Multi-shell single-sphere neutron energy spectrum measurement device and method and electronic equipment

Abstract

The invention relates to the technical field of neutron energy spectrum measurement, and provides a multi-shell single-sphere neutron energy spectrum measurement device and method and electronic equipment, and the multi-shell single-sphere neutron energy spectrum measurement device comprises a moderated sphere, a light release light detector and a light release light reading system. After one-time measurement is completed, light intensity signals of all the light release light detectors only need to be read out through the light release light read-out system, the read-out signals are solved through the response matrix, and then the neutron energy spectrum can be obtained. The multi-sphere neutron spectrometer solves the defects that a multi-sphere neutron spectrometer is large in sphere number and large in size and weight, more importantly, a plurality of signal collection and data acquisition systems of a traditional single-sphere spectrometer do not exist, and the technical effects that the device is simpler in structure, higher in integration degree and convenient to carry are achieved.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of neutron spectrum measurement, and relates to a multi-shell single-ball neutron spectrum measurement device, method and electronic equipment. BACKGROUND

[0002] The multi-ball spectrometer method is an important method for measuring neutron spectrum, and has the advantages of isotropic response and wide energy spectrum coverage. 3 The basic principle is that neutrons of different energies are slowed down by different diameter slow-down balls (usually made of polyethylene material), and the energy is slowed down to become thermal neutrons. The thermal neutrons are detected by a thermal neutron detector (such as a He proportional counter) placed at the center of the ball, and a signal is generated. Then, the signal is analyzed by a pre-established neutron response matrix of different energies to solve the neutron energy entering the different slow-down balls, thereby completing the measurement of the neutron spectrum.

[0003] The multi-ball spectrometer has the disadvantages of a large number of balls, a large volume, and the need to replace different size balls multiple times during the measurement process. In order to solve this problem, researchers have developed a single-ball neutron spectrometer, which has a similar basic principle to the multi-ball spectrometer. The difference between the single-ball neutron spectrometer and the multi-ball neutron spectrometer is that the thermal neutron detector is not placed at the center of each slow-down ball, but at a single ball at different radial depths, so that the thermal neutron detector can detect the neutrons after different slow-down degrees. The single-ball neutron spectrometer only needs to be irradiated once, solving the problem of multiple irradiations and measurements of the multi-ball spectrometer, as well as the problem of large volume and weight. However, there are still the following disadvantages: each position of the thermal neutron detector needs a set of signal measurement and data acquisition equipment connected thereto, resulting in a large number of instrument components, complex integration, and inconvenience for portable use. This is not conducive to the further miniaturization and portability of the single-ball neutron spectrometer, which in turn limits the use of the single-ball neutron spectrometer in some special environments and narrow spaces.

[0004] Therefore, there is an urgent need for a multi-shell single-ball neutron spectrum measurement scheme with simple structure and high integration. SUMMARY

[0005] The present application provides a multi-shell single-ball neutron spectrum measurement device, method and electronic equipment to solve at least one problem in the prior art.

[0006] To achieve the above-mentioned purpose, in a first aspect, the present application provides a multi-shell single-ball neutron spectrum measurement device, comprising: a slow-down ball, a photoluminescence detector and a photoluminescence readout system.

[0007] The slow-down ball is composed of N slow-down shells nested in the same center in order of decreasing diameter; the slow-down shell is a hollow ball; the thickness of each slow-down shell is the same; N≥2.

[0008] The photoluminescence detector is used for detecting neutrons based on the photoluminescence principle; along the same radial direction of the moderator sphere, photoluminescence detectors are arranged on the inner surface of each moderator shell and the outer surface of the outermost moderator shell;

[0009] The photoluminescence readout system is used for receiving the detection signals of the photoluminescence detectors and obtaining the light intensity count of the photoluminescence detectors.

[0010] Optionally, the moderator sphere is composed of N pairs of nested half-sphere shells; one pair of half-sphere shells with the same diameter forms a moderator shell.

[0011] Optionally, the photoluminescence detector includes a photoluminescence neutron detector and a photoluminescence gamma detector arranged side by side; the photoluminescence neutron detector is used for detecting neutron rays and gamma rays; the photoluminescence gamma detector is used for detecting gamma rays.

[0012] Optionally, the photoluminescence neutron detector includes a plastic pressing sheet and a photoluminescence neutron detection pressing sheet; the photoluminescence neutron detection pressing sheet is sandwiched between the two plastic pressing sheets to form a sandwich structure; the photoluminescence neutron detection pressing sheet is made of a photoluminescence neutron detection material; the photoluminescence gamma detector includes a plastic pressing sheet and a photoluminescence gamma detection pressing sheet; the photoluminescence gamma detection pressing sheet is sandwiched between the two plastic pressing sheets to form a sandwich structure; the photoluminescence gamma detection pressing sheet is made of a photoluminescence gamma detection material.

[0013] Optionally, the photoluminescence neutron detection material includes a photoluminescence material and a neutron conversion material; the mass ratio of the photoluminescence material to the neutron conversion material is 2-3:2-3; the neutron conversion material is 6 LiF or 6 Li2CO3. The photoluminescence gamma detection material includes a photoluminescence material and a lithium compound; the mass ratio of the photoluminescence material to the lithium compound is 2-3:2-3; the lithium compound is 7 LiF or 7 Li2CO3.

[0014] Secondly, the present invention provides a method for measuring the neutron energy spectrum of a multi-shell single-sphere neutron, used to perform neutron energy spectrum measurements using the multi-shell single-sphere neutron energy spectrum measuring device described above. The method includes: establishing a planar monoenergetic neutron source; establishing a geometric model of the single-sphere neutron energy spectrum measuring instrument based on a particle transport simulation program; defining the single-sphere neutron energy spectrum measuring instrument according to the multi-shell single-sphere neutron energy spectrum measuring device; and using the particle transport simulation program to simulate the monoenergetic neutron and the shells of each moderated sphere in the single-sphere neutron energy spectrum measuring instrument, as well as each optical... The physical processes of interaction between the optically stimulated luminescence (OSL) neutron detectors in the OSL detector are analyzed to obtain the response matrix. A multi-shell single-sphere neutron energy spectrum measurement device is placed in a neutron radiation field, with the OSL detectors facing the neutron source. After irradiating the multi-shell single-sphere neutron energy spectrum measurement device with the neutron source for a set time, the OSL detectors are removed, and the light intensity counts of each OSL detector are read out using an OSL readout system. Based on the response matrix and the light intensity counts of each OSL detector, the energy spectrum of the neutron source is obtained using a neutron energy spectrum despectroscopy algorithm.

