation and usage requirements of different scenarios. Fasteners can be bolts with nuts, or detachable connection methods such as clips and pins, to meet the installation requirements under different working conditions. The choice can be made according to the requirements, and no specific limitations are made here.

[0053] In one implementation, such as Figure 6 As shown, the first shield 211, the second shield 311, and the third shield 51 all include a shell 212 and a shielding material disposed within the shell 212. The shell 212 is made of fiberglass, and the shielding material is high-polyethylene powder and a boron-containing compound, with the boron content in the boron-containing compound ranging from 3% to 20%. It is understood that high-polyethylene powder, as the matrix material, has a good 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.

[0054] 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 casing 212 is made of fiberglass, which is lightweight, high-strength, and corrosion-resistant, effectively protecting the internal shielding material and preventing damage or spillage during transportation, installation, and use. Furthermore, the insulating properties of fiberglass prevent interference with other electronic components inside the device.

[0055] 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, It includes a support frame and a detection device and a radiation source disposed on the support frame, wherein a channel is formed between the detection device and the radiation source, which runs through a first direction and is used for a conveyor belt to pass through. The detection device includes a first shielding module and a detector. The first shielding module has a first shielding cavity extending along a second direction on one side facing the channel, and the detector is disposed in the first shielding cavity along the second direction. The radiation source includes a second shielding module and a neutron generator. The second shielding module has a second shielding cavity extending along the second direction on one side facing the channel, and the neutron generator is disposed in the second shielding cavity along the second direction and is disposed opposite to the detector. The thickness of the first shielding module decreases from the middle of the detector to both sides in the first direction, and the second direction intersects the first direction.

2. The neutron analysis apparatus as described in claim 1, characterized in that, The first shielding module includes multiple first shielding bodies, which together form the first shielding cavity, and any two adjacent first shielding bodies can be detachably connected.

3. The neutron analysis apparatus as described in claim 2, characterized in that, Multiple first shielding bodies are respectively arranged to extend along the second direction. The number of first shielding bodies along the first direction and located on both sides of the detector 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.

4. The neutron analysis apparatus as described in claim 3, characterized in that, The first shield is in the shape of a quadrangular prism. The detector has a top surface, a bottom surface, and two side surfaces connecting the top surface and the bottom surface. Multiple first shields respectively abut against the top surface and the two side surfaces of the detector.

5. The neutron analysis apparatus as described in any one of claims 2 to 4, characterized in that, The second shielding module includes multiple second shielding bodies, which together form the second shielding cavity, and any two adjacent second shielding bodies can be detachably connected.

6. The neutron analysis apparatus as described in claim 5, characterized in that, It also includes two third shielding modules disposed within the channel. The third shielding modules extend along the first direction and are respectively connected to the first shielding module and the second shielding module. The two third shielding modules are disposed on opposite sides of the channel along the second direction.

7. The neutron analysis apparatus as described in claim 6, characterized in that, The third shielding module includes multiple third shielding bodies, which are respectively extended along the first direction, and any two adjacent third shielding bodies can be detachably connected.

8. The neutron analysis apparatus as described in claim 7, characterized in that, The second shielding module has a fixed base on the side facing the first shielding module. The fixed base, the first shielding module, and the third shielding module enclose the channel. The second shielding module is also provided with a limiting member. The third shielding module is limited and installed between the limiting member and the fixed base.

9. The neutron analysis apparatus as described in claim 7, characterized in that, It also includes fasteners. The first shield, the second shield, and the third shield are all provided with connecting parts. Multiple mounting holes are provided on the connecting parts along the circumferential direction. The fasteners pass through the mounting holes to connect two adjacent first shields, two adjacent second shields, or two adjacent third shields, or to connect with the bracket.

10. The neutron analysis apparatus as described in claim 7, characterized in that, The first shield, the second shield, and the third shield all include a shell and a shielding material disposed within the shell, and the shell is made of fiberglass.

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