Neutron dose detection device and full-energy-range neutron energy spectrum detection method

Abstract

The invention relates to a neutron dose detection device and a full-energy-range neutron spectrum detection method, and belongs to the technical field of neutron detection.The neutron dose detection device comprises a first detection unit, a second detection unit and a third detection unit, and each detection unit comprises a neutron conversion layer and two detector units which are sequentially arranged from top to bottom; a neutron shielding layer is arranged on the periphery of the third detection unit and is used for blocking neutrons of which the energy is smaller than the first energy; the neutron conversion layer is used for reacting with incident neutrons to generate secondary charged particles; the detector unit is used for detecting the secondary charged particles and generating signals. The detection device with a compact structure occupies a small space, can be applied to miniaturized low-power-consumption equipment, 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 in particular to a neutron dose detection device and a full-energy range neutron energy spectrum detection method. Background Art

[0002] Since neutrons are not charged, their detection often requires indirect detection with the help of secondary charged particles produced by nuclear reactions between neutrons and certain atomic nuclei; however, the probability and mode of nuclear reactions between neutrons and atomic nuclei are related to the neutron energy, and different detection methods are required for neutrons in different energy ranges, resulting in the neutron probes required for full-energy neutron detection being often more complex. In addition, the dose conversion coefficient required to calculate the neutron radiation dose is closely related to the neutron energy, and distinguishing the incident neutron energy is crucial to improving the accuracy of the neutron dose. Therefore, how to simply and quickly detect neutrons in the full energy range and distinguish their incident energy has always been a hot topic in neutron detection research. Summary of the invention

[0003] In view of the above-mentioned problems existing in the existing neutron detection technology, the present invention provides a neutron dose detection device and a full-energy range neutron energy spectrum detection method. The device uses a compact semiconductor detector and a corresponding conversion layer, occupies a small space, and can be applied to miniaturized and low-power consumption equipment. In addition, the detection structure based on the semiconductor detector and the method for distinguishing the energy of incident neutrons can effectively detect and distinguish incident neutrons of different energies.

[0004] In order to achieve the above object, the present invention provides a neutron dose detection device, comprising: Three detection units, including a first detection unit, a second detection unit, and a third detection unit, each detection unit including a neutron conversion layer and two detector units arranged in sequence from top to bottom; Wherein, a neutron shielding layer is provided around the outer periphery of 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 produce secondary charged particles; The detector unit is used to detect the secondary charged particles and generate signals.

[0005] Preferably, the first detection unit comprises a first neutron conversion layer, a first detector unit, and a second detector unit which are arranged in sequence from top to bottom; 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; The third detection unit includes a third neutron conversion layer, a fifth detector unit, and a sixth detector unit which are arranged in sequence from top to bottom.

[0006] Preferably, the first detector unit, the third detector unit and the fifth detector unit include a semiconductor detector; The second detector unit, the fourth detector unit and the sixth detector unit include at least one semiconductor detector.

[0007] Preferably, the first detector unit, the third detector unit and the fifth detector unit have the same area and thickness.

[0008] Preferably, the second detector unit, the fourth detector unit and the sixth detector unit have the same area and thickness.

[0009] Preferably, 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 LiH-containing or LiOH-containing materials, and the second neutron conversion layer and the third neutron conversion layer have the same material, area and thickness.

[0010] Preferably, by selecting the thickness of the first detector unit, the first detector unit blocks secondary charged particles generated by nuclear reactions between neutrons having energy less than the first energy and the first neutron conversion layer.

[0011] In order to achieve the above object, the present invention also provides a full-energy range neutron spectrum detection method, using the above neutron dose detection device, comprising the following steps: S1. placing the neutron dose detection device in a radiation environment of neutrons with various energies, and obtaining deposition energy through the first detection unit, the second detection unit, and the third detection unit; 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; S3. Obtain the number of neutrons in multiple energy ranges according to the signals generated by different detector units.

[0012] Preferably, step S3 further comprises: S31, obtaining the number of neutrons having an 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, obtaining the number of neutrons having an energy greater than the first energy and less than the second energy according to the number of events in which the sixth detector unit in the third detection unit does not generate a signal but the fifth detector unit in the third detection unit generates a signal; S33, obtaining the number of neutrons having an energy greater than a third energy according to 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, obtaining the number of neutrons having an energy less than the second energy according to the number of events in which the fourth detector unit in the second detection unit does not generate a signal but the third detector unit in the second detection unit generates a signal; S35. According to 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, the number of neutrons with energy greater than the second energy and energy less than the third energy is obtained.