[0015] One optional approach is to determine the response matrix using the following formula:

[0016] R j (E i ) = C j (E i ) / Φ;

[0017] Where i = 1, 2, 3, 4, ..., n, represents the energy of the n incident neutrons; j = 1, 2, 3, 4, ..., N+1, represents the energy of the N+1 optically stimulated neutron detectors; C j (E i () indicates that the energy of the incident neutron is E i At that time, the j-th optically stimulated neutron detector in the single-sphere spectrometer reacts with the incident neutron. 6 Li(n, a) 3 The number of H reactions; Φ represents the fluence of incident neutrons.

[0018] One optional approach is that the optically stimulated light detector includes an optically stimulated light neutron detector and an optically stimulated light gamma detector arranged side by side.

[0019] After obtaining the response matrix, before irradiating the multi-shell single-sphere neutron energy spectrum measurement device with a neutron source, all optically stimulated light neutron detectors and optically stimulated light gamma detectors in the multi-shell single-sphere neutron energy spectrum measurement device are exposed to sunlight using a light source of a preset wavelength to reduce the background signal of the optically stimulated light detectors.

[0020] The response count ratio of the photoluminescence neutron detector and the photoluminescence gamma detector to gamma irradiation is obtained by simultaneously irradiating the photoluminescence neutron detector and the photoluminescence gamma detector with a gamma radiation source using any photoluminescence detector;

[0021] The multi-shell single-sphere neutron spectrum measurement device is placed in a neutron radiation field, and the photoluminescence neutron detector and the photoluminescence gamma detector are directly opposite the neutron source; after the multi-shell single-sphere neutron spectrum measurement device is irradiated for a set time by the neutron source, the photoluminescence neutron detector and the photoluminescence gamma detector are taken out, and the light intensity count of each photoluminescence neutron detector and the light intensity count of each photoluminescence gamma detector are read out by a photoluminescence readout system, respectively;

[0022] Based on the response count ratio of the photoluminescence neutron detector and the photoluminescence gamma detector to gamma irradiation, the light intensity count of each photoluminescence neutron detector, and the light intensity count of each photoluminescence gamma detector, the net light intensity count of each photoluminescence neutron detector to neutron irradiation is obtained.

[0023] Based on the response matrix and the net light intensity count of each photoluminescence neutron detector to neutron irradiation, the neutron spectrum of the neutron source is obtained by using a neutron spectrum deconvolution algorithm.

[0024] Optionally, the response count ratio A of the photoluminescence neutron detector and the photoluminescence gamma detector to gamma irradiation is obtained by the following formula,

[0025] A = S 6，γ / S 7，γ ;

[0026] S 6，γ is the response count of the photoluminescence neutron detector after irradiation by the gamma radiation source; and S 7，γ is the response count of the photoluminescence gamma detector after irradiation by the gamma source.

[0027] Based on the response count ratio of the photoluminescence neutron detector and the photoluminescence gamma detector to gamma irradiation, the light intensity count of each photoluminescence neutron detector, and the light intensity count of each photoluminescence gamma detector, the net light intensity count of each photoluminescence neutron detector to neutron irradiation is obtained by the following formula,

[0028] S (6，n),j = S (6，n+γ)，j -(A x S (7，n+γ)，j ).

[0029] S (6，n),j is the net light intensity count of each photoluminescence neutron detector to neutron irradiation; A is the response count ratio of the photoluminescence neutron detector and the photoluminescence gamma detector to gamma irradiation; and S (6，n+γ)，j is the light intensity count of each photoluminescence neutron detector; S (7，n+γ)，j j is the light intensity count of each photoluminescence neutron detector; S

[0030] In order to solve the above problems, the third aspect of the present application also provides an electronic device, comprising: at least one processor; and a memory connected in communication with the at least one processor; wherein the memory stores instructions executable by the at least one processor, and the instructions are executed by the at least one processor to enable the at least one processor to perform the steps of the multi-shell single-sphere neutron spectrum measurement method described above.

[0031] The multi-shell single-sphere neutron spectrum measurement device, method and electronic device of the present application mainly consist of a concentric multi-shell neutron moderator sphere, a plurality of photoluminescence detectors made of a mixture of photoluminescence material and neutron conversion material, and a photoluminescence readout system. Among them, the plurality of photoluminescence neutron detectors are placed on the surface of the spherical shell at different radii in the radial direction, so that the neutrons are moderated by the shell layer material of different thicknesses and then detected by the neutron detectors. After a measurement is completed, only the light intensity signals of each photoluminescence neutron detector need to be read out by a general photoluminescence readout system, and the signals read out are solved by a response matrix to obtain the neutron spectrum. The present application not only solves the defects of multiple spheres in the neutron spectrometer, large volume and weight, but more importantly, there is no multiple signal collection and data acquisition system in the traditional single-sphere spectrometer, which realizes a simpler device structure, higher integration and convenient portability. BRIEF DESCRIPTION OF DRAWINGS

[0032] Figure 1 A structural schematic diagram of a multi-shell single-sphere neutron spectrum measurement device provided by an embodiment of the present application;

[0033] Figure 2 A structural schematic diagram of a photoluminescence detector provided by an embodiment of the present application;

[0034] Figure 3 A principle schematic diagram of a multi-shell single-sphere neutron spectrum measurement method provided by an embodiment of the present application;

[0035] Figure 4 A response diagram of a photoluminescence neutron detector at different distances from the center of the sphere under different energy mono-energetic neutron irradiation conditions provided by an embodiment of the present application;

[0036] Figure 5 A structural schematic diagram of an electronic device of a multi-shell single-sphere neutron spectrum measurement method provided by an embodiment of the present application;

[0037] The implementation, functional features and advantages of the present application will be further described with reference to the embodiments and the accompanying drawings. DETAILED DESCRIPTION

[0038] It should be understood that the specific embodiments described herein are merely exemplary and not intended to limit the application.

[0039] Embodiment 1

[0040] The application provides a multi-shell single-sphere neutron energy spectrum measuring device, comprising: a moderating sphere, a photoluminescence detector, and a photoluminescence reading system; the moderating sphere is composed of N moderating spherical shells nested in sequence according to the same center and in the order of decreasing diameter; the moderating spherical shell is a hollow sphere; the thickness of each moderating spherical shell is the same; N≥2; the photoluminescence detector is used for detecting neutrons based on the photoluminescence principle; that is, the photoluminescence detector only comprises a photoluminescence neutron detector; along the same radial direction of the moderating sphere, the photoluminescence detector is arranged on the inner surface of each moderating spherical shell and the outer surface of the outermost moderating spherical shell; and the photoluminescence reading system is used for receiving the detection signal of the photoluminescence detector and obtaining the light intensity count of the photoluminescence detector.

