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

Abstract

The application discloses a self-tracking long-distance neutron source detection device and method, which can quickly obtain the accurate distance of a neutron source, and further reconstruct the three-dimensional space distribution of the neutron source, and improve the searching efficiency. The device comprises a detector double-sided array, a first detector array is used to determine the first collision point coordinates and the first energy value of each neutron incident to the detector, and a second detector array is used to determine the corresponding second collision point coordinates; a data processing system is used to determine the elastic collision angle, and according to the first collision point coordinates, the second collision point coordinates and the elastic collision angle of each neutron, the projection image of the neutron source on a specified plane is reconstructed, and the azimuthal coordinate of the neutron source is obtained; and a motion control system and an array automatic adjustment mechanism are used to control the detector double-sided array to perform horizontal rotation and pitch adjustment according to the azimuthal coordinate of the neutron source, and adjust the arrangement parameters of the detectors in the detector double-sided array, so that the reconstructed image of the neutron source is obtained.

Description

Technical Field

[0001] This application relates to the field of neutron detection technology, and in particular to a self-tracking long-distance neutron source detection device and method. Background Technology

[0002] With the development of nuclear energy and nuclear technology, the regulatory task of nuclear safety has become increasingly arduous. Among these tasks, the supervision and management of special nuclear materials is a crucial aspect of nuclear safety. Uranium and transuranic elements in special nuclear materials can release neutrons through spontaneous or induced fission. These neutrons can penetrate the shielding structure of high-Z materials. Therefore, the location of special nuclear materials within the shielding structure can be measured by detecting neutrons, and the location of special nuclear materials can be determined by measuring the neutron source position.

[0003] In related technologies, neutron detection mainly employs gas neutron detectors, such as He-3 counters, to perform static measurements of neutron sources. These devices generally have limited detection range, large size, low detection efficiency, and low detection accuracy, and cannot accurately locate or identify the type of neutron source. To meet the needs of customs and nuclear safety regulatory departments for large-scale neutron source inspections and rapid search for lost radioactive sources, a long-range dynamic neutron source detection device is urgently required. Summary of the Invention

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

[0005] According to a first aspect of this application, a self-tracking long-range neutron source detection device is provided, the device comprising: The detector consists of a dual-sided array, a data processing system, a motion control system, and an automatic array adjustment mechanism. The detector double-sided array uses a first detector array to determine the coordinates of the first collision point and the first energy value of each neutron incident on the detector, and uses a second detector array to determine the coordinates of the second collision point of the corresponding neutron after undergoing elastic collision. The first collision point coordinates, second collision point coordinates and first energy value corresponding to each neutron are transmitted to the 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. 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, the system reconstructs the projection image of the neutron source on the specified plane to obtain the azimuth coordinates of the neutron source. 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. The motion control system and array automatic adjustment mechanism control the detector double-sided array to perform horizontal rotation and pitch adjustment based on 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 on the same straight line, and adjust the arrangement parameters of the detectors in the detector double-sided array to obtain the reconstructed image of the neutron source.

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

[0007] Optionally, the distance between the plane where the first detector array and the plane where the second detector array are 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 its plane is adjusted by the motion control system and the array automatic adjustment mechanism.

[0008] According to a second aspect of this application, a self-tracking long-range neutron source detection method is provided, the method comprising: The first detector array in the double-sided detector array is continuously used to determine the coordinates of the first collision point and the first energy value of each neutron incident on the detector, and the second detector array in the double-sided detector array is used to determine the coordinates of the second collision point of the corresponding neutron after experiencing elastic collision. Using a data processing system, the elastic collision angle is determined based on the flight time of the neutron from the first detector array to the second detector array and the first energy value. Based on the coordinates of the first collision point, the second collision point, and the elastic collision angle corresponding to each neutron, the projection image of the neutron source on a specified plane is reconstructed to obtain the azimuth coordinates of the neutron source. 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. Using a motion control system and an array automatic adjustment mechanism, the detector's dual-sided array 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 aligned on the same straight line. The distance to the neutron source is determined by re-detecting using the adjusted double-sided array of detectors. The arrangement parameters of the double-sided array of detectors are adjusted using the motion control system and the array automatic adjustment mechanism. The reconstructed image of the neutron source is obtained by re-detecting using the adjusted double-sided array of detectors.