[0013] Preferably, the full-energy range neutron spectrum detection method comprises: S4. Generate a first deposition energy distribution diagram according to the signal generated by the third detector unit and the signal generated by the fourth detector unit in the second detection unit, generate a second deposition energy distribution diagram according to the signal generated by the fifth detector unit and the signal generated by the sixth detector unit in the third detection unit, and extract a recoil proton energy spectrum generated by a nuclear reaction between an incident neutron and a neutron conversion layer containing a LiH material or a LiOH material by a ΔE-E energy measurement method.

[0014] Compared with the prior art, the advantages and positive effects of the present invention are: (1) The present invention uses a compact semiconductor detector that occupies a small space and can be applied to miniaturized and low-power devices.

[0015] (2) The present invention is based on a neutron dose detection device and a neutron energy spectrum detection method, which can effectively detect and distinguish incident neutrons of different energies. BRIEF DESCRIPTION OF THE DRAWINGS

[0016] In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the specific embodiments of the present invention will be described in detail below in conjunction with the accompanying drawings. For ordinary technicians in this field, other drawings can be obtained based on these drawings without paying any creative work. Figure 1 A schematic diagram of the structure of a neutron dose detection device provided in an embodiment of the present invention; Figure 2 A schematic diagram of the structure of a first detection unit provided in an embodiment of the present invention; Figure 3 A schematic diagram of the structure of a second detection unit provided in an embodiment of the present invention; Figure 4 A schematic diagram of the structure of a third detection unit provided in an embodiment of the present invention; Figure 5A schematic diagram of simulation of the penetration rate of neutrons with different energies after passing through 1 mm thick metal gadolinium Gd provided by an embodiment of the present invention; Figure 6 Neutrons of different energies provided by the embodiment of the present invention pass through 6 Li(n,T) 4 Schematic diagram of the maximum energy of tritium produced by He reaction emitted from the conversion layer; Figure 7 Neutrons of different energies provided by the embodiment of the present invention pass through 1 Schematic diagram of the maximum energy of protons produced by the H(n,EL) reaction and emitted from the conversion layer; Figure 8 The tritium corresponding to the silicon detector with different thicknesses provided by the embodiment of the present invention can be completely deposited in the silicon detector with different thicknesses. 6 Li(n,T) 4 The neutron energy of He. The dashed line is the energy of protons that can be completely deposited in silicon detectors of different thicknesses. 1 Schematic diagram of neutron energy of H(n,EL); Fig. 9 A schematic diagram of the coincidence relationship between the deposited energies in the third detector unit and the fourth detector unit when simulating neutrons with incident energies uniformly distributed between 0.3 MeV and 4 MeV provided in an embodiment of the present invention.

[0017] 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 DESCRIPTION

[0018] The present invention is described in detail below by way of exemplary embodiments. However, it should be understood that elements, structures, and features in one embodiment may also be beneficially combined in other embodiments without further description.

[0019] In the description of the present invention, it should be noted that the directions or positional relationships indicated by the terms "upper", "lower", "left", "right", "inner", "outer", etc. are based on the positional relationships shown in the drawings, and are only for the convenience of describing the present invention and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific direction, be constructed and operated in a specific direction, and therefore cannot be understood as limiting the present invention. In addition, the terms "first", "second", "third", "fourth", "fifth", "sixth", and "seventh" are used for descriptive purposes only, and cannot be understood as indicating or implying relative importance. See also Figure 1 , an embodiment of the present invention provides a neutron dose detection device, comprising: Three detection units, including a first detection unit 1, a second detection unit 2, and a third detection unit 3, each detection unit including a neutron conversion layer and two detector units arranged in sequence from top to bottom; A neutron shielding layer 13 is disposed around the outer periphery of the third detection unit 3, and the neutron shielding layer 13 is used to block neutrons with energy less than the first energy; The neutron conversion layer is used to react with incident neutrons to produce secondary charged particles; The detector unit is used to detect the secondary charged particles and generate a signal.