[0041] It should be noted that the sensitivity of photoluminescence is higher than that of thermoluminescence, that is, the photoluminescence intensity is higher than the thermoluminescence intensity under the same charged particle energy deposition, or in other words, if the energy deposition is particularly small, photoluminescence can generate a luminescence signal, while thermoluminescence may not generate a luminescence signal. Such sensitivity is advantageous for measuring high-energy neutrons. The moderating spherical shell is made of polyethylene. The N moderating spherical shells that constitute the moderating sphere are relatively fixed. Adjacent moderating spherical shells can be connected and fixed by connecting rods with a fixed length. The specific fixing methods can be screwing, buckling, pinning, and bonding. As long as the moderating spherical shells are arranged in the same manner, they can be nested in the same manner. In the specific implementation process, the number of N is set according to the actual scene, and generally N≤15.

[0042] Compared with the disadvantages of non-repetitive reading, slow reading speed, and the need for high-temperature reading and annealing in the process of detecting neutron signals by the thermoluminescence principle, the application adopts the photoluminescence principle to prepare a photoluminescence detector and establish a response matrix corresponding to photoluminescence to obtain a multi-shell single-sphere neutron energy spectrum measuring device as a single-sphere neutron spectrometer. Specifically, the photoluminescence detector can react with neutrons and generate a considerable number of luminescence signals.

[0043] As an improvement of the embodiment, the moderating sphere is composed of N pairs of nested half-spherical shells; one pair of half-spherical shells with the same diameter constitutes a moderating spherical shell. In order to facilitate the arrangement of the photoluminescence detector, the moderating sphere is arranged as two half-spheres, and each half-sphere is formed by N half-spherical shells nested at equal intervals. Figure 1 The structure diagram of the multi-shell single-sphere neutron energy spectrum measuring device provided by the embodiment of the application is shown in Figure 1. Figure 1As shown, along the same radial direction of the moderator sphere 1, the photostimulated luminescence detector 2 is arranged on the inner surface of each moderator shell and the outer surface of the outermost moderator shell. It should be noted that the photostimulated luminescence detector 2 can be arranged on the inner surface of each moderator shell and the outer surface of the outermost moderator shell through various mechanical connections, or can be arranged by pasting.

[0044] For the N moderator shells of the moderator sphere, the diameter of the largest moderator shell is X cm, and the diameter of the smallest moderator shell is Y cm, Y can be 1-2 cm; the thickness of each moderator shell is (X-Y) / 2N; in the specific implementation process, the size of X can be determined according to the maximum neutron energy of the actually measured neutron spectrum, and X is 25-35 cm. Wherein, N+1 is the number of photostimulated luminescence detectors 2.

[0045] The photostimulated luminescence detector 2 can be a sheet structure; the material of the photostimulated luminescence detector 2 includes a photostimulated luminescence material and a neutron conversion material. Specifically, the neutron conversion material is mainly responsible for reacting with neutrons to produce charged ions; the photostimulated luminescence material is responsible for depositing the energy of the generated charged ions in the photostimulated luminescence material; and the photostimulated luminescence neutron detector is mixed by the neutron conversion material and the photostimulated luminescence material.

[0046] In the specific implementation process, the photostimulated luminescence material can be α-Al2O3:C. The neutron conversion material can be 6 LiF or 6 Li2CO3. The mass ratio of the photostimulated luminescence material and the neutron conversion material is 2-3:2-3. The photostimulated luminescence detector can be a circular tablet, a square tablet, a triangular tablet, a rhombic tablet or an irregular tablet. Preferably, the photostimulated luminescence detector 2 is a circular tablet. In the specific implementation process, the diameter D of the photostimulated luminescence detector circular tablet, 5mm≤D≤10mm.

[0047] In summary, the multi-shell single-ball neutron energy spectrum measuring device of the present application mainly comprises a concentric multi-shell neutron moderator ball, a plurality of photoluminescence neutron detectors made of mixed photoluminescence material and neutron conversion material, and a photoluminescence reading system. The plurality of photoluminescence neutron detectors are arranged on the surfaces of the shells at different radii in the radial direction, so that the neutrons are moderated by the shell materials of different thicknesses and then detected by the neutron detectors. The detection signals of the plurality of photoluminescence neutron detectors are read by the photoluminescence reading system, and the signals are solved by a response matrix to obtain the neutron energy spectrum. The present application not only solves the defects of the multi-ball neutron spectrometer, such as a large number of balls, large volume and heavy weight, but more importantly, it does not have the multiple signal collection and data acquisition system of the traditional single-ball spectrometer, and the device structure is simpler and more convenient and portable. Moreover, after a measurement is completed, only the light intensity signals of the photoluminescence neutron detectors need to be read by the general photoluminescence reading system, which greatly improves the convenience of the operation of the neutron spectrometer. At the same time, the photoluminescence principle (passive detection method) is used to collect the neutron detection signals, which has the advantages of fast reading speed, multiple reading and repeated use, and no need for annealing device, compared with the traditional thermoluminescence which cannot be repeatedly read, has a slow reading speed, and needs high-temperature reading and annealing. Therefore, the operation process of the single-ball neutron energy spectrum measuring device is further simplified, and the neutron energy spectrum measurement efficiency is improved.

[0048] Example 2

[0049] The present application provides a kind of multi-shell single-ball neutron energy spectrum measuring device, comprising: moderator ball, photoluminescence detector and photoluminescence reading system;The moderator ball is sequentially nested by N moderator shells according to the diameter from small to large same center;The moderator shell is hollow sphere;The thickness of each moderator shell is same;N≥2;The moderator ball is composed of N pairs of half shell body nesting each other;A pair of half shell body with same diameter forms a moderator shell.The photoluminescence detector is used to detect neutron based on photoluminescence principle;Along the same radial direction of the moderator ball, photoluminescence detector is arranged on the inner surface of each moderator shell and the outer surface of the outermost moderator shell;The photoluminescence reading system is used to receive the detection signal of the photoluminescence detector and obtain the light intensity count of photoluminescence detector.The moderator shell is made of polyethylene.The N moderator shells of the moderator ball are relatively fixed.

[0050] For the N moderator shells of the moderator ball, the diameter of the largest shell is X cm, the diameter of the smallest shell is Y cm, and the thickness of each shell is (X-Y) / 2N;The size of X can be determined according to the maximum neutron energy of the actual measured neutron spectrum, and in the specific implementation process, X is 25cm-35cm. Wherein, N+1 is the number of photoluminescence detectors.

