Self-tracking long-distance neutron source detection device and method

Abstract

The invention discloses a self-tracking long-distance neutron source detection device and method, and the device and method can quickly obtain the accurate distance of a neutron source, reconstruct the three-dimensional space distribution of the neutron source, and improve the searching efficiency. The device comprises a detector double-sided array, wherein the detector double-sided array adopts a first detector array to determine a first collision point coordinate and a first energy value of each neutron incident to a detector, and adopts a second detector array to determine a second collision point coordinate of the corresponding neutron; the data processing system determines an elastic collision angle, reconstructs a projection image of the neutron source on a specified plane according to the first collision point coordinate, the second collision point coordinate and the elastic collision angle corresponding to each neutron, and obtains an azimuth coordinate of the neutron source; and the motion control system and the array automatic adjustment mechanism control the detector double-sided array to perform horizontal rotation and pitching adjustment according to the azimuth coordinates of the neutron source, and adjust the arrangement parameters of the detectors in the detector double-sided array to obtain a reconstructed image of the neutron source.

Description

Technical Field

[0001] The present application relates to the technical field of neutron detection, and in particular to a self-tracking long-distance neutron source detection device and method. Background Art

[0002] With the development of nuclear energy and nuclear technology, the regulatory burden of nuclear safety has become increasingly burdensome. The supervision and management of special nuclear materials is a crucial component of nuclear safety. Uranium and transuranium elements in special nuclear materials can release neutrons through spontaneous or induced fission. Neutrons can penetrate high-Z shielding structures. Neutron detection can be used to measure the presence of special nuclear materials within shielding structures, and the location of special nuclear materials can be determined by measuring the position of the neutron source.

[0003] Related technologies primarily use gas neutron detectors, such as He-3 counters, to perform static measurements of neutron sources. These devices typically have limited detection range, are bulky, have low detection efficiency, and lack high accuracy, making them incapable of accurately locating or identifying neutron sources. To meet the needs of customs and nuclear safety regulators for large-scale neutron source inspections and rapid searches for lost radioactive sources, a long-range dynamic neutron source detection device is urgently needed. Summary of the Invention

[0004] In view of this, the present application provides a self-tracking long-distance neutron source detection device and method, the main purpose of which is to solve the problems of gas neutron detectors having limited detection distance, large size, low detection efficiency, low detection accuracy, and inability to accurately locate the neutron source.

[0005] According to a first aspect of the present application, a self-tracking remote neutron source detection device is provided, the device comprising: Double-sided detector array, data processing system, motion control system and array automatic adjustment mechanism; The double-sided detector array uses a first detector array to determine the coordinates of a first collision point and a first energy value of each neutron incident on the detector, and uses a second detector array to determine the coordinates of a second collision point of the corresponding neutron incident on the detector after undergoing an elastic collision, and transmits the first collision point coordinates, second collision point coordinates, and first energy value corresponding to each neutron to a data processing system for processing; The data processing system determines the elastic collision angle based on the flight time of each neutron from the first detector array to the second detector array and the corresponding first energy value, and reconstructs the projection image of the neutron source on a designated plane based on the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron to obtain the azimuth coordinates of the neutron source, wherein the designated plane is any plane on a line connecting the center of a first plane corresponding to the first detector array and the center of a second plane corresponding to the second detector array; The motion control system and the array automatic adjustment mechanism control the horizontal rotation and pitch adjustment of the double-sided array of detectors according to the azimuth coordinates of the neutron source so that the center of the first plane, the center of the second plane and the azimuth coordinates of the neutron source are in the same straight line, and adjust the arrangement parameters of the detectors in the double-sided array of detectors to obtain a reconstructed image of the neutron source.

[0006] Optionally, the double-sided detector array includes a first detector array and a second detector array; the plane where the first detector array is located and the plane where the second detector array is located are parallel to each other and are spaced apart.

