A neutron dose detection device and an all-energy-range neutron energy spectrum detection method

Abstract

The present invention relates to a neutron dose detection device and an all-energy-range neutron energy spectrum detection method, belonging to the technical field of neutron detection. It includes a first detection unit, a second detection unit, and a third detection unit. Each detection unit includes a neutron conversion layer and two detector units arranged in sequence from top to bottom. A neutron shielding layer is provided around the third detection unit, and the neutron shielding layer is used to block neutrons with energy less than the first energy. The neutron conversion layer is used to react with incident neutrons to generate secondary charged particles. The detector unit is used to detect the secondary charged particles and generate signals. Through the compact detection device, it occupies a small space, can be applied in miniaturized and low-power-consuming devices, and can effectively detect and distinguish incident neutrons with different energies.

Description

Technical Field

[0001] The present invention relates to the technical field of neutron detection, and particularly relates to a neutron dose detection device and an all-energy-range neutron energy spectrum detection method. Background Art

[0002] Since neutrons are electrically neutral, the detection of neutrons often requires indirect detection by means of secondary charged particles generated by the nuclear reaction of neutrons with certain atomic nuclei. However, the probability and mode of the nuclear reaction between neutrons and atomic nuclei are related to the neutron energy. Different detection means are required for neutrons in different energy ranges, resulting in a relatively complex neutron probe for all-energy-range neutron detection. In addition, the dose conversion coefficient required for calculating the neutron radiation dose is closely related to the neutron energy. Distinguishing the incident neutron energy is crucial for improving the accuracy of neutron dose. Therefore, how to simply and quickly detect all-energy-range neutrons and distinguish their incident energy has always been a research hotspot in neutron detection. Summary of the Invention

[0003] In view of the above problems existing in the existing neutron detection technology, the present invention provides a neutron dose detection device and an all-energy-range neutron energy spectrum detection method, which use a compact semiconductor detector and a corresponding conversion layer, occupy a small space, can be applied to miniaturized and low-power-consuming devices, and based on the detection structure of the semiconductor detector and the method of distinguishing the incident neutron energy, can effectively detect and distinguish incident neutrons with different energies.

[0004] To achieve the above object, the present invention provides a neutron dose detection device, comprising:

[0005] Three detection units, including a first detection unit, a second detection unit, and a third detection unit. Each detection unit includes a neutron conversion layer and two detector units arranged in sequence from top to bottom;

[0006] Wherein, a neutron shielding layer is provided around the third detection unit, and the neutron shielding layer is used to block neutrons with energy less than the first energy;

[0007] The neutron conversion layer is used to react with incident neutrons to generate secondary charged particles;

[0008] The detector unit is used to detect the secondary charged particles and generate signals.

[0009] Preferably, the first detection unit includes a first neutron conversion layer, a first detector unit, and a second detector unit arranged in sequence from top to bottom;

[0010] The second detection unit includes a second neutron conversion layer, a third detector unit, and a fourth detector unit arranged in sequence from top to bottom;

[0011] The third detection unit includes a third neutron conversion layer, a fifth detector unit, and a sixth detector unit arranged in sequence from top to bottom.

[0012] Preferably, the first detector unit, the third detector unit, and the fifth detector unit each include a semiconductor detector;

[0013] The second detector unit, the fourth detector unit, and the sixth detector unit each include at least one semiconductor detector.

[0014] Preferably, the first detector unit, the third detector unit, and the fifth detector unit have the same area and thickness.

[0015] Preferably, the second detector unit, the fourth detector unit, and the sixth detector unit have the same area and thickness.

[0016] Preferably, the first neutron conversion layer is made of a material containing LiF;

[0017] The second neutron conversion layer and the third neutron conversion layer are made of a material containing LiH or LiOH, and the second neutron conversion layer and the third neutron conversion layer have the same material, area, and thickness.

[0018] Preferably, by selecting the thickness of the first detector unit, the first detector unit blocks secondary charged particles generated by nuclear reactions between neutrons with energy less than the first energy and the first neutron conversion layer.