[0051] Figure 2This is a schematic diagram of the structure of an optically stimulated light detector provided in an embodiment of the present invention; as shown. Figure 2 As shown, the optically stimulated luminescence (OSL) detector includes an OSL neutron detector and an OSL gamma detector arranged side-by-side. The OSL neutron detector is used to detect neutron rays and gamma rays, while the OSL gamma detector is used to detect gamma rays. It should be noted that, since neutron radiation fields generally have a certain gamma radiation background, in this embodiment, to remove gamma ray interference signals and improve the accuracy of neutron measurements, the OSL detector includes two detectors: an OSL neutron detector and an OSL gamma detector. That is, side-by-side arrangement means that the OSL neutron detector and the OSL gamma detector are placed at the same neutron detection point on the same slowed-down spherical shell. The OSL neutron detector and the OSL gamma detector are simultaneously irradiated by the same neutron source. Therefore, in the specific implementation process, the distance between the OSL neutron detector and the OSL gamma detector needs to be minimized. Specifically, in order to identify and remove gamma-ray signals in the neutron radiation field when measuring the neutron energy spectrum and improve the accuracy of the neutron energy spectrum, two optically stimulated luminescence (OSL) detectors need to be deployed simultaneously at each measurement point in the shell of the sphere. One is an OSL neutron detector, which is sensitive to both neutrons and gamma rays, so the detector's output signal is the sum of the output signals of both neutrons and gamma rays; the other is an OSL gamma detector, which is only sensitive to gamma rays, so its output signal only contains gamma-ray signals. In other words, the arrangement of the optically stimulated light neutron detector and the optically stimulated light gamma detector in the multi-shell single-sphere neutron energy spectrum measurement device is as follows: along the same radial direction of the sphere, on the inner surface of each moderated spherical shell, one optically stimulated light neutron detector and one optically stimulated light gamma detector are arranged in parallel pairs, with a total of N pairs of optically stimulated light detectors arranged on the inner surface of each moderated spherical shell; the remaining pair of optically stimulated light neutron detectors and optically stimulated light gamma detectors are arranged on the outer surface of the outermost moderated spherical shell, and are in the same radial direction as the other N pairs of optically stimulated light detectors.

[0052] The optically stimulated light neutron detector is made of an optically stimulated light neutron detection material; the optically stimulated light neutron detection material includes an optically stimulated light material and a neutron conversion material; the optically stimulated light material can be α-Al₂O₃:C. The neutron conversion material can be... 6 LiF or 6 Li2CO3; as the optimal choice for achieving the best optically stimulated luminescence effect, the mass ratio of the optically stimulated luminescence material to the neutron conversion material is 1:1.

[0053] The optically stimulated luminescence (OSL) gamma detector is made of an OSL gamma detection material; the OSL gamma detection material includes an OSL material and a lithium compound; the lithium compound is... 7 LiF or 7 Li2CO3. As the optimal choice for achieving the best optically stimulated luminescence (OSL) effect, the mass ratio of the OSL material to the lithium compound is 1:1.

[0054] It should be noted that the existing photoluminescence measurement method is mainly based on the detection of gamma rays by alpha-Al2O3:C material, and photoluminescence measurement methods for neutron detection are rarely seen. The present application prepares a photoluminescence neutron detector, so that the reaction of neutrons with the photoluminescence neutron detector can produce a considerable amount of luminescence signal, so as to realize the use of photoluminescence detection technology for neutron spectrum measurement.

[0055] As an improvement of the present embodiment, in order to improve the connection stability of the photoluminescence neutron detector in one step, the photoluminescence neutron detector comprises plastic pressing sheets and a photoluminescence neutron detection pressing sheet; that is, the photoluminescence neutron detection pressing sheet is clamped between the two plastic pressing sheets to form a sandwich structure; and the photoluminescence neutron detection pressing sheet is made of photoluminescence neutron detection material. The plastic pressing sheet is a transparent sheet prepared from polyethylene. The uniformly mixed photoluminescence neutron detection material is pressed and formed into a sheet, and the sheet is packaged between two plastic sheets to form a sandwich structure of the photoluminescence neutron detector.

[0056] It should be noted that the photoluminescence neutron detection pressing sheet and the upper and lower plastic pressing sheets can be fixed by pasting to form a sandwich structure, and then the bottom of the lower plastic pressing sheet is set to be pasted and fixed on the inner surface of each slow neutron shell and the outer surface of the outermost slow neutron shell. The size of the upper and lower plastic pressing sheets can be consistent with that of the photoluminescence neutron detection pressing sheet, or the size of the upper and lower plastic pressing sheets can be larger than that of the photoluminescence neutron detection pressing sheet, or the size of the upper and lower plastic pressing sheets can be smaller than that of the photoluminescence neutron detection pressing sheet. No specific limitation is made here. In the present embodiment, the thickness of the plastic sheet is 0.05mm, and the diameter is 5mm-10mm.

[0057] As an improvement of the embodiment, in order to improve the connection stability of the photoluminescence gamma detector, the photoluminescence gamma detector comprises a plastic pressing sheet and a photoluminescence gamma detection pressing sheet; the photoluminescence gamma detection pressing sheet is clamped in the middle of the two plastic pressing sheets to form a sandwich structure; and the photoluminescence gamma detection pressing sheet is made of photoluminescence gamma detection material. The photoluminescence gamma detection material after uniform mixing is pressed and formed into a sheet, and the sheet is packaged in the middle of two plastic sheets to form a sandwich structure photoluminescence gamma detector. It should be noted that after the photoluminescence gamma detection pressing sheet and the upper and lower plastic pressing sheets are fixed by pasting to form a sandwich structure, a pasting position is arranged at the bottom of the lower plastic pressing sheet, and the photoluminescence neutron detection pressing sheet is pasted and fixed side by side on the inner surface of each moderator spherical shell and the outer surface of the outermost moderator spherical shell. As a preferred mode, a groove or hole with the same size as the photoluminescence gamma detector and the photoluminescence neutron detector is arranged at the detection position on the inner surface of each moderator spherical shell and the outer surface of the outermost moderator spherical shell, and the photoluminescence gamma detector and the photoluminescence neutron detector are accommodated in the corresponding groove or hole.

[0058] The photoluminescence neutron detector and the photoluminescence gamma detector in the sandwich structure are both circular, with a diameter D of 5mm≤D≤10mm and a thickness T of 0.1mm≤T≤0.2mm.

[0059] Embodiment 3

[0060] Referring to Figure 3 Fig. 1 shows a flowchart of a multi-shell single-sphere neutron energy spectrum measurement method provided by an embodiment of the present application. The present application provides a multi-shell single-sphere neutron energy spectrum measurement method for measuring the neutron energy spectrum by using the multi-shell single-sphere neutron energy spectrum measurement device described in Embodiment 1. The method can be executed by a system, which can be realized by software and / or hardware.

[0061] In the embodiment, the multi-shell single-sphere neutron energy spectrum measurement method comprises steps S110-S140.

[0062] S110, a planar single-energy neutron source is established.

[0063] The neutron energy emitted by the planar neutron source is E i (i=1, 2, 3, 4………n), i is the number of set single-energy neutron energy points; the length of the planar single-energy neutron source is L cm, the width is M cm, and L≥X; M≥X. The neutron source can be 137 C s equivalent gamma radiation source.

[0064] S120, a geometric model of the single-sphere neutron energy spectrum measuring instrument is established based on a particle transport simulation program; the single-sphere neutron energy spectrum measuring instrument is defined according to the multi-shell single-sphere neutron energy spectrum measuring device; and the interaction physical processes of mono-energetic neutrons and each shell layer of the single-sphere neutron energy spectrum measuring instrument and the photoluminescence neutron detector in each photoluminescence detector are simulated respectively by using the particle transport simulation program, so as to obtain a response matrix.