[0007] Optionally, the distance between the plane where the first detector array is located and the plane where the second detector array is located in the double-sided detector array is adjusted by the motion control system and the array automatic adjustment mechanism; the horizontal rotation angle and pitch adjustment angle of the double-sided detector array are adjusted by the motion control system and the array automatic adjustment mechanism; the position of each detector in the double-sided detector array within the plane in which it is located is adjusted by the motion control system and the array automatic adjustment mechanism.

[0008] According to a second aspect of the present application, a self-tracking remote neutron source detection method is provided, the method comprising: Continuously using the first detector array of the double-sided detector array to determine the coordinates of a first collision point and a first energy value of each neutron incident on the detector, and using the second detector array of the double-sided detector array to determine the coordinates of a second collision point of the corresponding neutron incident on the detector after undergoing an elastic collision; Determining, using a data processing system, an elastic collision angle based on the flight time and first energy value of the neutrons from the first detector array to the second detector array, and reconstructing a projection image of the neutron source on a designated plane based on the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron to obtain azimuth coordinates of the neutron source, where the designated plane is any plane on a line connecting the center of a first plane corresponding to the first detector array and the center of a second plane corresponding to the second detector array; Using a motion control system and an array automatic adjustment mechanism, the double-sided array of the detector is controlled to perform horizontal rotation and pitch adjustment so that the azimuth coordinates of the center of the first plane, the center of the second plane, and the neutron source are in the same straight line; The adjusted double-sided detector array is used for re-detection to determine the distance to the neutron source, and the motion control system and the array automatic adjustment mechanism are used to adjust the arrangement parameters of the double-sided detector array, and the adjusted double-sided detector array is used for re-detection to obtain a reconstructed image of the neutron source.

[0009] Optionally, determining the elastic collision angle according to the flight time of the neutron from the first detector array to the second detector array and the first energy value includes: determining a neutron mass of the neutron, determining a flight time of the neutron from the first collision point coordinate to the second collision point coordinate, and determining a flight distance of the neutron based on the first collision point coordinate and the second collision point coordinate; The second energy value corresponding to the neutron is calculated according to the following formula:

[0010] in, is the second energy value, is the neutron mass, is the flight distance, is the flight time; Calculate the ratio between the first energy value and the second energy value according to the following formula, calculate the square root of the ratio, and use the arc tangent of the square root as the elastic collision angle; ; in, is the first energy value, is the elastic collision angle, is the second energy value.

[0011] Optionally, reconstructing a projection image of the neutron source on a specified plane according to the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron to obtain the azimuth coordinates of the neutron source includes: Determine any plane on the line connecting the centers of the first and second planes as the designated plane, reconstruct the conic curve based on the coordinates of the first collision point, the coordinates of the second collision point, and the elastic collision angle corresponding to each neutron, and project the conic curve onto the designated plane to obtain the equation of the ellipse; Divide the specified plane into multiple grids, and establish a straight line passing through the center of each grid along the specified coordinate axis. Substitute the straight line expression into the ellipse equation corresponding to each neutron to obtain the coordinates of the intersection of each ellipse and the straight line, and increment the grid pixel value where the intersection is located. The pixel values ​​of each grid are summed to obtain the projection image of the neutron source on the specified plane, and the azimuth coordinates of the neutron source are obtained based on the projection image.

[0012] Optionally, a conic section is reconstructed based on the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron, and the conic section is projected onto a specified plane to obtain an ellipse equation, including: The equation of the ellipse is ;

[0013] in, is the constant coefficient of the elliptic equation, is the elastic collision angle, and the coordinates of the first collision point are , the coordinates of the second collision point are , To specify a plane, is the distance between the first detector array and the second detector array.

[0014] Optionally, a motion control system and an array automatic adjustment mechanism are used to control the double-sided array of the detector to perform horizontal rotation and pitch adjustment so that the azimuth coordinates of the first plane center, the second plane center and the neutron source are in the same straight line, including: calling a data processing system to send a parameter adjustment request to the motion control system according to the azimuth coordinates of the neutron source, and the motion control system controls the double-sided array of the detector to perform horizontal rotation and pitch adjustment through the array automatic adjustment mechanism so that the azimuth coordinates of the first plane center, the second plane center and the neutron source are in the same straight line.