[0020] It should be noted that the arrangement sequence of the first detection unit 1 , the second detection unit 2 , and the third detection unit 3 is not limited to a vertical arrangement, and may be a parallel arrangement or any other arrangement, depending on actual needs.

[0021] Specifically, in one 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 which are arranged in sequence from top to bottom.

[0022] Specifically, in one 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 which are arranged in sequence from top to bottom.

[0023] Specifically, in one 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 which are arranged in sequence from top to bottom.

[0024] Specifically, see Figure 2-Figure 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.

[0025] Specifically, see Figure 2-Figure 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.

[0026] 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 than three, depending on actual needs.

[0027] Specifically, see Figure 2-Figure 4 In a specific embodiment, the area and thickness 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 the area and thickness of the first detector unit 4, the third detector unit 6 and the fifth detector unit 8 can be appropriately selected 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, that is, the area and thickness of the first detector unit 4, the third detector unit 6 and the fifth detector unit 8 can be selected according to actual needs.

[0028] Specifically, see Figure 2-Figure 4 In a specific embodiment, the area and thickness 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 the area and thickness of the second detector unit 5, the fourth detector unit 7 and the sixth detector unit 9 can be appropriately selected 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, that is, the area and thickness of the second detector unit 5, the fourth detector unit 7 and the sixth detector unit 9 can be selected according to actual needs.

[0029] Specifically, see Figure 2-Figure 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 material, area and thickness of the second neutron conversion layer 11 and the third neutron conversion layer 12 are the same. It should be noted that the area and thickness of the second neutron conversion layer 11 and the third neutron conversion layer 12 can be appropriately selected according to the energy and detection efficiency requirements of the neutrons to be detected, that is, the area and thickness of the second neutron conversion layer 11 and the third neutron conversion layer 12 can be selected according to actual needs.

[0030] Specifically, see Figure 4 The material of the neutron shielding layer 13 can be a material such as metal cadmium or metal gadolinium that can block neutrons with energy less than the first energy.

[0031] Specifically, see 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 between neutrons having energy less than the first energy and the first neutron conversion layer 10.

[0032] The neutron dose detection device of the present invention, through its special structural design, uses a compact semiconductor detector, occupies a small space, can be applied to miniaturized and low-power equipment, and can more accurately detect the energy of incident neutrons.

[0033] The embodiment of the present invention also provides a full-energy range neutron spectrum detection method, using the above-mentioned neutron dose detection device, see Figure 1-Figure 4 , which contains the following steps: S1. placing the neutron dose detection device in a radiation environment of neutrons with various energies, and obtaining deposition energy through the first detection unit 1, the second detection unit 2 and the third detection unit 3; S2, the incident neutrons react with the neutron conversion layer in the detection unit to produce secondary charged particles, and the secondary charged particles are detected by the detector unit and a signal is generated; S3, obtaining the number of neutrons in multiple energy segments according to the signals generated by different detector units; S4, generating a first deposition energy distribution diagram according to the signal generated by the third detector unit 6 in the second detection unit 2 and the signal generated by the fourth detector unit 7, generating a second deposition energy distribution diagram according to the signal generated by the fifth detector unit 8 in the third detection unit 3 and the signal generated by the sixth detector unit 9, and extracting the recoil proton energy spectrum generated by the nuclear reaction between the incident neutron and the LiH-containing material or the neutron conversion layer containing LiOH by using a ΔE-E energy measurement method; specifically, extracting the recoil proton energy spectrum generated by the nuclear reaction between the incident neutron and the LiH or LiOH by using a ΔE-E energy measurement method. 1 The energy spectrum of recoil protons produced by H nuclear reactions provides data for inverting the energy spectrum of incident neutrons.

[0034] Specifically, see Figure 1-Figure 4 , the above step S3 further comprises: S31. 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, the number of neutrons with energy less than the first energy is obtained; 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.

[0035] S32, obtaining the number of neutrons having an energy greater than the first energy and less than the second energy according to the number of events in which the sixth detector unit 9 in the third detection unit 3 does not generate a signal but the fifth detector unit 8 in the third detection unit 3 generates a signal; S33. 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, the number of neutrons with energy greater than the third energy is obtained; wherein 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.