[0019] To achieve the above object, the present invention also provides an all-energy-range neutron energy spectrum detection method, which uses the above neutron dose detection device and includes the following steps:

[0020] S1. Place the neutron dose detection device in a radiation environment of neutrons with various energies, and obtain the deposited energy through the first detection unit, the second detection unit, and the third detection unit;

[0021] S2. Incident neutrons react with the neutron conversion layer in the detection unit to generate secondary charged particles, and the detector unit detects the secondary charged particles and generates signals;

[0022] S3. Obtain the number of neutrons in multiple energy ranges based on the signals generated by different detector units.

[0023] Preferably, step S3 further includes:

[0024] S31. Obtain the number of neutrons with energy less than the first energy based on the number of signals generated by the fifth detector unit in the third detection unit and the number of signals generated by the third detector unit in the second detection unit;

[0025] S32. Obtain the number of neutrons with energy greater than the first energy and less than the second energy according to the number of events in which the fifth detector unit in the third detector unit generates a signal while the sixth detector unit in the third detector unit does not generate a signal;

[0026] S33. Obtain the number of neutrons with energy greater than the third energy according to the number of signals generated by the fourth detector unit in the second detector unit and the number of signals generated by the second detector unit in the first detector unit; wherein, the third energy is greater than the second energy;

[0027] S34. Obtain the number of neutrons with energy less than the second energy according to the number of events in which the third detector unit in the second detector unit generates a signal while the fourth detector unit in the second detector unit does not generate a signal;

[0028] S35. Obtain the number of neutrons with energy greater than the second energy and less than the third energy according to the number of signals generated by the third detector unit in the second detector unit, the number of neutrons with energy greater than the third energy, and the number of neutrons with energy less than the second energy.

[0029] Preferably, the all-round neutron energy spectrum detection method includes:

[0030] S4. Generate a first deposited energy distribution map according to the signals generated by the third detector unit and the fourth detector unit in the second detector unit, generate a second deposited energy distribution map according to the signals generated by the fifth detector unit and the sixth detector unit in the third detector unit, and extract the recoil proton energy spectrum generated by the nuclear reaction of incident neutrons with the neutron conversion layer containing LiH material or LiOH material through the ΔE-E energy measurement method.

[0031] Compared with the prior art, the advantages and positive effects of the present invention are as follows:

[0032] (1) The present invention uses a semiconductor detector with a compact structure, which occupies a small space and can be applied to miniaturized and low-power devices.

[0033] (2) Based on the neutron dose detection device and the neutron energy spectrum detection method, the present invention can effectively detect and distinguish incident neutrons with different energies. Description of the Drawings

[0034] In order to more clearly illustrate the technical solutions in the embodiments of the present application or the prior art, the following will describe the specific embodiments of the present invention in detail with reference to the drawings. For those of ordinary skill in the art, other drawings can also be obtained based on these drawings without creative efforts.

[0035] Figure 1 It is a schematic structural diagram of the neutron dose detection device provided by the embodiment of the present invention;

[0036] Figure 2 Schematic diagram of the structure of the first detection unit provided by an embodiment of the present invention;

[0037] Figure 3 Schematic diagram of the structure of the second detection unit provided by an embodiment of the present invention;

[0038] Figure 4 Schematic diagram of the structure of the third detection unit provided by an embodiment of the present invention;

[0039] Figure 5 Schematic diagram of the simulation of the penetration rate of neutrons with different energies after passing through 1 mm thick gadolinium metal (Gd) according to an embodiment of the present invention;

[0040] Figure 6 For neutrons with different energies provided by an embodiment of the present invention passing through 6 Li(n,T) 4 Schematic diagram of the maximum energy of tritium emitted from the conversion layer through the He reaction;

[0041] Figure 7 For neutrons with different energies provided by an embodiment of the present invention passing through 1 Schematic diagram of the maximum energy of protons emitted from the conversion layer through the H(n,EL) reaction;