[0015] Optionally, re-detection is performed using the adjusted double-sided detector array to determine the neutron source distance, including: re-detecting the first collision point coordinates, second collision point coordinates and elastic collision angle corresponding to each neutron using the adjusted double-sided detector array, determining the projection image of each neutron on each specified plane based on the first collision point coordinates, second collision point coordinates and elastic collision angle corresponding to each neutron, determining a target plane with the highest imaging resolution among multiple specified planes, and determining the neutron source distance based on the coordinates of the target plane.

[0016] Optionally, the method further includes: The data processing system is called to send a parameter adjustment request to the motion control system based on the projection image of the target plane. The motion control system controls the adjustment of the spacing between the first detector array and the second detector array in the double-sided detector array through the array automatic adjustment mechanism, and adjusts the arrangement spacing of the detectors in the first detector array and the second detector array.

[0017] By means of the above technical solution, the present application provides a self-tracking long-distance neutron source detection device and method. The present application proposes a neutron detection device with a double-sided array arranged in front and back. Through a fixed single detection, a two-dimensional image of the neutron source can be reconstructed, and the orientation of the neutron source can be quickly obtained. Then, the algorithm searches for the optimal image reconstruction distance, quickly obtains the accurate distance of the neutron source, and then reconstructs the three-dimensional spatial distribution of the neutron source, ensuring that the neutron source search range is further narrowed and the search efficiency is improved. In addition, the embodiment of the present application improves the imaging quality and obtains detailed information about the neutron source by optimizing the parameters of the front and rear detector array plane distances and the detector spacing within the array plane in the double-sided array of the detector, which can provide effective support for further accurate determination of the number and distribution of long-distance neutron sources.

[0018] The above description is only an overview of the technical solution of the present application. In order to more clearly understand the technical means of the present application, it can be implemented in accordance with the contents of the specification. In order to make the above and other purposes, features and advantages of the present application more obvious and easy to understand, the specific implementation methods of the present application are listed below. BRIEF DESCRIPTION OF THE DRAWINGS

[0019] Various other advantages and benefits will become apparent to those skilled in the art upon reading the detailed description of the preferred embodiment below. The accompanying drawings are for illustration purposes only and are not to be considered as limiting the present application. The same reference symbols are used throughout the drawings to represent the same components. In the drawings: Figure 1 A schematic diagram of a self-tracking long-distance neutron source detection device provided in an embodiment of the present application is shown; Figure 2 A schematic flow chart of a self-tracking remote neutron source detection method provided in an embodiment of the present application is shown; Figure 3 A schematic flow chart of a self-tracking remote neutron source detection method provided in an embodiment of the present application is shown; Figure 4 A schematic diagram of pixel grid division in an imaging plane of a self-tracking remote neutron source detection method provided in an embodiment of the present application is shown; Figure 5 The neutron source detection imaging simulation test results of a self-tracking long-distance neutron source detection method provided by an embodiment of the present application are shown; Figure 6 The neutron source detection imaging simulation test results of a self-tracking long-distance neutron source detection method provided by an embodiment of the present application are shown. DETAILED DESCRIPTION

[0020] The following describes in detail embodiments of the present application, examples of which are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain the present application, and are not to be construed as limiting the present application.

[0021] Those skilled in the art will understand that, unless otherwise stated, the singular forms "a," "an," "said," and "the" used herein may also include plural forms. It should be further understood that the term "comprising" used in the specification of this application refers to the presence of the stated features, integers, steps, operations, elements, and / or components, but does not preclude the presence or addition of one or more other features, integers, steps, operations, elements, components, and / or groups thereof.