[0065] Specifically, the geometric model of the single-sphere spectrometer is established by using the particle transport simulation program. The size of the geometric model is consistent with the actual size of the single-sphere spectrometer, and the material of the geometric model is polyethylene. The geometric shape, size, element composition, density and specific coordinate position of each photoluminescence neutron detector are defined in the geometric model. The distance between the planar mono-energetic neutron source and the geometric model of the single-sphere spectrometer is set to K cm, and the medium between the planar mono-energetic neutron source and the geometric model of the single-sphere spectrometer is set to air. The interaction physical processes of mono-energetic neutrons with energy E i and each polyethylene shell layer of the single-sphere neutron spectrometer and N+1 photoluminescence neutron detectors are simulated respectively by using the particle transport simulation program.

[0066] For example, the geometric model of the single-sphere spectrometer is established based on the MCNP program. According to the model requirements, the structure of the single-sphere spectrometer is determined, including the shell material (such as polyethylene), thickness, type and position of the internal detector, etc. Then, an input file is written, which contains model description, physical parameters and simulation requirements, etc. The geometric structure is defined in the input file, the cell is used to define the sphere, including the volume and the filling material, for example, a polyethylene sphere with a radius of 10 cm is defined, which is filled with a neutron detector inside. At the same time, the material properties are set, the material composition and density of each component are described in detail in the material definition part. The physical process is defined, the particle type (neutron), energy range and interaction process of the simulation are specified. The source term is set, the position, energy distribution and emission direction of the initial neutron source are defined according to the simulation requirements. Finally, the simulation is run and verified, the input file is compiled and run, the correctness and rationality of the model are verified by analyzing the output results, and the model is adjusted and optimized if necessary.

[0067] It should be noted that the existing response matrix is a response matrix based on the measurement of the neutron energy spectrum by the thermoluminescence detector. The present application establishes a new response matrix based on the measurement of the neutron energy spectrum by the photoluminescence detector.

[0068] The response matrix is determined by the following formula,

[0069] R j (E i )=C j (E i ) / Φ;

[0070] wherein, i = 1, 2, 3, 4………n, represents the energy of the total n incident neutrons; j = 1, 2, 3, 4………N+1; represents the total N+1 photoluminescence neutron detectors; C j (E i ) represents the number of times of the H(n, a) reaction between the jth photoluminescence neutron detector in the single sphere spectrometer and the incident neutrons with the incident neutron energy E i 6 3 H reaction; and Φ represents the fluence of the incident neutrons, and Φ = 1 / (L×M); L is the length of the planar monochromatic neutron source, and M is the width of the planar monochromatic neutron source.

[0071] S130, the multi-shell single sphere neutron energy spectrum measurement device is placed in a neutron radiation field, and the photoluminescence detector is directly opposite the neutron source; after the neutron source irradiates the multi-shell single sphere neutron energy spectrum measurement device for a set time, the photoluminescence detector is taken out, and the light intensity count of each photoluminescence detector is read out by using a photoluminescence reading system.

[0072] Specifically, the single sphere neutron energy spectrum measurement device of the present application is placed in a neutron radiation field, and the photoluminescence detector is directly opposite the neutron source, and the irradiation time is set to t minutes; after the irradiation time t ends, the N+1 photoluminescence detectors are taken out, and the light intensity count of each detector is read out by using a photoluminescence reading system. The light intensity count S (6，n+γ)，j of the N+1 photoluminescence neutron detectors under neutron irradiation is obtained, wherein j = 1, 2, 3, 4………N+1; represents the total N+1 photoluminescence neutron detectors.

[0073] S140, based on the response matrix and the light intensity count of each photoluminescence detector, the neutron energy spectrum of the neutron source is obtained by using a neutron energy spectrum deconvolution algorithm.

[0074] wherein, the light intensity count S (6，n+γ)，j of each photoluminescence detector, the response matrix R j (E i ), and the mathematical relationship between the neutron energy spectrum can be calculated by using the existing neutron energy spectrum calculation formula:

[0075] Specifically, the neutron energy spectrum is solved by using the above-mentioned neutron energy spectrum formula, and the neutron energy spectrum can be solved by using the existing deconvolution algorithm; for example, any one of the generalized least square algorithm, the maximum entropy algorithm, the Bayesian algorithm, the Monte Carlo algorithm, the genetic algorithm, and the neural network algorithm.

[0076] In the specific implementation process, the present embodiment can measure the neutron energy range from thermal neutrons (10 -8 ​​The neutron energy spectrum measurement device can meet the neutron energy spectrum measurement requirements in most scenarios at present.

[0077] Embodiment 4

[0078] A multi-shell single-sphere neutron energy spectrum measurement method is provided, which is used for neutron energy spectrum measurement by using the multi-shell single-sphere neutron energy spectrum measurement device in embodiment 2. Different from the photoluminescence detector in embodiments 1 and 3, which only includes photoluminescence neutron detectors, the photoluminescence detector in this embodiment includes photoluminescence neutron detectors and photoluminescence gamma detectors arranged side by side. The implementation of steps S110-S120 is the same as that in embodiment 3, and will not be described here.

[0079] S131, after obtaining the response matrix, before the neutron source irradiates the multi-shell single-sphere neutron energy spectrum measurement device, a light source with a preset wavelength is used to bleach all photoluminescence neutron detectors and photoluminescence gamma detectors in the multi-shell single-sphere neutron energy spectrum measurement device, so as to reduce the background signal of the photoluminescence detector. It should be noted that, in the specific implementation process, blue light is generally used for bleaching, and the bleaching time is related to the power of the blue light. The larger the power, the shorter the bleaching time. The power and time parameters are set according to the specific application scenario. For example, the blue light excitation wavelength is between 450 nm and 479 nm.

[0080] S132, taking any photoluminescence detector (including a group of photoluminescence neutron detectors and photoluminescence gamma detectors), a gamma source is used to irradiate the photoluminescence neutron detector and the photoluminescence gamma detector at the same time, so as to obtain the response count ratio of the photoluminescence neutron detector to the photoluminescence gamma detector to gamma irradiation.

[0081] The response count ratio A of the photoluminescence neutron detector to the photoluminescence gamma detector to gamma irradiation is obtained by the following formula,

[0082] A = S 6，γ / S 7，γ ;

[0083] Wherein, S 6，γ is the response count of the photoluminescence neutron detector after irradiation by the gamma source; S 7，γ is the response count of the photoluminescence gamma detector after irradiation by the gamma source.