[0009] Optionally, the elastic collision angle is determined based on the flight time of the neutron from the first detector array to the second detector array and the first energy value, including: Determine the neutron mass, the flight time of the neutron from the coordinates of the first collision point to the coordinates of the second collision point, and the flight distance of the neutron based on the coordinates of the first and second collision points; The second energy value corresponding to the neutron is calculated using the following formula:

[0010] in, The second energy value, The mass of a neutron. For flight distance, For flight time; Calculate the ratio between the first energy value and the second energy value according to the following formula, and calculate the square root of the ratio. Use the arctangent of the square root as the elastic collision angle. ; in, The first energy value, For elastic collision angle, This is the second energy value.

[0011] Optionally, 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, a projection image of the neutron source on a specified plane is reconstructed to obtain the azimuth coordinates of the neutron source, including: Determine any plane as the designated plane on the line connecting the center of the first plane and the center of the second plane. Reconstruct the conic section 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. Project the conic section 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 expression of the straight line into the equation of the ellipse corresponding to each neutron to obtain the coordinates of the intersection point of each ellipse and the straight line, and increment the pixel value of the grid where the intersection point is located. Summing the pixel values ​​of each grid cell yields a projection image of the neutron source on a specified plane. Based on this projection image, the azimuth coordinates of the neutron source are obtained.

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

[0013] in, These are the constant coefficients of the ellipse equation. Given the elastic collision angle, the coordinates of the first collision point are: The coordinates of the second collision point are , For a specified plane, The distance between the first detector array and the second detector array is denoted as .

[0014] Optionally, the motion control system and the array automatic adjustment mechanism are used to control the detector's dual-sided array to perform horizontal rotation and pitch adjustment so that the center of the first plane, the center of the second plane, and the azimuth coordinates of the neutron source are aligned on a straight line. This includes: calling the data processing system to send a parameter adjustment request to the motion control system based on the azimuth coordinates of the neutron source; and the motion control system controlling the detector's dual-sided array to perform horizontal rotation and pitch adjustment through the array automatic adjustment mechanism so that the center of the first plane, the center of the second plane, and the azimuth coordinates of the neutron source are aligned on a straight line.

[0015] Optionally, the neutron source distance is determined by re-detecting using the adjusted double-sided array of detectors, including: re-detecting the coordinates of the first collision point, the coordinates of the second collision point, and the elastic collision angle corresponding to each neutron using the adjusted double-sided array of detectors; determining the projection image of each neutron on each specified plane 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; determining the 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 invoked to send a parameter adjustment request to the motion control system based on the projected image of the target plane. The motion control system then uses an array automatic adjustment mechanism to adjust the spacing between the first detector array and the second detector array in the double-sided detector array, as well as the arrangement spacing of the detectors within the first detector array and the second detector array.

[0017] By employing the above technical solutions, this application provides a self-tracking long-range neutron source detection device and method. This application proposes a neutron detection device with a double-sided array arranged front and rear. A two-dimensional image of the neutron source can be reconstructed with a single, fixed detection, quickly obtaining the neutron source's location. Furthermore, an algorithm searches for the optimal image reconstruction distance to quickly obtain the accurate distance to the neutron source, thereby reconstructing the three-dimensional spatial distribution of the neutron source. This ensures a further reduction in the neutron source search range and improves search efficiency. In addition, the embodiments of this application optimize the parameters of the distance between the front and rear detector array planes and the spacing between detectors within the array plane to improve imaging quality and obtain detailed information about the neutron source. This provides effective support for further accurate determination of the number and distribution of long-range neutron sources.