[0042] Figure 8 For the neutrons corresponding to tritium that can be completely deposited in silicon detectors with different thicknesses provided by an embodiment of the present invention 6 Li(n,T) 4 He, and the dashed line is the schematic diagram of the neutron energy corresponding to protons that can be completely deposited in silicon detectors with different thicknesses 1 H(n,EL);

[0043] Figure 9 Schematic diagram of the coincidence relationship of the deposited energy in the third detector unit and the fourth detector unit when simulating neutrons with a uniformly distributed incident energy between 0.3 MeV and 4 MeV according to an embodiment of the present invention.

[0044] In the figure, 1. The first detection unit; 2. The second detection unit; 3. The third detection unit; 4. The first detector unit; 5. The second detector unit; 6. The third detector unit; 7. The fourth detector unit; 8. The fifth detector unit; 9. The sixth detector unit; 10. The first neutron conversion layer; 11. The second neutron conversion layer; 12. The third neutron conversion layer; 13. The neutron shielding layer. Detailed implementation manners

[0045] Next, the present invention will be specifically described through exemplary embodiments. However, it should be understood that, without further elaboration, the elements, structures, and features in one embodiment can also be beneficially incorporated into other embodiments.

[0046] In the description of the present invention, it should be noted that the orientation or positional relationships indicated by the terms "upper", "lower", "left", "right", "inner", "outer", etc. are based on the positional relationships shown in the drawings. These are only for the convenience of describing the present invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus should not be construed as a limitation of the present invention. In addition, the terms "first", "second", "third", "fourth", "fifth", "sixth", "seventh" are only used for descriptive purposes and cannot be construed as indicating or implying relative importance.

[0047] See Figure 1 , an embodiment of the present invention provides a neutron dose detection device, including:

[0048] Three detection units, including a first detection unit 1, a second detection unit 2, and a third detection unit 3. Each detection unit includes a neutron conversion layer and two detector units arranged in sequence from top to bottom;

[0049] Among them, a neutron shielding layer 13 is provided around the third detection unit 3. The neutron shielding layer 13 is used to block neutrons with energy less than the first energy;

[0050] The neutron conversion layer is used to react with incident neutrons to generate secondary charged particles;

[0051] The detector unit is used to detect secondary charged particles and generate signals.

[0052] It should be noted that the arrangement order of the first detection unit 1, the second detection unit 2, and the third detection unit 3 is not limited to vertical arrangement. It can be parallel arrangement or any other form of arrangement, specifically determined according to actual needs.

[0053] Specifically, in a specific embodiment, see Figure 2 , the first detection unit 1 includes a first neutron conversion layer 10, a first detector unit 4, and a second detector unit 5 arranged in sequence from top to bottom.

[0054] Specifically, in a specific embodiment, see Figure 3 , the second detection unit 2 includes a second neutron conversion layer 11, a third detector unit 6, and a fourth detector unit 7 arranged in sequence from top to bottom.

[0055] Specifically, in a specific embodiment, see Figure 4, the third detection unit 3 includes a third neutron conversion layer 12, a fifth detector unit 8, and a sixth detector unit 9 arranged in sequence from top to bottom.

[0056] Specifically, continue to refer to Figures 2 - 4 , in a specific embodiment, the first detector unit 4, the third detector unit 6, and the fifth detector unit 8 include a semiconductor detector.

[0057] Specifically, continue to refer to Figures 2 - 4 , in a specific embodiment, the second detector unit 5, the fourth detector unit 7, and the sixth detector unit 9 include at least one semiconductor detector.

[0058] It should be noted that in each detection unit, each semiconductor detector in each detector unit works independently and can record the deposited energy separately. In the second detector unit 5, the fourth detector unit 7, and the sixth detector unit 9, the number of semiconductor detectors is not limited to one, and can be two, three, or more, depending on actual needs.