[0036] S34, obtaining the number of neutrons having an energy less than the second energy according to the number of events in which the fourth detector unit 7 in the second detection unit 2 does not generate a signal but the third detector unit 6 in the second detection unit 2 generates a signal; S35. 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, the number of neutrons with energy greater than the second energy and less than the third energy is obtained; 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 from the number of signals generated by the third detector unit 6, and then subtracting the number of neutrons with energy less than the second energy.

[0037] The above-mentioned full-energy range neutron energy spectrum detection method of the present invention can effectively detect and distinguish incident neutrons of different energies.

[0038] Since it is difficult to obtain neutrons with a specific energy distribution in actual experiments, the neutrons with a specific energy distribution are simulated by using the Geant4 simulation software, and then the neutron dose detection device and the full-energy neutron spectrum detection method of the present invention are used to detect neutrons to verify their effectiveness.

[0039] In this embodiment, the first detector unit 4, the third detector unit 6 and the fifth detector unit 8 all use a silicon detector 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 silicon detector with a thickness of 65 μm and a side length of 20 mm, and the first neutron conversion layer 10 uses a silicon-rich layer with a thickness of 28 μm and a side length of 20 mm. 6 LiF of Li, 6 The Li abundance is 95%, and the second neutron conversion layer 11 and the third neutron conversion layer 12 are both made of a rich 6 LiH of Li, 6 The Li abundance is 95%, the neutron shielding layer 13 uses 1 mm thick metal gadolinium, and the neutron energy of the first energy is set to 0.4 eV, the neutron energy of the second energy is set to E1, and the neutron energy of the third energy is set to E2.

[0040] See also Figure 5 , neutrons with different energies are injected, and the penetration rate after passing through 1 mm thick gadolinium Gd is calculated according to Figure 5 It can be seen that metallic gadolinium can block neutrons with energies less than 0.4 eV.

[0041] The third detector unit 6 can detect secondary particle signals produced by nuclear reactions of neutrons of all energies and the second neutron conversion layer 11, while the fifth detector unit 8 can only detect secondary particle signals produced by nuclear reactions of neutrons with energies higher than 0.4 eV and the third neutron conversion layer 12. The number N1 of neutrons with energies 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.

[0042] See also Figure 6 , Figure 6 Neutrons of different energies pass through 6 Li(n,T) 4 The maximum energy of tritium produced by He reaction emitted from the neutron conversion layer is Figure 6 The horizontal dashed line in the figure indicates that the maximum energy of tritium that can be deposited in 65μm silicon is 2.9MeV. The tritium produced by neutrons with energy exceeding 0.3 MeV can penetrate 65μm silicon. The number of neutrons N2 with energy between 0.4 eV-E1 (E1=0.3MeV) can be obtained from the number of events that do not generate signals in the sixth detector unit 9 but generate signals in the fifth detector unit 8. See also Figure 7 , Figure 7 Neutrons of different energies pass through 1 The maximum energy of protons ejected from the conversion layer by the H(n,EL) reaction is Figure 7 The horizontal dotted line in the figure 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 detection 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 pass through the first neutron conversion layer 10 to generate recoil protons and reach the second detector unit 5, then the number N3 of neutrons 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.

[0043] Continue to see Figure 6 , tritium produced by neutrons with energy exceeding 0.3 MeV can penetrate 65 μm of silicon, and the number N4 of neutrons with energy less than E1 can be obtained from the number of events in which the fourth detector unit 7 does not generate a signal but generates a signal in the third detector unit 6 .

[0044] The third detector unit 6 can detect neutrons of all energies and secondary particle signals generated by the reaction of the second neutron conversion layer 11. The number of neutrons with energies 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, 0.4eV-E1, E1-E2, and greater than E2 can be obtained.

[0045] See also Figure 8 The neutron energy E1 and the neutron energy E2 are adjusted by the thickness of the first detector unit 4, the third detector unit 6 and the fifth detector unit 8. E1 is the value corresponding to the tritium that can be completely deposited in silicon of different thicknesses. 6 Li(n,T) 4 The neutron energy of He, E2 is the energy of protons that can be completely deposited in silicon of different thicknesses 1 The neutron energy of H(n,EL) is that for a certain thickness of silicon, a neutron with energy E1 passes through 6 Li(n,T) 4 The tritium produced by the He reaction can just penetrate, while the neutron with energy E2 passes through 1 The protons produced by the H(n,EL) reaction can just penetrate.