[0084] S133, the multi-shell single-sphere neutron energy spectrum measurement device is placed in a neutron radiation field, and the photoluminescence neutron detector and the photoluminescence gamma detector are directly opposite the neutron source; after the neutron source irradiates the multi-shell single-sphere neutron energy spectrum measurement device for a set time, the photoluminescence neutron detector and the photoluminescence gamma detector are taken out, and the light intensity count of each photoluminescence neutron detector and each photoluminescence gamma detector is read out by a photoluminescence readout system, respectively.

[0085] S134. Based on the response count ratio of the optically stimulated light neutron detector and the optically stimulated light gamma detector to gamma irradiation, the light intensity count of each optically stimulated light neutron detector and the light intensity count of each optically stimulated light gamma detector, obtain the net light intensity count of each optically stimulated light neutron detector to neutron irradiation.

[0086] This can be achieved through the following formula.

[0087] S (6，n),j =S (6，n+γ)，j -(A×S (7，n+γ)，j );

[0088] Among them, S (6，n),j S is the net count of light intensity for each optically stimulated light neutron detector in response to neutron irradiation; A is the ratio of the response counts of the optically stimulated light neutron detector to the optically stimulated light gamma detector in response to gamma irradiation; S (6，n+γ)， j is the light intensity count for each optically stimulated luminescence neutron detector; S (7，n+γ)，j Count the light intensity for each optically stimulated luminescence (OSL) gamma detector.

[0089] S140. Based on the response matrix and the net count of light intensity of neutron irradiation by each optically stimulated luminescence neutron detector, the energy spectrum of the neutron source is obtained using a neutron energy spectrum descaling algorithm.

[0090] Figure 4 This is a response diagram of an optically stimulated light neutron detector at different distances from the center of a sphere under different energies of monoenergetic neutron irradiation conditions, according to an embodiment of the present invention. By observing... Figure 4 As can be seen, the measurable neutron energy range of this embodiment is from neutron (10) - 8 The range is from 100 MeV to 100 MeV. An optically stimulated luminescence (OSL) detector is positioned 14 cm from the center of the sphere, on the outer surface of the outermost moderated spherical shell. When the neutron energy is between 10⁻¹⁰ MeV... 2 At MeV, the responses of all curves (i.e., the intensity signals of optically stimulated luminescence) are very small, indicating that even for high-energy neutrons, after being moderated by a thicker moderation layer, the energy deposited in the luminescent detector is still very small as the thickness of the moderation shell increases. In other words, to measure very high-energy neutrons, a thicker shell is necessary, which inevitably leads to a very small response from the luminescent detector. In this case, if the goal is to increase the detector response and improve measurement accuracy, optically stimulated luminescence (OSL) is more advantageous than thermoluminescence (TEL). Or, to put it another way, for high-energy neutron measurements, OSL has a greater advantage in sensitivity.

[0091] In the implementation process, the present application integrates various functions on a hardware, and sets a man-machine interaction system, only manual input of parameters of the multi-shell single sphere neutron energy spectrum measuring device and the like is needed. The neutron energy spectrum calculation is automatically performed by the data processing module of the hardware. In the whole detection process, the detection system can not only display the test results on the man-machine interaction module, but also export the results to a file, and some test items can be analyzed and counted, that is, automatic comparison, automatic output of results and automatic statistical analysis are realized. Not only the problems of large amount of data of the multi-shell single sphere neutron energy spectrum measurement and long time consumption of the detection results in the prior art are solved, but also the professional requirements of the multi-shell single sphere neutron energy spectrum measurement on the operator are further weakened, and the accuracy and efficiency of the multi-shell single sphere neutron energy spectrum measurement are greatly improved.

[0092] As shown in Figure 5 The present application provides an electronic device 5 capable of realizing a multi-shell single sphere neutron energy spectrum measurement method.

[0093] The electronic device 5 can include a processor 50, a memory 51 and a bus, and can further include a computer program stored in the memory 51 and executable on the processor 50, such as a multi-shell single sphere neutron energy spectrum measurement program 52.

[0094] The memory 51 includes at least one type of readable storage medium, including a flash memory, a mobile hard disk, a multimedia card, a card type memory (such as an SD or DX memory, etc.), a magnetic memory, a disk, an optical disk, etc. The memory 51 can be an internal storage unit of the electronic device 3 in some embodiments, such as a mobile hard disk of the electronic device 5. The memory 31 can also be an external storage device of the electronic device 5 in other embodiments, such as a plug-in mobile hard disk, a smart media card (SMC), a secure digital (SD) card, a flash card, etc. equipped on the electronic device 3. Further, the memory 51 can include both the internal storage unit and the external storage device of the electronic device 5. The memory 51 can be used not only to store application software and various data installed on the electronic device 5, such as the code of the multi-shell single sphere neutron energy spectrum measurement program, but also to temporarily store data that has been output or will be output.

[0095] The processor 50 may, in some embodiments, be composed of integrated circuits, for example, can be composed of a single packaged integrated circuit, or can be composed of multiple packaged integrated circuits of the same function or different functions, including one or more combinations of central processing units (CPUs), microprocessors, digital processing chips, graphics processors, and various control chips. The processor 50 is the control core of the electronic device, which connects various components of the entire electronic device through various interfaces and lines, executes programs or modules stored in the memory 51 (such as multi-shell single-sphere neutron spectrum measurement programs, etc.), and calls data stored in the memory 51 to perform various functions and process data of the electronic device 5.

[0096] The bus can be a peripheral component interconnect (PCI) bus or an extended industry standard architecture (EISA) bus, etc. The bus can be divided into an address bus, a data bus, a control bus, etc. The bus is configured to realize the connection and communication between the memory 51 and the at least one processor 50, etc.

[0097] Figure 5 Only the electronic device with components is shown, and those skilled in the art can understand that, Figure 5 The structure shown does not constitute a limitation on the electronic device 5, and can include fewer or more components than shown, or combine certain components, or different component arrangements.

[0098] For example, although not shown, the electronic device 5 can also include a power supply (such as a battery) for powering various components. Preferably, the power supply can be logically connected to the at least one processor 50 through a power management device, so as to realize functions such as charge management, discharge management, and power consumption management through the power management device. The power supply can also include one or more direct current or alternating current power supplies, recharging devices, power supply fault detection circuits, power supply converters or inverters, power supply status indicators, and any other components. The electronic device 5 can also include various sensors, Bluetooth modules, Wi-Fi modules, etc., which are not described here.

[0099] Further, the electronic device 5 can also include a network interface, which can optionally include a wired interface and / or a wireless interface (such as a WI-FI interface, a Bluetooth interface, etc.), and is usually used to establish a communication connection between the electronic device 3 and other electronic devices.

[0100] Optionally, the electronic device 5 can also include a user interface, which can be a display, an input unit such as a keyboard, and optionally a standard wired interface, a wireless interface. Optionally, in some embodiments, the display can be an LED display, a liquid crystal display, a touch liquid crystal display, an OLED (Organic Light-Emitting Diode) touch, etc. Among them, the display can also be appropriately called a display screen or a display unit, which is used to display information processed in the electronic device 5 and to display a visualized user interface.