[0022] Those skilled in the art will understand that, unless otherwise defined, all terms (including technical and scientific terms) used herein have the same meaning as commonly understood by those skilled in the art to which this application belongs. It should also be understood that terms such as those defined in common dictionaries should be understood to have meanings consistent with their meanings in the context of the prior art and, unless specifically defined as such, will not be interpreted in an idealized or overly formal sense.

[0023] Those skilled in the art will appreciate that the term "terminal" as used herein includes both devices that are wireless signal receivers, i.e., devices that only have wireless signal receivers without transmission capabilities, and devices that have receiving and transmitting hardware capable of performing two-way communication over a two-way communication link. Such devices may include: cellular or other communication devices with single-line displays, multi-line displays, or cellular or other communication devices without multi-line displays; PCS (Personal Communications Service) devices that may combine voice, data processing, fax, and / or data communication capabilities; PDAs (Personal Digital Assistants) that may include a radio frequency receiver, a pager, Internet / Intranet access, a web browser, a notepad, a calendar, and / or a GPS (Global Positioning System) receiver; and conventional laptop and / or palmtop computers or other devices that have and / or include a radio frequency receiver. As used herein, a "terminal" can be portable, transportable, installed in a vehicle (air, sea, and / or land), or adapted and / or configured to operate locally and / or in a distributed manner at any other location on Earth and / or in space. A "terminal" as used herein can also refer to a communication terminal, an Internet access terminal, or a music / video playback terminal, such as a PDA, a mobile internet device (MID), and / or a mobile phone with music / video playback capabilities, as well as devices such as smart televisions and set-top boxes.

[0024] The present application embodiment provides a self-tracking long-distance neutron source detection device, such as Figure 1 As shown, the device comprises: a double-sided detector array 1, a data processing system 2, a motion control system 3 and an array automatic adjustment mechanism 4; The double-sided detector array 1 uses a first detector array to determine the first collision point coordinates and first energy value of each neutron incident on the detector, and uses a second detector array to determine the second collision point coordinates of the corresponding neutron incident on the detector after undergoing an elastic collision, and transmits the first collision point coordinates, second collision point coordinates and first energy value corresponding to each neutron to the data processing system 2 for processing.

[0025] The data processing system 2 determines the elastic collision angle based on the flight time of each neutron from the first detector array to the second detector array and the corresponding first energy value, and reconstructs the projection image of the neutron source on the specified plane based on the first collision point coordinates, the second collision point coordinates and the elastic collision angle corresponding to each neutron to obtain the azimuth coordinates of the neutron source, wherein the specified plane is any plane on the line connecting the center of the first plane corresponding to the first detector array and the center of the second plane corresponding to the second detector array.

[0026] The motion control system 3 and the array automatic adjustment mechanism 4 control the detector double-sided array 1 to perform horizontal rotation and pitch adjustment according to the azimuth coordinates of the neutron source so that the azimuth coordinates of the first plane center, the second plane center and the neutron source are in the same straight line, and adjust the arrangement parameters of the detectors in the detector double-sided array 1 to obtain a reconstructed image of the neutron source.

[0027] It is understandable that if Figure 1 As shown, the double-sided detector array 1 includes a first detector array and a second detector array. The double-sided detector array 1 consists of 18 detectors, with the first and second detector arrays each comprising 9 detectors. The detectors are made of plastic scintillator (EJ-276) coupled with SiPM and have a radius of 5 cm. The center-to-center spacing of the detectors can be adjusted using the motion control system 3 and the array automatic adjustment mechanism 4, with an initial center-to-center spacing of 25 cm. The planes containing the first and second detector arrays are parallel and spaced apart. The distance between the first and second planes corresponding to the first and second detector arrays can be adjusted using the motion control system 3 and the array automatic adjustment mechanism 4, with an initial distance of 50 cm. Furthermore, the horizontal rotation and elevation angles of the double-sided detector arrays are also adjusted using the motion control system 3 and the array automatic adjustment mechanism 4.

