A nuclear power plant neutron energy spectrum and direction measurement device, system, and method

Abstract

The application relates to a nuclear power plant neutron energy spectrum and direction measuring device, system and method, which comprises a packaging shell, the packaging shell comprises an upper shell and a lower shell, a detection module is arranged between the upper shell and the lower shell, the detection module comprises a support and a plurality of plastic scintillators, the support is used for fixing and spacing the plurality of plastic scintillators to shield neutrons, a first signal acquisition module is arranged between the upper shell and the detection module and is used for acquiring a first group of scintillation light signals generated by the plurality of plastic scintillators close to one end of the upper shell, and a second signal acquisition module is arranged between the detection module and the lower shell and is used for acquiring a second group of scintillation light signals generated by the plurality of plastic scintillators close to one end of the lower shell. The application can realize simultaneous measurement of neutron energy spectrum and direction, has the advantages of lightness, radiation resistance and real-time monitoring, and is suitable for nuclear power neutron energy spectrum and direction measurement.

Description

Technical Field

[0001] This invention relates to the field of nuclear radiation monitoring, and more specifically, to a device, system, and method for measuring the neutron energy spectrum and direction in a nuclear power plant. Background Technology

[0002] Nuclear reactors generate a large number of neutrons during operation, and their energy distribution (energy spectrum) and spatial distribution (direction) directly affect reactor power control, fuel consumption rate, and radiation protection design. Furthermore, the lack of direction measurement technology may lead to the failure to detect neutron leakage or excessively high local doses in a timely manner.

[0003] Early neutron detectors (such as ³He proportional counters) lacked sufficient sensitivity to high-energy neutrons (>10 MeV) and struggled to distinguish between neutrons and gamma rays, resulting in significant energy spectrum measurement errors. Currently, the most widely used method for neutron energy spectrum measurement is the multi-sphere neutron spectrometer. This method utilizes multiple moderating spheres with varying moderating thicknesses to slow down fast neutrons at different energy levels to the slow neutron energy region, which are then measured by an internal slow neutron detector. Each moderating sphere has a different neutron response function, and the combination of multiple spheres forms a unique neutron response matrix. The neutron response matrix of the multi-sphere spectrometer is obtained through experiments or simulations, and then the spectrum is deciphered using iterative methods and other algorithms to obtain the neutron energy spectrum of the target source. Besides multi-sphere neutron spectrometers, there are also single-sphere neutron spectrometers and activated neutron spectrometers. However, these spectrometers, similar to multi-sphere spectrometers, are suitable for directional and collimated field measurements and suffer from drawbacks such as bulky equipment, inability to measure neutron direction, or a lower upper limit for measured energy. Summary of the Invention

[0004] The technical problem to be solved by the present invention is to provide a device, system and method for measuring neutron energy spectrum and direction in nuclear power plants, addressing the problems existing in the prior art.

[0005] The technical solution adopted by this invention to solve its technical problem is: constructing a neutron energy spectrum and direction measurement device for nuclear power plants, comprising: Encapsulation housing; the encapsulation housing includes an upper housing and a lower housing; A detection module is disposed between the upper housing and the lower housing; the detection module includes: a support member and a plurality of plastic scintillators; the support member is used to fix the plurality of plastic scintillators and separate the plurality of plastic scintillators to shield neutrons; The first signal acquisition module is disposed between the upper housing and the detection module, and is used to acquire the first set of scintillating light signals generated by the plurality of plastic scintillators near the end of the upper housing; The second signal acquisition module is located between the detection module and the lower housing, and is used to acquire the second set of flashing light signals generated by the plurality of plastic scintillators near one end of the lower housing.

[0006] In the neutron energy spectrum and direction measurement device for nuclear power plants described in this invention, the support member has a cross-shaped structure, and the plurality of plastic scintillators include: a first scintillator, a second scintillator, a third scintillator, and a fourth scintillator; The first scintillator, the second scintillator, the third scintillator, and the fourth scintillator are fixed to the support in a cross shape.

[0007] In the neutron energy spectrum and direction measurement device for nuclear power plants described in this invention, the support member is a cross-shaped high-density polyethylene.

[0008] In the neutron energy spectrum and direction measurement device for nuclear power plants described in this invention, each of the plastic scintillators is a long strip structure; Each of the plastic scintillators is covered with a reflective film, which is used to reflect the fluorescence emitted by the plastic scintillator.