[0101] It should be understood that the above embodiments are only for illustration and do not limit the scope of the patent application.

[0102] The multi-shell single-sphere neutron spectrum measurement program 52 stored in the memory 51 in the electronic device 5 is a combination of a plurality of instructions, which, when executed in the processor 50, can achieve: establishing a planar mono-energetic neutron source; establishing a geometric model of a single-sphere neutron spectrum measurement instrument based on a particle transport simulation program; defining the single-sphere neutron spectrum measurement instrument according to the multi-shell single-sphere neutron spectrum measurement device; and using a particle transport simulation program to simulate the interaction physical processes of mono-energetic neutrons and each shell of the single-sphere neutron spectrum measurement instrument, as well as the interaction physical processes of each photoluminescence neutron detector in the photoluminescence detector, to obtain a response matrix; placing the multi-shell single-sphere neutron spectrum measurement device in a neutron radiation field, and placing the photoluminescence detector directly opposite the neutron source; after irradiating the multi-shell single-sphere neutron spectrum measurement device with the neutron source for a set time, removing the photoluminescence detector, and reading out the light intensity count of each photoluminescence detector with a photoluminescence readout system; based on the response matrix and the light intensity count of each photoluminescence detector, obtaining the neutron source spectrum using a neutron spectrum deconvolution algorithm.

[0103] Specifically, the specific implementation method of the processor 50 for the above instructions can refer to Figure 1 The description of the related steps in the corresponding embodiments will not be repeated here. It should be emphasized that, in order to further ensure the privacy and security of the above multi-shell single-sphere neutron spectrum measurement program, the above database can be stored in the node of the blockchain where the server cluster is located by processing data.

[0104] Further, the modules / units integrated in the electronic device 5, if implemented in the form of software functional units and sold or used as independent products, can be stored in a computer readable storage medium. The computer readable medium can include any entity or device capable of carrying the computer program codes, recording medium, U disk, mobile hard disk, magnetic disk, optical disk, computer memory, read-only memory (ROM).

[0105] The embodiment of the present application also provides a computer readable storage medium, which can be non-volatile or volatile, and stores a computer program. The computer program is executed by a processor to realize the following steps: establishing a planar single-energy neutron source; establishing a geometric model of a single-ball neutron spectrum measurement instrument based on a particle transport simulation program; defining the single-ball neutron spectrum measurement instrument according to the multi-shell single-ball neutron spectrum measurement device; simulating the interaction physical processes of single-energy neutrons and each shell layer of the single-ball neutron spectrum measurement instrument and the interaction physical processes of the photoluminescence neutron detector in each photoluminescence detector by using the particle transport simulation program, and then obtaining a response matrix; placing the multi-shell single-ball neutron spectrum measurement device in a neutron radiation field, and making the photoluminescence detector face the neutron source; taking out the photoluminescence detector after irradiating the multi-shell single-ball neutron spectrum measurement device by using the neutron source for a set time, and reading out the light intensity count of each photoluminescence detector by using a photoluminescence reading system; and obtaining the energy spectrum of the neutron source by using a neutron spectrum deconvolution algorithm based on the response matrix and the light intensity count of each photoluminescence detector. Specifically, the computer program is executed by the processor to realize the method, and the description of the related steps in the embodiment of the multi-shell single-ball neutron spectrum measurement method can be referred to, and details are not described herein.

[0106] In several embodiments provided in the present application, it should be understood that the disclosed devices, apparatuses and methods can be implemented by other manners. For example, the apparatus embodiment described above is only schematic, for example, the division of the modules is only a logical function division, and another division manner can be used in actual implementation.

[0107] The modules described as separate components can or can not be physically separated, and the components displayed as modules can or can not be physical units, that is, they can be located in one place, or can be distributed on multiple network units. According to actual needs, part or all of the modules can be selected to achieve the purpose of the embodiment scheme.

[0108] In addition, each function module in each embodiment of the present application can be integrated in one processing unit, or each unit can be physically present separately, or two or more units can be integrated in one unit. The integrated unit can be realized in the form of hardware or in the form of hardware plus software function modules.

[0109] It is obvious for those skilled in the art that the present application is not limited to the details of the above exemplary embodiments, and the present application can be realized in other specific forms without departing from the spirit or essential characteristics of the present application.

[0110] Therefore, from any point of view, the embodiments should be regarded as exemplary and non-limiting, and the scope of the present application is defined by the appended claims rather than the above description, and therefore all changes falling within the meaning and scope of the equivalent elements of the claims are intended to be included in the present application. Any additional reference signs in the claims should not be considered as limiting the claims involved.

[0111] The blockchain referred to in the present application is a new application mode of distributed data storage, peer-to-peer transmission, consensus mechanism, encryption algorithm and other computer technologies. Blockchain, in essence, is a decentralized database, which is a series of data blocks associated using cryptography. Each data block contains information about a batch of network transactions, which is used to verify the validity (anti-fake) of the information and generate the next block. The blockchain can include a blockchain underlying platform, a platform product service layer, and an application service layer.

[0112] In addition, it is obvious that the word "comprising" does not exclude other units or steps, and the singular does not exclude the plural. The plurality of units or devices stated in the device claim can also be realized by one unit or device through software or hardware. The second word is used to indicate the name, and does not indicate any specific order.

[0113] Finally, it should be pointed out that the above embodiments are only used to illustrate the technical solutions of the present application and are not limiting. Although the present application has been described in detail with reference to the preferred embodiments, it should be understood by those skilled in the art that the technical solutions of the present application can be modified or replaced equivalently without departing from the spirit and scope of the technical solutions of the present application.

Claims

1. A multi-shell single-sphere neutron energy spectrum measuring device, characterized in that, include: Slowing sphere, optically stimulated luminescence detector, and optically stimulated luminescence readout system; The moderating sphere is composed of N moderating spherical shells nested together at the same center in ascending order of diameter; each moderating spherical shell is a hollow sphere; each moderating spherical shell has the same thickness; N≥2; The optically stimulated luminescence detector is used to detect neutrons based on the principle of optically stimulated luminescence; along the same radial direction of the moderated sphere, optically stimulated luminescence detectors are set on the inner surface of each moderated spherical shell and on the outer surface of the outermost moderated spherical shell. The optically stimulated luminescence (OSL) readout system is used to receive the detection signal from the OSL detector and obtain the light intensity count of the OSL detector.

2. The multi-shell single-sphere neutron energy spectrum measuring device as described in claim 1, characterized in that, The slowing sphere is composed of N pairs of nested hemispherical shells; a pair of hemispherical shells with the same diameter form a slowing sphere.