[0059] Specifically, continue to refer to Figures 2 - 4 , in a specific embodiment, the areas and thicknesses of the first detector unit 4, the third detector unit 6, and the fifth detector unit 8 are the same. It should be noted that according to the size of the detection structure space, the processing level of the semiconductor detector, and the energy range of the neutrons to be detected, the areas and thicknesses of the first detector unit 4, the third detector unit 6, and the fifth detector unit 8 can be appropriately selected, that is, the areas and thicknesses of the first detector unit 4, the third detector unit 6, and the fifth detector unit 8 can be selected according to actual needs.

[0060] Specifically, continue to refer to Figures 2 - 4 , in a specific embodiment, the areas and thicknesses of the second detector unit 5, the fourth detector unit 7, and the sixth detector unit 9 are the same. It should be noted that according to the size of the detection structure space, the processing level of the semiconductor detector, and the energy range of the neutrons to be detected, the areas and thicknesses of the second detector unit 5, the fourth detector unit 7, and the sixth detector unit 9 can be appropriately selected, that is, the areas and thicknesses of the second detector unit 5, the fourth detector unit 7, and the sixth detector unit 9 can be selected according to actual needs.

[0061] Specifically, continue to refer to Figures 2 - 4, in a specific embodiment, the first neutron conversion layer 10 is made of a material containing LiF; the second neutron conversion layer 11 and the third neutron conversion layer 12 are made of a material containing LiH or a material containing LiOH; the materials, areas, and thicknesses of the second neutron conversion layer 11 and the third neutron conversion layer 12 are the same. It should be noted that, according to the energy of the neutrons to be detected and the requirements of detection efficiency, the areas and thicknesses of the second neutron conversion layer 11 and the third neutron conversion layer 12 can be appropriately selected, that is, the areas and thicknesses of the second neutron conversion layer 11 and the third neutron conversion layer 12 can be selected according to actual needs.

[0062] Specifically, continue to refer to Figure 4 , the material of the neutron shielding layer 13 can be a material such as metallic cadmium or metallic gadolinium that can block neutrons with energy less than the first energy.

[0063] Specifically, continue to refer to Figure 2 , by selecting the thickness of the first detector unit 4, the first detector unit 4 blocks the secondary charged particles generated by the nuclear reaction of neutrons with energy less than the first energy with the first neutron conversion layer 10.

[0064] The above neutron dose detection device of the present invention, through its special structural design, uses a semiconductor detector with a compact structure, occupies a small space, can be applied in miniaturized and low-power devices, and can more accurately detect the energy of incident neutrons.

[0065] The embodiment of the present invention also provides an all-energy-range neutron energy spectrum detection method, which uses the above neutron dose detection device, refer to Figures 1 - 4 , and includes the following steps:

[0066] S1. Place the neutron dose detection device in a radiation environment of neutrons with various energies, and obtain the deposited energy through the first detection unit 1, the second detection unit 2, and the third detection unit 3;

[0067] S2. The incident neutrons react with the neutron conversion layer in the detection unit to generate secondary charged particles, and the detector unit detects the secondary charged particles and generates signals;

[0068] S3. Obtain the number of neutrons in multiple energy segments according to the signals generated by different detector units;

[0069] S4. Generate a first deposition energy distribution map based on the signals generated by the third detector unit 6 and the fourth detector unit 7 in the second detection unit 2, and generate a second deposition energy distribution map based on the signals generated by the fifth detector unit 8 and the sixth detector unit 9 in the third detection unit 3. Extract the recoil proton energy spectrum generated by the nuclear reaction of incident neutrons with the LiH material or the neutron conversion layer containing LiOH through the ΔE-E energy measurement method. Specifically, extract the recoil proton energy spectrum generated by the nuclear reaction of incident neutrons with 1 H in LiH or LiOH to provide data for inverting the incident neutron energy spectrum.