[0028] This application proposes a neutron detection device with a double-sided array arranged front and back. Through a fixed single detection, a two-dimensional image of the neutron source can be reconstructed, and the orientation of the neutron source can be quickly obtained. Then, an algorithm is used to search for the optimal image reconstruction distance, quickly obtain the accurate distance of the neutron source, and then reconstruct the three-dimensional spatial distribution of the neutron source, ensuring that the neutron source search range is further narrowed and the search efficiency is improved. In addition, the embodiments of the present application improve the imaging quality and obtain detailed information about the neutron source by optimizing the parameters of the front and rear detector array plane distances and the detector spacing within the array plane in the double-sided detector array, providing effective support for further accurate determination of the number and distribution of distant neutron sources.

[0029] The present invention provides a self-tracking remote neutron source detection method. Figure 2 As shown, the method includes: 201. Continue to use the first detector array of the double-sided detector array to determine the first collision point coordinates and the first energy value of each neutron incident on the detector, and use the second detector array in the double-sided detector array to determine the second collision point coordinates of the corresponding neutron incident on the detector after experiencing an elastic collision.

[0030] In the embodiment of the present application, the double-sided detector array is composed of a first detector array and a second detector array with a spatial spacing, wherein the first plane where the first detector array is located and the second plane where the second detector array is located are parallel to each other and spaced apart. The plane distance between the first plane where the first detector array is located and the second plane where the second detector array is located is .like Figure 3 As shown, Neutrons emitted by a neutron source When the incident light enters the double-sided detector array, it first hits the first detector array. With the detector of hydrogen nuclei An elastic collision occurs and the detector measures the hydrogen nucleus through a photoelectric converter Neutrons obtained Part of the energy The neutrons that have completed the first energy transfer continue to move in the scattering direction, passing through the preset plane spacing and reaching the second detector array. Detected by the detector.

[0031] 202. Utilizing a data processing system, the elastic collision angle is determined based on the flight time and the first energy value of the neutron from the first detector array to the second detector array, and the projection image of the neutron source on a designated plane is reconstructed based on the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron to obtain the azimuthal coordinates of the neutron source, where the designated plane is any plane on a line connecting the center of a first plane corresponding to the first detector array and the center of a second plane corresponding to the second detector array.

[0032] In the embodiment of the present application, the neutron mass of the neutron is first determined by using a data processing system. , and then determine the coordinates of the neutron from the first collision point Fly to the coordinates of the second collision point Flight time , and determining the flight distance of the neutron according to the coordinates of the first collision point and the second collision point , calculate the neutron at the second collision point according to the following formula 1 The second energy value .

[0033] Formula 1:

[0034] Furthermore, according to the first energy value and the second energy value, a ratio between the first energy value and the second energy value is calculated based on the following formula 2, and the square root of the ratio is calculated, and the arc tangent value of the square root is used as the elastic collision angle.

[0035] Formula 2:

[0036] in, is the first energy value, is the elastic collision angle, is the second energy value.

[0037] Furthermore, any plane is determined on the line connecting the center of the first plane and the center of the second plane. As the specified plane, according to the coordinates of the first collision point corresponding to each neutron , coordinates of the second collision point and elastic collision angle , reconstruct the conic curve and project the conic curve onto the specified plane On the above, we get the ellipse equation shown in the following formula 3: Formula 3:

[0038] in,

[0039] is the constant coefficient of the elliptic equation, is the elastic collision angle, and the coordinates of the first collision point are , the coordinates of the second collision point are , is the specified plane, is the distance between the first detector array and the second detector array.