[0009] In the neutron energy spectrum and direction measurement device for nuclear power plants described in this invention, the first signal acquisition module includes: a first circuit board and a first detector, a second detector, a third detector and a fourth detector fixed on the first circuit board; The first circuit board includes a first opening, a second opening, a third opening, and a fourth opening; the first opening, the second opening, the third opening, and the fourth opening are respectively disposed corresponding to the ends of the first scintillator, the second scintillator, the third scintillator, and the fourth scintillator facing the upper housing. The first detector, the second detector, the third detector, and the fourth detector are respectively fixed in the first opening, the second opening, the third opening, and the fourth opening; The first detector is used to detect the scintillating light signal generated by the first scintillator towards the end of the upper housing; The second detector is used to detect the scintillating light signal generated by the second scintillator towards the end of the upper housing; The third detector is used to detect the scintillating light signal generated by the third scintillator toward the end of the upper housing; The fourth detector is used to detect the scintillating light signal generated by the fourth scintillator towards the end of the upper housing.

[0010] In the neutron energy spectrum and direction measurement device for nuclear power plants described in this invention, the second signal acquisition module includes: a second circuit board and a fifth detector, a sixth detector, a seventh detector and an eighth detector fixed on the second circuit board; The second circuit board includes a fifth opening, a sixth opening, a seventh opening, and an eighth opening; the fifth opening, the sixth opening, the seventh opening, and the eighth opening are respectively disposed corresponding to the ends of the first scintillator, the second scintillator, the third scintillator, and the fourth scintillator facing the lower housing; The fifth detector, the sixth detector, the seventh detector, and the eighth detector are respectively fixed in the fifth opening, the sixth opening, the seventh opening, and the eighth opening; The fifth detector is used to detect the scintillating light signal generated by the first scintillator toward the end of the lower housing; The sixth detector is used to detect the scintillating light signal generated by the second scintillator toward the end of the lower housing; The seventh detector is used to detect the scintillating light signal generated by the third scintillator toward the end of the lower housing; The eighth detector is used to detect the scintillating light signal generated by the fourth scintillator towards the end of the lower housing.

[0011] In the neutron energy spectrum and direction measurement device for nuclear power plants described in this invention, the first detector, the second detector, the third detector, the fourth detector, the fifth detector, the sixth detector, the seventh detector, and the eighth detector are all silicon photomultiplier tubes.

[0012] The neutron energy spectrum and direction measurement device for nuclear power plants described in this invention further includes: a first preprocessing module and a second preprocessing module; The first preprocessing module is connected to the first signal acquisition module and is used to preprocess the first group of flashing light signals; The second preprocessing module is connected to the second signal acquisition module and is used to preprocess the second set of flashing light signals.

[0013] The present invention also provides a neutron energy spectrum and direction measurement system for nuclear power plants, comprising: an energy spectrum measurement module, a direction measurement module, and the aforementioned neutron energy spectrum and direction measurement device for nuclear power plants; The energy spectrum measurement module is used to collect the first set of scintillation signals and the second set of scintillation signals, and to process and invert the neutron energy spectrum based on the first set of scintillation signals and the second set of scintillation signals. The direction measurement module is used to collect the first set of scintillation signals and the second set of scintillation signals, and to calculate the neutron direction based on the first set of scintillation signals and the second set of scintillation signals.

[0014] This invention also provides a method for measuring the neutron energy spectrum and direction in a nuclear power plant, applied to the aforementioned nuclear power plant neutron energy spectrum and direction measurement system, comprising: The first signal acquisition module acquires the first set of flashing light signals; The second signal acquisition module acquires the second set of flashing light signals; The neutron energy spectrum is obtained by processing and inversion calculation based on the first set of scintillation signals and the second set of scintillation signals. The neutron direction is obtained by calculation based on the first set of scintillation signals and the second set of scintillation signals.

[0015] The neutron spectrum and direction measurement device, system, and method for nuclear power plants implementing the present invention have the following beneficial effects: It includes: an encapsulated shell; the encapsulated shell includes an upper shell and a lower shell; a detection module disposed between the upper shell and the lower shell; the detection module includes: a support member and multiple plastic scintillators; the support member is used to fix the multiple plastic scintillators and separate them to shield against neutrons; a first signal acquisition module disposed between the upper shell and the detection module, used to acquire a first set of scintillator light signals generated by the multiple plastic scintillators near the end of the upper shell; a second signal acquisition module disposed between the detection module and the lower shell, used to acquire a second set of scintillator light signals generated by the multiple plastic scintillators near the end of the lower shell. The present invention enables simultaneous measurement of neutron spectrum and direction, and has the advantages of being lightweight, radiation-resistant, and capable of real-time monitoring, making it suitable for neutron spectrum and direction measurement in nuclear power plants. Attached Figure Description