[0070] Specifically, continue to refer to Figures 1 - 4 , and the above step S3 further includes:

[0071] S31. Obtain the number of neutrons with energy less than the first energy according to the number of signals generated by the fifth detector unit 8 in the third detection unit 3 and the number of signals generated by the third detector unit 6 in the second detection unit 2. Specifically, the number of neutrons with energy less than the first energy is obtained by subtracting the number of signals generated by the third detector unit 6 from the number of signals generated by the fifth detector unit 8.

[0072] S32. Obtain the number of neutrons with energy greater than the first energy and less than the second energy according to the number of events where the sixth detector unit 9 in the third detection unit 3 does not generate a signal while the fifth detector unit 8 in the third detection unit 3 generates a signal.

[0073] S33. Obtain the number of neutrons with energy greater than the third energy according to the number of signals generated by the fourth detector unit 7 in the second detection unit 2 and the number of signals generated by the second detector unit 5 in the first detection unit 1; where the third energy is greater than the second energy. Specifically, the number of neutrons with energy greater than the third energy is obtained by subtracting the number of signals generated by the second detector unit 5 from the number of signals generated by the fourth detector unit 7.

[0074] S34. Obtain the number of neutrons with energy less than the second energy according to the number of events where the fourth detector unit 7 in the second detection unit 2 does not generate a signal while the third detector unit 6 in the second detection unit 2 generates a signal.

[0075] S35. Obtain the number of neutrons with energy greater than the second energy and less than the third energy according to the number of signals generated by the third detector unit 6 in the second detection unit 2, the number of neutrons with energy greater than the third energy, and the number of neutrons with energy less than the second energy. Specifically, the number of neutrons with energy greater than the second energy and less than the third energy is obtained by subtracting the number of neutrons with energy greater than the third energy and the number of neutrons with energy less than the second energy from the number of signals generated by the third detector unit 6.

[0076] The above-mentioned all-energy-range neutron energy spectrum detection method of the present invention can effectively detect and distinguish incident neutrons of different energies.

[0077] Since it is difficult to obtain neutrons with a specific energy distribution in actual experiments, neutrons with a specific energy distribution are simulated by Geant4 simulation software below, and then the above-mentioned neutron dose detection device and all-energy-range neutron energy spectrum detection method of the present invention are used to detect neutrons to verify their effectiveness.

[0078] In this embodiment, the first detector unit 4, the third detector unit 6, and the fifth detector unit 8 all use silicon detectors with a thickness of 65 μm and a side length of 20 mm. The second detector unit 5, the fourth detector unit 7, and the sixth detector unit 9 all use a single silicon detector with a thickness of 65 μm and a side length of 20 mm. The first neutron conversion layer 10 uses LiF rich in 6 Li with a thickness of 28 μm and a side length of 20 mm. 6 The Li abundance is 95%. The second neutron conversion layer 11 and the third neutron conversion layer 12 both use LiH rich in 6 Li with a thickness of 100 μm and a side length of 20 mm. 6 The Li abundance is 95%. The neutron shielding layer 13 uses 1 mm thick metallic gadolinium, and the energy of neutrons with the first energy is set to 0.4 eV, the energy of neutrons with the second energy is set to E1, and the energy of neutrons with the third energy is set to E2.

[0079] See Figure 5 , for incident neutrons of different energies, calculate the penetration rate after passing through 1 mm thick metallic gadolinium Gd. According to Figure 5 it can be seen that metallic gadolinium can block neutrons with an energy less than 0.4 eV.

[0080] The third detector unit 6 can detect the secondary particle signals generated by the nuclear reaction of all-energy neutrons and the second neutron conversion layer 11, while the fifth detector unit 8 can only detect the secondary particle signals generated by the nuclear reaction of neutrons with an energy higher than 0.4 eV and the third neutron conversion layer 12. The number of neutrons N1 with an energy less than 0.4 eV can be obtained by subtracting the number of signals generated by the third detector unit 6 from the number of signals generated by the fifth detector unit 8.