[0040] Furthermore, if Figure 4 As shown, the plane will be specified Divide the image into multiple pixel grids of the same size and create a straight line passing through the center of each grid along a specified coordinate axis (such as the y-axis). 、 、 , ..., put the straight line expression into the elliptic equation corresponding to the neutron, so that the elliptic equation becomes about By solving the quadratic equation, we can get the coordinates of the intersection of each line and the ellipse, and then get the grid where the intersection is located. The pixel value of the grid is increased by 1, that is, the pixel value of the grid where the intersection is located is increased. Repeat the above steps to continuously detect the ellipse equation corresponding to each neutron, substitute the straight line expression into the ellipse equation corresponding to each neutron, and adjust the pixel value of the corresponding grid. Finally, sum the pixel values ​​calculated for each grid in each neutron collision to get the neutron source in the specified plane. The projection image on the neutron source is obtained according to the projection image. .

[0041] Utilize the motion control system and array automatic adjustment mechanism to control the double-sided array of the detector to perform horizontal rotation and pitch adjustment so that the azimuth coordinates of the first plane center, the second plane center and the neutron source are in the same straight line.

[0042] In the embodiment of the present application, the data processing system is based on the azimuth coordinates of the neutron source. , sends a parameter adjustment request to the motion control system, tracks the orientation of the neutron source through the array automatic adjustment mechanism, that is, adjusts the double-sided array of the detector horizontally and records the angle , make pitch adjustments and record the angles , so that the azimuthal coordinates of the center of the first plane, the center of the second plane and the neutron source The three points are in a straight line.

[0043] 204. Re-detection is performed using the adjusted double-sided detector array to determine the distance to the neutron source, and arrangement parameters of the double-sided detector array are adjusted using a motion control system and an automatic array adjustment mechanism, and re-detection is performed using the adjusted double-sided detector array to obtain a reconstructed image of the neutron source.

[0044] In the embodiment of the present application, the data processing system is based on and Re-determine the candidate plane set on the line connecting the center of the first plane and the center of the second plane, and re-select any plane in the candidate plane set Repeat steps 201 and 202 to perform iterative detection, use the adjusted double-sided detector array to re-detect the first collision point coordinates, second collision point coordinates, and elastic collision angle corresponding to each neutron, determine the projection image of each neutron on each designated plane based on the first collision point coordinates, second collision point coordinates, and elastic collision angle corresponding to each neutron, and determine a target plane with the highest imaging resolution among multiple designated planes. , and then determine the neutron source distance according to the coordinates of the target plane as .

[0045] In addition, the data processing system can also send parameter adjustment requests to the motion control system according to the projection image of the target plane. The motion control system adjusts the distance between the first detector array and the second detector array in the double-sided detector array through the array automatic adjustment mechanism, and adjusts the arrangement distance of the detectors in the first detector array and the second detector array. The imaging of the neutron source on the plane is optimal. The simulation and experimental test results of the neutron source detection based on the above device and method are as follows: Figure 5 and Figure 6 As shown, accurate imaging of the neutron source is achieved.

[0046] The method provided in the embodiment of the present application reconstructs a two-dimensional image of the neutron source through a fixed single detection by neutron detection devices arranged in front and behind a double-sided array, quickly obtaining the orientation of the neutron source. The algorithm then searches for the optimal image reconstruction distance, quickly obtaining the accurate distance to the neutron source, and then reconstructing the three-dimensional spatial distribution of the neutron source, thereby further narrowing the neutron source search range and improving search efficiency. Furthermore, the embodiment of the present application optimizes the parameters of the front and rear detector array plane distances and the detector spacing within the array plane in the double-sided detector array to improve imaging quality and obtain detailed information about the neutron source, providing effective support for further accurate determination of the number and distribution of distant neutron sources.

[0047] Those skilled in the art will appreciate that all or part of the processes in the above-described method embodiments can be implemented by instructing the relevant hardware through a computer program. The computer program can be stored in a computer-readable storage medium. When executed, the program can include the processes in the above-described method embodiments. The aforementioned storage medium can be a non-volatile storage medium such as a magnetic disk, an optical disk, a read-only memory (ROM), or a random access memory (RAM).

[0048] The present invention also provides a storage medium storing computer-readable instructions. When the computer-readable instructions are executed by one or more processors, the one or more processors execute the steps of the data relationship reconstruction method in any of the above embodiments.