[0016] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings: Figure 1 This is a schematic diagram of the structure of the neutron energy spectrum and direction measurement device for nuclear power plants provided by the present invention; Figure 2 This is a schematic diagram showing the positions of the plastic scintillator and the cross-shaped support provided by the present invention; Figure 3 This is a flowchart of the method for measuring the neutron energy spectrum and direction in nuclear power plants provided by the present invention. Detailed Implementation

[0017] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0018] refer to Figure 1This invention provides a device for measuring the neutron energy spectrum and direction in nuclear power plants. This device can simultaneously measure the neutron energy spectrum and neutron direction, and has advantages such as portability, radiation resistance (SiPM tolerance not less than 100 kGy), and real-time monitoring, making it suitable for measuring the neutron energy spectrum and direction in nuclear power plants.

[0019] Specifically, such as Figure 1 As shown, the neutron energy spectrum and direction measurement device of the nuclear power plant includes: an encapsulation shell, a detection module, a first signal acquisition module 2, and a second signal acquisition module 6.

[0020] The encapsulation shell includes an upper shell 1 and a lower shell 7; the upper shell 1 and the lower shell 7 can be fixed together by bolts, and the dimensions of the upper shell and the lower shell 7 are determined by the detection module. Preferably, in order to improve the detection accuracy of the detection module, the encapsulation shell material needs to be a low atomic number material.

[0021] In some embodiments, the detection module is disposed between the upper housing 1 and the lower housing 7. This detection module enables the measurement of the neutron energy spectrum and neutron direction. The detection module possesses good n-γ discrimination capability. Preferably, in some embodiments, the detection module includes a support member 4 and multiple plastic scintillators; the support member 4 is used to fix and separate the multiple plastic scintillators to shield against neutrons.

[0022] Preferably, in this embodiment of the invention, the support member 4 has a cross-shaped structure. Specifically, the cross-shaped support member 4 is made of cross-shaped high-density polyethylene. By using cross-shaped high-density polyethylene, neutrons can be shielded, thereby allowing scintillators at different locations to have different count rates, further enabling the measurement of neutron direction. Optionally, the high-density polyethylene can be 0.9~1.0 g / cm³. 3 0.95 g / cm³ is preferred. 3 .

[0023] Furthermore, to ensure the accuracy and reliability of subsequent neutron energy spectrum measurements and neutron direction measurements, the cross-shaped high-density polyethylene used in this invention has a specific thickness and width (…). t and w The Monte Carlo method needs to be used to simulate and optimize the cross-shaped high-density polyethylene to obtain the optimal thickness and width. Figure 1 The thickness and width of the cross-shaped high-density polyethylene were obtained by simulating the cross-shaped high-density polyethylene using the Monte Carlo method, which simulates the counting of four plastic scintillators under different incident angles.

[0024] In a preferred embodiment, such as Figure 1As shown, the plurality of plastic scintillators include: a first scintillator 401, a second scintillator 402, a third scintillator 403, and a fourth scintillator 404; the first scintillator 401, the second scintillator 402, the third scintillator 403, and the fourth scintillator 404 are fixed to the support member 4 in a cross shape. Specifically, as shown... Figure 2 As shown, the four scintillators are arranged in a cross shape. In this embodiment of the invention, each plastic scintillator has an elongated structure. To reduce fluorescence loss and improve the collection efficiency of the first signal acquisition module 2 and the second signal acquisition module 6, in this embodiment of the invention, each plastic scintillator is covered with a reflective film 400, which reflects the fluorescence emitted by the plastic scintillator. The reflective film 400 can be made of titanium dioxide coating.

[0025] like Figure 1 As shown, in this embodiment of the invention, the first signal acquisition module 2 is disposed between the upper housing 1 and the detection module, and is used to acquire the first set of flashing light signals generated by multiple plastic scintillators near one end of the upper housing 1. The first signal acquisition module 2 includes: a first circuit board 3 and a first detector, a second detector, a third detector and a fourth detector fixed on the first circuit board 3; the first circuit board 3 includes a first opening, a second opening, a third opening and a fourth opening; the first opening, the second opening, the third opening and the fourth opening are respectively disposed corresponding to the ends of the first scintillator 401, the second scintillator 402, the third scintillator 403 and the fourth scintillator 404 facing the upper housing 1; the first detector, the second detector, the third detector and the fourth detector are respectively fixed in the first opening, the second opening, the third opening and the fourth opening.