3. The multi-shell single-sphere neutron energy spectrum measuring device as described in claim 1, characterized in that, The optically stimulated luminescence detector includes an optically stimulated luminescence neutron detector and an optically stimulated luminescence gamma detector arranged side by side; The optically stimulated light neutron detector is used to detect neutron rays and gamma rays; The optically stimulated luminescence gamma detector is used to detect gamma rays.

4. The multi-shell single-sphere neutron energy spectrum measuring device as described in claim 3, characterized in that, The optically stimulated light neutron detector includes a plastic sheet and an optically stimulated light neutron detector sheet; the optically stimulated light neutron detector sheet is sandwiched between the two plastic sheets to form a sandwich structure; the optically stimulated light neutron detector sheet is made of an optically stimulated light neutron detector material. The optically stimulated luminescence (OSL) gamma detector includes a plastic sheet and an OSL gamma detector sheet; the OSL gamma detector sheet is sandwiched between two plastic sheets to form a sandwich structure; the OSL gamma detector sheet is made of an OSL gamma detector material.

5. The multi-shell single-sphere neutron energy spectrum measuring device as described in claim 4, characterized in that, The optically stimulated luminescence (OSL) neutron detector material comprises an OSL material and a neutron conversion material; the mass ratio of the OSL material to the neutron conversion material is 2–3:2–3; the neutron conversion material is... 6 LiF or 6 Li2CO3. The optically stimulated luminescence (OSL) gamma-ray detector material comprises an OSL material and a lithium compound; the mass ratio of the OSL material to the lithium compound is 2-3:2-3; the lithium compound is... 7 LiF or 7 Li2CO3.

6. A method for measuring the neutron energy spectrum of a multi-shell single sphere, characterized in that, A method for performing neutron energy spectrum measurements using the multi-shell single-sphere neutron energy spectrum measuring device according to any one of claims 1-5, comprising: Establish a planar monoenergetic neutron source; A geometric model of a single-sphere neutron energy spectrum analyzer is established based on a particle transport simulation program. The single-sphere neutron energy spectrum analyzer is defined according to the multi-shell single-sphere neutron energy spectrum analyzer. The particle transport simulation program is used to simulate the physical processes of interaction between monoenergetic neutrons and the shells of each moderated sphere in the single-sphere neutron energy spectrum analyzer, as well as the optically stimulated light neutron detectors in each optically stimulated light detector, thereby obtaining the response matrix. The multi-shell single-sphere neutron energy spectrum measurement device is placed in the neutron radiation field, and the optically stimulated luminescence (OSL) detector is facing the neutron source. After the multi-shell single-sphere neutron energy spectrum measurement device is irradiated with the neutron source for a set time, the OSL detector is removed, and the light intensity count of each OSL detector is read out using the OSL readout system. Based on the response matrix and the light intensity count of each optically stimulated light detector, the energy spectrum of the neutron source is obtained using a neutron energy spectrum descaling algorithm.

7. The method for measuring the neutron energy spectrum of a multi-shell single sphere as described in claim 6, characterized in that, The response matrix is ​​determined by the following formula: R j (E i )(C j (E i ) / Φ1 Where i = 1, 2, 3, 4, ..., n, represents the energy of the n incident neutrons; j = 1, 2, 3, 4, ..., N+1, represents the energy of the N+1 optically stimulated neutron detectors; C j (E i () indicates that the energy of the incident neutron is E i At that time, the j-th optically stimulated neutron detector in the single-sphere spectrometer reacts with the incident neutron. 6 Li(n, a) 3 The number of H reactions; Φ represents the fluence of incident neutrons.

8. The method for measuring the neutron energy spectrum of a multi-shell single sphere as described in claim 6, characterized in that, When the optically stimulated light detector includes an optically stimulated light neutron detector and an optically stimulated light gamma detector arranged side by side... After obtaining the response matrix, before irradiating the multi-shell single-sphere neutron energy spectrum measurement device with a neutron source, all optically stimulated light neutron detectors and optically stimulated light gamma detectors in the multi-shell single-sphere neutron energy spectrum measurement device are exposed to sunlight using a light source of a preset wavelength to reduce the background signal of the optically stimulated light detectors. Take any optically stimulated light detector and simultaneously irradiate an optically stimulated light neutron detector and an optically stimulated light gamma detector using a gamma radiation source to obtain the response count ratio of the optically stimulated light neutron detector and the optically stimulated light gamma detector to gamma irradiation. The multi-shell single-sphere neutron energy spectrum measurement device is placed in the neutron radiation field, and the optically stimulated light neutron detector and the optically stimulated light gamma detector are facing the neutron source. After the multi-shell single-sphere neutron energy spectrum measurement device is irradiated by the neutron source for a set time, the optically stimulated light neutron detector and the optically stimulated light gamma detector are taken out, and the light intensity count of each optically stimulated light neutron detector and each optically stimulated light gamma detector is read out by the optically stimulated light readout system. Based on the response count ratio of the optically stimulated light neutron detector and the optically stimulated light gamma detector to gamma irradiation, the light intensity count of each optically stimulated light neutron detector and the light intensity count of each optically stimulated light gamma detector, the net light intensity count of each optically stimulated light neutron detector to neutron irradiation is obtained. Based on the response matrix and the net count of light intensity of neutron irradiation for each optically stimulated luminescence neutron detector, the energy spectrum of the neutron source is obtained using a neutron energy spectrum descaling algorithm.

9. The method for measuring the neutron energy spectrum of a multi-shell single sphere as described in claim 6, characterized in that, The response count ratio A of the optically stimulated light neutron detector and the optically stimulated light gamma detector to gamma irradiation is obtained by the following formula. A=S 6，γ / S 7，γ ; Among them, S 6，γ The response count of the optically stimulated light neutron detector after irradiation by a gamma radiation source; S 7，γ The response count of the optically stimulated luminescence gamma detector after irradiation by a gamma source; Based on the response count ratio of the optically stimulated light neutron detector and the optically stimulated light gamma detector to gamma irradiation, the light intensity count of each optically stimulated light neutron detector, and the light intensity count of each optically stimulated light gamma detector, the net light intensity count of each optically stimulated light neutron detector to neutron irradiation is obtained through the following formula. S (6，n),j =S (6，n+γ)，j -(A×S (7，n+γ)，j ); Among them, S (6，n),j S is the net count of light intensity for each optically stimulated light neutron detector in response to neutron irradiation; A is the ratio of the response counts of the optically stimulated light neutron detector to the optically stimulated light gamma detector in response to gamma irradiation; S (6，n+γ)，j Count the light intensity for each optically stimulated light neutron detector; S (7，n+γ)，j Count the light intensity for each optically stimulated luminescence (OSL) gamma detector.

10. An electronic device, characterized in that, The electronic device includes: At least one processor; and, A memory communicatively connected to the at least one processor; wherein, The memory stores instructions executable by the at least one processor, which, when executed by the at least one processor, enables the at least one processor to perform the steps in the multi-shell single-sphere neutron energy spectrum measurement method as described in any one of claims 6-9.

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