[0049] Those skilled in the art will appreciate that all or part of the processes in the above-described method embodiments can be implemented by instructing the relevant hardware through a computer program. The computer program can be stored in a computer-readable storage medium. When executed, the program can include the processes in the above-described method embodiments. The aforementioned storage medium can be a non-volatile storage medium such as a magnetic disk, an optical disk, a read-only memory (ROM), or a random access memory (RAM).

[0050] Those skilled in the art will appreciate that the steps, measures, and schemes in the various operations, methods, and processes discussed in this application may be interchanged, modified, combined, or deleted. Furthermore, other steps, measures, and schemes in the various operations, methods, and processes discussed in this application may also be interchanged, modified, rearranged, decomposed, combined, or deleted. Furthermore, steps, measures, and schemes in the prior art that are similar to those disclosed in this application may also be interchanged, modified, rearranged, decomposed, combined, or deleted.

[0051] The above description is only part of the implementation methods of the present application. It should be pointed out that for ordinary technicians in this technical field, several improvements and modifications can be made without departing from the principles of the present application. These improvements and modifications should also be regarded as the scope of protection of the present application.

Claims

1. A self-tracking long-distance neutron source detection device, characterized in that: include: Double-sided detector array, data processing system, motion control system and array automatic adjustment mechanism; The double-sided detector array uses a first detector array to determine the coordinates of a first collision point and a first energy value of each neutron incident on the detector, and uses a second detector array to determine the coordinates of a second collision point of the corresponding neutron incident on the detector after undergoing an elastic collision, and transmits the first collision point coordinates, second collision point coordinates, and first energy value corresponding to each neutron to the data processing system for processing; The data processing system determines an elastic collision angle based on the flight time of each neutron from the first detector array to the second detector array and the corresponding first energy value, and reconstructs a projection image of the neutron source on a specified plane based on the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron to obtain the azimuth coordinates of the neutron source, wherein the specified plane is any plane on a line connecting the center of a first plane corresponding to the first detector array and the center of a second plane corresponding to the second detector array; The motion control system and the array automatic adjustment mechanism control the double-sided detector array to perform horizontal rotation and pitch adjustment according to the azimuth coordinates of the neutron source so that the center of the first plane, the center of the second plane and the azimuth coordinates of the neutron source are in the same straight line, and adjust the arrangement parameters of the detectors in the double-sided detector array to obtain a reconstructed image of the neutron source.

2. The self-tracking long-distance neutron source detection device according to claim 1, characterized in that: The double-sided detector array includes a first detector array and a second detector array; The plane where the first detector array is located and the plane where the second detector array is located are parallel to each other and spaced apart.

3. The self-tracking long-distance neutron source detection device according to claim 2, characterized in that: The distance between the plane where the first detector array is located and the plane where the second detector array is located in the double-sided detector array is adjusted by the motion control system and the array automatic adjustment mechanism; The horizontal rotation angle and the pitch adjustment angle of the double-sided detector array are adjusted by the motion control system and the array automatic adjustment mechanism; The position of each detector in the double-sided detector array within the plane where it is located is adjusted by the cooperation of the motion control system and the array automatic adjustment mechanism.

4. A self-tracking long-distance neutron source detection method suitable for a self-tracking long-distance neutron source detection device, characterized in that: include: Continuously using a first detector array of the double-sided detector array to determine a first collision point coordinate and a first energy value of each neutron incident on the detector, and using a second detector array of the double-sided detector array to determine a second collision point coordinate of the corresponding neutron incident on the detector after undergoing an elastic collision; Determining, using a data processing system, an elastic collision angle based on the flight time of the neutrons from the first detector array to the second detector array and the first energy value, and reconstructing a projection image of the neutron source on a designated plane based on the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron to obtain the azimuth coordinates of the neutron source, wherein the designated plane is any plane on a line connecting the center of a first plane corresponding to the first detector array and the center of a second plane corresponding to the second detector array; Using a motion control system and an array automatic adjustment mechanism, the double-sided detector array is controlled to perform horizontal rotation and pitch adjustment so that the azimuth coordinates of the first plane center, the second plane center, and the neutron source are in the same straight line; The adjusted double-sided detector array is used for re-detection to determine the distance to the neutron source, and the motion control system and the array automatic adjustment mechanism are used to adjust the arrangement parameters of the double-sided detector array, and the adjusted double-sided detector array is used for re-detection to obtain a reconstructed image of the neutron source.