[0018] The above description is only an overview of the technical solution of this application. In order to better understand the technical means of this application and to implement it in accordance with the contents of the specification, and to make the above and other objects, features and advantages of this application more obvious and understandable, the following are specific embodiments of this application. Attached Figure Description

[0019] Various other advantages and benefits will become apparent to those skilled in the art upon reading the following detailed description of preferred embodiments. The accompanying drawings are for illustrative purposes only and are not intended to limit the scope of this application. Furthermore, the same reference numerals denote the same parts throughout the drawings. In the drawings: Figure 1 This illustration shows a schematic diagram of a self-tracking long-range neutron source detection device provided in an embodiment of this application; Figure 2 This illustration shows a flowchart of a self-tracking long-range neutron source detection method provided in an embodiment of this application. Figure 3 This illustration shows a flowchart of a self-tracking long-range neutron source detection method provided in an embodiment of this application. Figure 4 This illustration shows a schematic diagram of the imaging plane pixel grid division of a self-tracking long-range neutron source detection method provided in an embodiment of this application; Figure 5 The following is a simulation test result of neutron source detection imaging for a self-tracking long-range neutron source detection method provided in an embodiment of this application; Figure 6 The simulation test results of neutron source detection imaging for a self-tracking long-range neutron source detection method provided in this application embodiment are shown. Detailed Implementation

[0020] The embodiments of this application are described in detail below. Examples of these embodiments are shown in the accompanying drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below with reference to the accompanying drawings are exemplary and are only used to explain this application, and should not be construed as limiting this application.

[0021] Those skilled in the art will understand that, unless specifically stated otherwise, the singular forms “a,” “an,” “the,” and “the” used herein may also include the plural forms. It should be further understood that the word “comprising” as used in the specification of this application means the presence of the stated features, integers, steps, operations, elements, and / or components, but does not exclude 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 used herein (including technical and scientific terms) have the same meaning as commonly understood by one of ordinary skill in the art to which this application pertains. It should also be understood that terms such as those defined in general dictionaries should be understood to have the same meaning as in the context of the prior art, and should not be interpreted in an idealized or overly formal sense unless specifically defined as herein.

[0023] Those skilled in the art will understand that the term "terminal" as used herein includes both devices that are wireless signal receivers, devices that are wireless signal receivers without transmitting capability, and devices with receiving and transmitting hardware, having receiving and transmitting hardware capable of performing bidirectional communication on a bidirectional communication link. Such devices may include: cellular or other communication devices having a single-line display, a multi-line display, or a cellular or other communication device without a multi-line display; PCS (Personal Communications Service) that can combine voice, data processing, fax, and / or data communication capabilities; PDA (Personal Digital Assistant) that may include a radio frequency receiver, pager, Internet / intranet access, web browser, notepad, calendar, and / or GPS (Global Positioning System) receiver; and conventional laptop and / or handheld computers or other devices that have and / or include a radio frequency receiver. As used herein, "terminal" can be portable, transportable, installed in a means of transportation (air, sea, and / or land), or suitable and / or configured to operate locally, and / or in a distributed manner, operating in any other location on Earth and / or in space. "Terminal" as used herein can also be a communication terminal, an internet access terminal, or a music / video playback terminal, such as a PDA, a MID (Mobile Internet Device), and / or a mobile phone with music / video playback capabilities, or a smart TV, set-top box, etc.

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

[0025] 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. 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, it reconstructs the projection image of the neutron source on a specified plane to obtain the azimuth coordinates of the neutron source. 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 center of the first plane, the center of the second plane and the azimuth coordinates of the neutron source are on the same straight line, and adjust the arrangement parameters of the detectors in the detector double-sided array 1 to obtain the reconstructed image of the neutron source.

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

[0028] This application proposes a neutron detection device with a dual-array front-and-back arrangement. A single, fixed detection can reconstruct a two-dimensional image of the neutron source, quickly determining its location. Furthermore, an algorithm searches for the optimal image reconstruction distance to rapidly obtain the accurate distance to the neutron source, thereby reconstructing its three-dimensional spatial distribution. This further narrows the search range and improves search efficiency. In addition, this application's embodiments optimize the parameters of the distance between the front and rear detector array planes and the spacing between detectors within the array plane to improve imaging quality and obtain detailed information about the neutron source. This provides effective support for further accurate determination of the number and distribution of distant neutron sources.

[0029] This application provides a self-tracking long-range neutron source detection method, such as... Figure 2 As shown, the method includes: 201. The first detector array of the double-sided detector array is continuously used to determine the coordinates of the first collision point and the first energy value of each neutron incident on the detector, and the second detector array in the double-sided detector array is used to determine the coordinates of the second collision point of the corresponding neutron after experiencing elastic collision.