[0046] See also Fig. 9 , the incident neutrons with uniform energy between 0.3 MeV and 4 MeV, the neutrons vertically incident on the second detection unit 2 in front of the second neutron conversion layer 11, Fig. 9 From the correspondence between the deposition energies in the third detector unit 6 and the fourth detector unit 7, it can be clearly seen that the recoil proton deposition energy spectrum is extracted based on the tritium and proton signals generated by the reaction between the neutrons and the second neutron conversion layer 11 and their respective strip shapes, providing data for inverting the incident neutron energy spectrum.

[0047] The above embodiments are used to explain the present invention rather than to limit the present invention. Any modification and change made to the present invention within the spirit of the present invention and the protection scope of the claims shall fall within the protection scope of the present invention.

Claims

1. A neutron dose detection device, characterized in that: include: Three detection units, including a first detection unit, a second detection unit, and a third detection unit, each detection unit including a neutron conversion layer and two detector units arranged in sequence from top to bottom; Wherein, a neutron shielding layer is provided around the outer periphery of 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 produce secondary charged particles; The detector unit is used to detect the secondary charged particles and generate signals.

2. The neutron dose detection device according to claim 1, characterized in that: The first detection unit includes a first neutron conversion layer, a first detector unit, and a second detector unit which are arranged in sequence from top to bottom; 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; The third detection unit includes a third neutron conversion layer, a fifth detector unit, and a sixth detector unit which are arranged in sequence from top to bottom.

3. The neutron dose detection device according to claim 2, characterized in that: The first detector unit, the third detector unit and the fifth detector unit include a semiconductor detector; The second detector unit, the fourth detector unit and the sixth detector unit include at least one semiconductor detector.

4. The neutron dose detection device according to claim 2, characterized in that: The first detector unit, the third detector unit and the fifth detector unit have the same area and thickness.

5. The neutron dose detection device according to claim 2, characterized in that: The second detector unit, the fourth detector unit and the sixth detector unit have the same area and thickness.

6. The neutron dose detection device according to claim 2, characterized in that: The first neutron conversion layer is made of LiF-containing material; The second neutron conversion layer and the third neutron conversion layer are made of LiH-containing material or LiOH-containing material, and the second neutron conversion layer and the third neutron conversion layer have the same material, area and thickness.

7. The neutron dose detection device according to claim 3, characterized in that: By selecting the thickness of the first detector unit, the first detector unit is enabled to block secondary charged particles generated by nuclear reactions between neutrons having energy less than the first energy and the first neutron conversion layer.

8. 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 7, characterized in that: Contains the following steps: S1. placing the neutron dose detection device in a radiation environment of neutrons with various energies, and obtaining deposition energy through the first detection unit, the second detection unit, and the third detection unit; 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; S3. Obtain the neutron numbers of multiple energy segments according to the signals generated by different detector units.

9. The full-energy-range neutron spectrum detection method according to claim 8, characterized in that: The step S3 further comprises: S31, obtaining the number of neutrons having an 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, obtaining the number of neutrons having an energy greater than the first energy and less than the second energy according to the number of events in which the sixth detector unit in the third detection unit does not generate a signal but the fifth detector unit in the third detection unit generates a signal; S33, obtaining the number of neutrons having an energy greater than a third energy according to 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, obtaining the number of neutrons having an energy less than the second energy according to the number of events in which the fourth detector unit in the second detection unit does not generate a signal but the third detector unit in the second detection unit generates a signal; S35. According to 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, the number of neutrons with energy greater than the second energy and energy less than the third energy is obtained.

10. The full-energy-range neutron spectrum detection method according to claim 8, characterized in that: The method further comprises: S4. Generate a first deposition energy distribution diagram according to the signal generated by the third detector unit and the signal generated by the fourth detector unit in the second detection unit, generate a second deposition energy distribution diagram according to the signal generated by the fifth detector unit and the signal generated by the sixth detector unit in the third detection unit, and extract a recoil proton energy spectrum generated by a nuclear reaction between an incident neutron and a neutron conversion layer containing a LiH material or a LiOH material by a ΔE-E energy measurement method.

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