5. The method according to claim 4, characterized in that Determining the elastic collision angle according to the flight time of the neutron from the first detector array to the second detector array and the first energy value includes: determining a neutron mass of the neutron, determining a flight time of the neutron from the first collision point coordinate to the second collision point coordinate, and determining a flight distance of the neutron based on the first collision point coordinate and the second collision point coordinate; The second energy value corresponding to the neutron is calculated according to the following formula: in, is the second energy value, is the neutron mass, is the flight distance, is the flight time; Calculating a ratio between the first energy value and the second energy value according to the following formula, calculating a square root of the ratio, and using an arc tangent of the square root as the elastic collision angle; ； in, is the first energy value, is the elastic collision angle, is the second energy value.

6. The method according to claim 4, characterized in that The method of reconstructing a projection image of a neutron source on a designated plane according to the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron to obtain the azimuth coordinates of the neutron source includes: Determine any plane on the line connecting the centers of the first plane and the second plane as a designated plane, reconstruct a conic curve based on the coordinates of the first collision point, the coordinates of the second collision point, and the elastic collision angle corresponding to each neutron, and project the conic curve onto the designated plane to obtain an ellipse equation; Divide the specified plane into multiple grids, and establish a straight line passing through the center of each grid along the specified coordinate axis. Substitute the straight line expression into the ellipse equation corresponding to each neutron to obtain the coordinates of the intersection of each ellipse and the straight line, and increment the grid pixel value where the intersection is located; The pixel values ​​of each grid are summed to obtain a projection image of the neutron source on the specified plane, and the azimuth coordinates of the neutron source are obtained according to the projection image.

7. The method according to claim 6, characterized in that The step of reconstructing a conic curve according to the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron, and projecting the conic curve onto the specified plane to obtain an ellipse equation includes: The equation of the ellipse is ; in, is the constant coefficient of the elliptic equation, is the elastic collision angle, and the coordinates of the first collision point are , the coordinates of the second collision point are , is the specified plane, is the distance between the first detector array and the second detector array.

8. The method according to claim 4, characterized in that The method comprises: using a motion control system and an automatic array adjustment mechanism to control the double-sided detector array to perform horizontal rotation and pitch adjustment so that the azimuth coordinates of the first plane center, the second plane center, and the neutron source are in the same straight line, including: calling a data processing system to send a parameter adjustment request to the motion control system according to the azimuth coordinates of the neutron source, and the motion control system controlling the double-sided detector array to perform horizontal rotation and pitch adjustment through the automatic array adjustment mechanism so that the azimuth coordinates of the first plane center, the second plane center, and the neutron source are in the same straight line.

9. The method according to claim 8, characterized in that The method of re-detecting with the adjusted double-sided detector array to determine the neutron source distance includes: re-detecting the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron with the adjusted double-sided detector array; determining the projection image of each neutron on each designated plane based on the first collision point coordinates, the second collision point coordinates, and the elastic collision angle corresponding to each neutron; determining a target plane with the highest imaging resolution among multiple designated planes; and determining the neutron source distance based on the coordinates of the target plane.

10. The method according to claim 9, characterized in that The method further comprises: The data processing system is called to send a parameter adjustment request to the motion control system based on the projection image of the target plane. The motion control system controls the adjustment of the spacing between the first detector array and the second detector array in the double-sided detector array through the array automatic adjustment mechanism, and adjusts the arrangement spacing of the detectors in the first detector array and the second detector array.

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