[0030] In this embodiment, the detector double-sided array comprises a first detector array and a second detector array with a spatial spacing, wherein the first detector array on a first plane and the second detector array on a second plane are parallel to each other and spaced apart. The planar distance between the first plane containing the first detector array and the second plane containing the second detector array is [missing information]. .like Figure 3 As shown, Neutrons emitted by a neutron source When the incident detector is a double-sided array, the first collision point of the first detector array is... With the detector's hydrogen nucleus An elastic collision occurs, and the detector measures the hydrogen nucleus via a photoelectric converter. The obtained neutron Part of the energy The neutrons that have completed the initial energy transfer continue to move along the scattering direction, passing through the predetermined planar spacing and reaching the second detector array, where they collide at the second point. It was detected by the detector.

[0031] 202. Using the data processing system, determine the elastic collision angle based on the flight time of the neutron from the first detector array to the second detector array and the first energy value. Also, 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, reconstruct the projection image of the neutron source on the specified plane to obtain the azimuth coordinates of the neutron source. 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.

[0032] In this embodiment of the application, the neutron mass of the neutron is first determined using a data processing system. This allows us to determine the coordinates of the neutron from the first collision point. Fly to the coordinates of the second collision point Flight time And determine the neutron's flight distance based on the coordinates of the first and second collision points. The neutron at the second collision point is calculated according to Formula 1 below. Second energy value .

[0033] Formula 1:

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

[0035] Formula 2:

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

[0037] Furthermore, any plane is defined on the line connecting the center of the first plane and the center of the second plane. As a designated plane, based on the coordinates of the first collision point corresponding to each neutron. Coordinates of the second collision point and elastic collision angle Reconstruct the conic section and project it onto the specified plane. The above yields the equation of the ellipse as shown in Formula 3 below: Formula 3:

[0038] in,

[0039] These are the constant coefficients of the ellipse equation. Let be the elastic collision angle, and let the coordinates of the first collision point be . The coordinates of the second collision point are , For the specified plane, The distance between the first detector array and the second detector array is denoted as .

[0040] Furthermore, such as Figure 4 As shown, the specified plane Divide the data into multiple pixel grids of equal size, and establish straight lines passing through the centers of each grid along a specified coordinate axis (such as the y-axis). , , Substituting the expression for the straight line into the equation of the ellipse corresponding to the neutron, we transform the ellipse equation into one about... The quadratic equation is used to determine the coordinates of the intersection points of each line and the ellipse. This leads to the grid cell containing each intersection point, and the pixel value of that grid cell is incremented by 1. This process is repeated to continuously probe the ellipse equation for each neutron, substituting the linear expression into the equation and adjusting the pixel values ​​of the corresponding grid cells. Finally, the pixel values ​​calculated for each grid cell in each neutron collision are summed to obtain the neutron source's position on the specified plane. The azimuth coordinates of the neutron source are obtained from the projected image. .

[0041] 203. Using a motion control system and an array automatic adjustment mechanism, the detector's double-sided array 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 on the same straight line.

[0042] In this embodiment of the application, the data processing system is based on the azimuth coordinates of the neutron source. It sends a parameter adjustment request to the motion control system, and tracks the orientation of the neutron source through the array automatic adjustment mechanism, that is, it performs horizontal rotation adjustment of the detector's double-sided array and records the angle. Adjust the pitch and record the angle. This makes the orientation coordinates of the center of the first plane, the center of the second plane, and the neutron source... The three points are on a straight line.

[0043] 204. Using the adjusted double-sided array of detectors, re-detect to determine the distance to the neutron source, and using the motion control system and array automatic adjustment mechanism to adjust the arrangement parameters of the double-sided array of detectors, and using the adjusted double-sided array of detectors to re-detect to obtain a reconstructed image of the neutron source.

[0044] In this embodiment of the application, the data processing system is based on and Re-determine the candidate plane set along the line connecting the center of the first plane and the center of the second plane, and then re-select any plane from the candidate plane set. As the designated plane, repeat steps 201 and 202 for iterative detection. Using the adjusted double-sided array of detectors, re-detect the coordinates of the first and second collision points and the elastic collision angle corresponding to each neutron. Based on these coordinates, determine the projection image of each neutron on each designated plane. Among multiple designated planes, determine the target plane with the highest imaging resolution. Then, based on the coordinates of the target plane, the neutron source distance is determined as... .