[0081] See Figure 6 , Figure 6 is the maximum energy of tritium emitted from the neutron conversion layer due to the 6 Li(n,T) 4 He reaction for neutrons of different energies, as shown in Figure 6The horizontal dotted line in [Figure] indicates that the maximum energy of tritium that can be deposited in 65-μm silicon is 2.9 MeV. Tritium generated by neutrons with energy exceeding 0.3 MeV can penetrate 65-μm silicon. Then, the number of neutrons N2 with energy between 0.4 eV and E1 (E1 = 0.3 MeV) can be obtained from the number of events where no signal is generated in the sixth detector unit 9 but a signal is generated in the fifth detector unit 8.

[0082] See Figure 7 , Figure 7 is the maximum energy of protons emitted from the conversion layer through the 1 H(n,EL) reaction for neutrons with different energies. As shown in Figure 7 , the horizontal dotted line indicates that the maximum energy of protons that can be deposited in 65-μm silicon is 1.9 MeV. Protons generated by neutrons with energy exceeding 1.9 MeV can penetrate 65-μm silicon. In the second detector unit 2, the second neutron conversion layer 11 contains 1 H. Neutrons with energy exceeding 1.9 MeV can generate recoil protons through the second neutron conversion layer 11 and reach the third detector unit 6. The first neutron conversion layer 10 does not contain 1 H. Neutrons with energy exceeding 1.9 MeV will not generate recoil protons through the first neutron conversion layer 10 and reach the second detector unit 5. Then, the number of neutrons N3 with energy greater than E2 (E2 = 1.9 MeV) can be obtained by subtracting the number of signals generated in the second detector unit 5 from the number of signals generated in the fourth detector unit 7.

[0083] Continue to see Figure 6 . Tritium generated by neutrons with energy exceeding 0.3 MeV can penetrate 65-μm silicon. Then, the number of neutrons N4 with energy less than E1 can be obtained from the number of events where no signal is generated in the fourth detector unit 7 but a signal is generated in the third detector unit 6.

[0084] The third detector unit 6 can detect secondary particle signals generated by the reaction of neutrons with all energies and the second neutron conversion layer 11. Then, the number of neutrons with energy between E1 and E2 can be obtained by subtracting (N3 + N4) from the number of signals generated in the third detector unit 6. Thus, the number of incident neutrons in the four energy ranges of less than 0.4 eV, 0.4 eV - E1, E1 - E2, and greater than E2 can be obtained.

[0085] See Figure 8 . The magnitudes of neutron energy E1 and neutron energy E2 are adjusted by the thicknesses of the first detector unit 4, the third detector unit 6, and the fifth detector unit 8. E1 is the neutron energy corresponding to 6 Li(n,T) 4 He that can be completely deposited in silicon with different thicknesses. E2 is the neutron energy corresponding to protons that can be completely deposited in silicon with different thicknesses1 The neutron energy of H(n,EL), for silicon of a certain thickness, neutrons with energy E1 pass through 6 Li(n,T) 4 The tritium produced by the He reaction can just penetrate, while neutrons with energy E2 pass through 1 The protons produced by the H(n,EL) reaction can just penetrate.

[0086] See Figure 9 , neutrons with incident energy uniformly distributed between 0.3 MeV and 4 MeV are vertically incident on the second detection unit 2 in front of the second neutron conversion layer 11. Figure 9 For the coincidence relationship of the deposited energies in the third detector unit 6 and the fourth detector unit 7, it can be clearly seen that according to the tritium and proton signals generated by the reaction of neutrons and the second neutron conversion layer 11 and their respective strip shapes, the recoil proton deposited energy spectrum is extracted, providing data for inverting the incident neutron energy spectrum.

[0087] The above embodiments are used to explain the present invention, rather than limiting the present invention. Within the spirit and scope of the claims of the present invention, any modifications and changes made to the present invention fall within the protection scope of the present invention.