[0045] Furthermore, the data processing system can also send parameter adjustment requests to the motion control system based on the projected image of the target plane. The motion control system, through an automatic array adjustment mechanism, controls the adjustment of the spacing between the first and second detector arrays in the double-sided detector array, as well as the adjustment of the arrangement spacing of the detectors within the first and second detector arrays, so that... Imaging of a neutron source on a plane is optimal. Simulation and experimental test results of 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 was achieved.

[0046] The method provided in this application reconstructs a two-dimensional image of a neutron source using a single, fixed detection by neutron detection devices arranged in a double-sided array, quickly obtaining the neutron source's location. Furthermore, an algorithm searches for the optimal image reconstruction distance to rapidly obtain the accurate distance to the neutron source, thereby reconstructing the three-dimensional spatial distribution of the neutron source. This further narrows the neutron source search range and improves search efficiency. In addition, this application optimizes the parameters of the distance between the front and rear detector array planes and the spacing between detectors within the array plane to improve imaging quality and obtain detailed information about the neutron source. This provides effective support for further accurate determination of the number and distribution of distant neutron sources.

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

[0048] The present invention also provides a storage medium storing computer-readable instructions, which, when executed by one or more processors, cause the one or more processors to perform the steps of the data relationship reconstruction method of any of the above embodiments.

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

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

[0051] The above description is only a partial embodiment of this application. It should be noted that for those skilled in the art, several improvements and modifications can be made without departing from the principle of this application, and these improvements and modifications should also be considered within the scope of protection of this application.

Claims

1. A self-tracking long-range neutron source detection device, characterized in that, include: The detector consists of a dual-sided array, a data processing system, a motion control system, and an automatic array adjustment mechanism. The detector double-sided array uses a first detector array to determine the coordinates of the first collision point and the first energy value of each neutron incident on the detector, and uses a second detector array to determine the coordinates of the second collision point of the corresponding neutron after undergoing elastic collision. The first collision point coordinates, second collision point coordinates and the first energy value corresponding to each neutron are transmitted to the 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. 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, the system reconstructs the projection image of the neutron source on a specified plane to obtain the azimuth coordinates of the neutron source. 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. The motion control system and the array automatic adjustment mechanism control the detector double-sided 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 on the same straight line, and adjust the arrangement parameters of the detectors in the detector double-sided array to obtain the reconstructed image of the neutron source. Determining the elastic collision angle based on the neutron's flight time from the first detector array to the second detector array and the first energy value includes: The neutron mass of the neutron is determined, the flight time of the neutron from the coordinates of the first collision point to the coordinates of the second collision point is determined, and the flight distance of the neutron is determined based on the coordinates of the first collision point and the coordinates of the second collision point; The second energy value corresponding to the neutron is calculated according to the following formula: in, This is the second energy value. The mass of the neutron is... The flight distance is... The flight time; The ratio between the first energy value and the second energy value is calculated according to the following formula, and the square root of the ratio is calculated. The arctangent of the square root is taken as the elastic collision angle. ； in, The first energy value, The elastic collision angle is... This is the second energy value; The step of reconstructing the projection image of the neutron source on a specified plane 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, to obtain the azimuth coordinates of the neutron source, includes: Determine any plane as a designated plane on the line connecting the center of the first plane and the center of the second plane. Reconstruct the conic section 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. Project the conic section onto the designated plane to obtain the ellipse equation. The specified plane is divided into multiple grids, and a straight line passing through the center of each grid is established along the specified coordinate axis. The expression of the straight line is substituted into the ellipse equation corresponding to each neutron to obtain the coordinates of the intersection point of each ellipse and the straight line. The pixel value of the grid where the intersection point is located is incremented. The pixel values ​​of each grid are summed to obtain the projection image of the neutron source on the specified plane. The azimuth coordinates of the neutron source are obtained based on the projection image.

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

3. The self-tracking long-range neutron source detection device according to claim 2, characterized in that, The distance between the plane containing the first detector array and the plane containing the second detector array in the dual-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 detector's dual-sided array are adjusted by the motion control system and the array's automatic adjustment mechanism. The position of each detector in the dual-sided array is adjusted within its plane by the motion control system and the array automatic adjustment mechanism.

4. A method for detecting a self-tracking long-range neutron source suitable for a self-tracking long-range neutron source detection device, characterized in that, include: The first detector array of the double-sided detector array is continuously used to determine the coordinates of the first collision point and the first energy value of each neutron incident on the detector, and the second detector array in the double-sided detector array is used to determine the coordinates of the second collision point of the corresponding neutron after experiencing an elastic collision. Using a data processing system, the elastic collision angle is determined based on the flight time of the neutron from the first detector array to the second detector array and the first energy value. 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, the projection image of the neutron source on a specified plane is reconstructed to obtain the azimuth coordinates of the neutron source. 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. Using a motion control system and an array automatic adjustment mechanism, the detector's dual-sided array 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 aligned on the same straight line. The distance to the neutron source is determined by re-detecting using the adjusted double-sided array of detectors, and the arrangement parameters of the double-sided array of detectors are adjusted using the motion control system and the array automatic adjustment mechanism. The reconstructed image of the neutron source is obtained by re-detecting using the adjusted double-sided array of detectors. Determining the elastic collision angle based on the neutron's flight time from the first detector array to the second detector array and the first energy value includes: The neutron mass of the neutron is determined, the flight time of the neutron from the coordinates of the first collision point to the coordinates of the second collision point is determined, and the flight distance of the neutron is determined based on the coordinates of the first collision point and the coordinates of the second collision point; The second energy value corresponding to the neutron is calculated according to the following formula: in, This is the second energy value. The mass of the neutron is [value missing]. The flight distance is... The flight time; The ratio between the first energy value and the second energy value is calculated according to the following formula, and the square root of the ratio is calculated. The arctangent of the square root is taken as the elastic collision angle. ； in, The first energy value, The elastic collision angle is... This is the second energy value; The step of reconstructing the projection image of the neutron source on a specified plane 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, to obtain the azimuth coordinates of the neutron source, includes: Determine any plane as a designated plane on the line connecting the center of the first plane and the center of the second plane. Reconstruct the conic section 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. Project the conic section onto the designated plane to obtain the ellipse equation. The specified plane is divided into multiple grids, and a straight line passing through the center of each grid is established along the specified coordinate axis. The expression of the straight line is substituted into the ellipse equation corresponding to each neutron to obtain the coordinates of the intersection point of each ellipse and the straight line. The pixel value of the grid where the intersection point is located is incremented. The pixel values ​​of each grid are summed to obtain the projection image of the neutron source on the specified plane. The azimuth coordinates of the neutron source are obtained based on the projection image.

5. The method according to claim 4, characterized in that, The process of reconstructing a conic section 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 projecting the conic section onto the specified plane to obtain the equation of an ellipse, includes: The equation of the ellipse is: ; in, These are the constant coefficients of the ellipse equation. Let be the elastic collision angle, and let the coordinates of the first collision point be . The coordinates of the second collision point are , For the specified plane, The distance between the first detector array and the second detector array is denoted as .

6. The method according to claim 4, characterized in that, The method of using a motion control system and an automatic array adjustment mechanism to control the detector's dual-sided array to perform horizontal rotation and pitch adjustment so that the center of the first plane, the center of the second plane, and the azimuth coordinates of the neutron source are aligned on a straight line includes: calling a data processing system to send a parameter adjustment request to the motion control system based on the azimuth coordinates of the neutron source; and the motion control system controlling the detector's dual-sided array to perform horizontal rotation and pitch adjustment through the automatic array adjustment mechanism so that the center of the first plane, the center of the second plane, and the azimuth coordinates of the neutron source are aligned on a straight line.

7. The method according to claim 6, characterized in that, The step of re-detecting using the adjusted double-sided array of detectors to determine the neutron source distance includes: re-detecting the coordinates of the first collision point, the coordinates of the second collision point, and the elastic collision angle corresponding to each neutron using the adjusted double-sided array of detectors; determining the projection image of each neutron on each specified plane 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; determining the 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.

8. The method according to claim 7, characterized in that, The method further includes: The data processing system is invoked to send a parameter adjustment request to the motion control system based on the projected image of the target plane. The motion control system then uses an array automatic adjustment mechanism to adjust the spacing between the first detector array and the second detector array in the double-sided detector array, as well as the arrangement spacing of the detectors within the first detector array and the second detector array.

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