Claims

1. A neutron dose detection device, characterized in that, Comprising: Three detection units, including a first detection unit, a second detection unit, and a third detection unit. Each detection unit includes a neutron conversion layer and two detector units arranged successively from top to bottom. Wherein, a neutron shielding layer is provided around the third detection unit, and the neutron shielding layer is used to block neutrons with energy less than a first energy. The neutron conversion layer is used to react with incident neutrons to generate secondary charged particles. The detector unit is used to detect the secondary charged particles and generate signals. Wherein, the first detection unit includes a first neutron conversion layer, a first detector unit, and a second detector unit arranged successively from top to bottom. The second detection unit includes a second neutron conversion layer, a third detector unit, and a fourth detector unit arranged successively from top to bottom. The third detection unit includes a third neutron conversion layer, a fifth detector unit, and a sixth detector unit arranged successively from top to bottom. Wherein, the first neutron conversion layer is made of a material containing LiF. The second neutron conversion layer and the third neutron conversion layer are made of a material containing LiH or a material containing LiOH, and the materials, areas, and thicknesses of the second neutron conversion layer and the third neutron conversion layer are the same.

2. The neutron dose detection device according to claim 1, wherein The first detector unit, the third detector unit, and the fifth detector unit each include a semiconductor detector. The second detector unit, the fourth detector unit, and the sixth detector unit each include at least one semiconductor detector.

3. The neutron dose detection device according to claim 1, characterized in that, The areas and thicknesses of the first detector unit, the third detector unit, and the fifth detector unit are the same.

4. The neutron dose detection device according to claim 1, characterized in that, The areas and thicknesses of the second detector unit, the fourth detector unit, and the sixth detector unit are the same.

5. The neutron dose detection device according to claim 2, characterized in that, By selecting the thickness of the first detector unit, the first detector unit blocks the secondary charged particles generated by the nuclear reaction of neutrons with energy less than the first energy with the first neutron conversion layer.

6. A method for detecting neutron energy spectrum in all energy ranges, using the neutron dose detection device according to any one of claims 1 to 5, characterized in that, Containing the following steps: S1. Place the neutron dose detection device in a radiation environment of neutrons with various energies, and obtain the deposited energy through the first detection unit, the second detection unit, and the third detection unit. S2. Incident neutrons react with the neutron conversion layer in the detection unit to generate secondary charged particles, and the detector unit detects the secondary charged particles and generates signals. S3. Obtain the number of neutrons in multiple energy segments according to the signals generated by different detector units.

7. The all-energy-section neutron energy spectrum detection method according to claim 6, characterized in that The step S3 further includes: S31. Obtain the number of neutrons with energy less than the first energy according to the number of signals generated by the fifth detector unit in the third detection unit and the number of signals generated by the third detector unit in the second detection unit. S32. Obtain the number of neutrons with energy greater than the first energy and less than the second energy according to the number of events where no signal is generated by the sixth detector unit in the third detection unit but a signal is generated by the fifth detector unit in the third detection unit. S33. Obtain the number of neutrons with energy greater than the third energy based on the number of signals generated by the fourth detector unit in the second detection unit and the number of signals generated by the second detector unit in the first detection unit; wherein, the third energy is greater than the second energy. S34. Obtain the number of neutrons with energy less than the second energy based on the number of events where the fourth detector unit in the second detection unit does not generate a signal while the third detector unit in the second detection unit generates a signal. S35. Obtain the number of neutrons with energy greater than the second energy and less than the third energy based on the number of signals generated by the third detector unit in the second detection unit, the number of neutrons with energy greater than the third energy, and the number of neutrons with energy less than the second energy.

8. The all-round neutron energy spectrum detection method according to claim 6, characterized in that The method further includes: S4. Generate a first deposited energy distribution map based on the signals generated by the third detector unit and the fourth detector unit in the second detection unit, generate a second deposited energy distribution map based on the signals generated by the fifth detector unit and the sixth detector unit in the third detection unit, and extract the energy spectrum of recoil protons generated by the nuclear reaction of incident neutrons with the neutron conversion layer containing LiH material or LiOH material through the ΔE-E energy measurement method.

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