[0026] The first detector is used to detect the flash light signal generated by the first scintillator 401 towards the end of the upper housing 1; the second detector is used to detect the flash light signal generated by the second scintillator 402 towards the end of the upper housing 1; the third detector is used to detect the flash light signal generated by the third scintillator 403 towards the end of the upper housing 1; and the fourth detector is used to detect the flash light signal generated by the fourth scintillator 404 towards the end of the upper housing 1. The flash light signals detected by the first, second, third, and fourth detectors constitute the first set of flash light signals.

[0027] like Figure 1As shown, in this embodiment of the invention, the second signal acquisition module 6 is disposed between the detection module and the lower housing 7, and is used to acquire the second set of flashing light signals generated by multiple plastic scintillators near one end of the lower housing 7. The second signal acquisition module 6 includes: a second circuit board 5 and a fifth detector, a sixth detector, a seventh detector, and an eighth detector fixed on the second circuit board 5; the second circuit board 5 includes a fifth opening, a sixth opening, a seventh opening, and an eighth opening; the fifth opening, the sixth opening, the seventh opening, and the eighth opening are respectively disposed corresponding to the ends of the first scintillator 401, the second scintillator 402, the third scintillator 403, and the fourth scintillator 404 facing the lower housing 7; the fifth detector, the sixth detector, the seventh detector, and the eighth detector are respectively fixed in the fifth opening, the sixth opening, the seventh opening, and the eighth opening.

[0028] The fifth detector is used to detect the scintillating light signal generated by the first scintillator 401 towards the end of the lower housing 7; the sixth detector is used to detect the scintillating light signal generated by the second scintillator 402 towards the end of the lower housing 7; the seventh detector is used to detect the scintillating light signal generated by the third scintillator 403 towards the end of the lower housing 7; and the eighth detector is used to detect the scintillating light signal generated by the fourth scintillator 404 towards the end of the lower housing 7. The scintillating signals detected by the fifth, sixth, seventh, and eighth detectors constitute the second set of scintillating light signals.

[0029] Preferably, in this embodiment of the invention, the first detector, second detector, third detector, fourth detector, fifth detector, sixth detector, seventh detector, and eighth detector are all silicon photomultiplier tubes. The area of ​​the scintillator is consistent with the effective area of ​​the silicon photomultiplier tube, and each scintillator is coupled to its corresponding silicon photomultiplier tube at both ends via silicone grease, thereby ensuring that the gap between the scintillator and the silicon photomultiplier tube is completely filled with silicone grease, avoiding air obstruction. Specifically, as shown... Figure 1 As shown, four openings are respectively provided on the first circuit board 3 and the second circuit board 5. Silicon photomultiplier tubes are fixed through these openings so that the silicon photomultiplier tubes are coupled to the corresponding scintillators.

[0030] Furthermore, in this embodiment of the invention, the neutron energy spectrum and direction measurement device for the nuclear power plant further includes: a first preprocessing module and a second preprocessing module; the first preprocessing module is connected to the first signal acquisition module 2 and is used to preprocess the first set of scintillation signals; the second preprocessing module is connected to the second signal acquisition module 6 and is used to preprocess the second set of scintillation signals. The first preprocessing module is mounted on the first circuit board 3, and the second preprocessing module is mounted on the second circuit board 5. Both the first and second preprocessing modules include a preamplifier circuit and a filter circuit, which improve the reliability and stability of signal acquisition while reducing signal noise interference.

[0031] This invention also provides a neutron energy spectrum and direction measurement system for nuclear power plants. It includes: an energy spectrum measurement module, a direction measurement module, and the neutron energy spectrum and direction measurement device for nuclear power plants disclosed in this embodiment. The energy spectrum measurement module and the direction measurement module can be installed on the host of an external device.

[0032] The energy spectrum measurement module is used to acquire a first set of scintillation signals and a second set of scintillation signals, and to process and invert these signals to obtain the neutron energy spectrum. In this embodiment, the energy spectrum measurement module can use Cs-137, Na-22, or Am-Be sources for energy calibration. Then, a detector response matrix is ​​established using the Monte Carlo method to simulate the photon output distribution of monoenergetic neutrons (0.2–60 MeV, step size 0.5 MeV) in the scintillator. The measured Am-Be source neutron light output is combined with the response matrix and the ISO reference spectrum for spectral decomposition, and the energy distribution is inverted using an iterative algorithm (such as MAXED, but not limited to it).

[0033] The direction measurement module is used to collect the first set of scintillation signals and the second set of scintillation signals, and to calculate the neutron direction based on the first set of scintillation signals and the second set of scintillation signals. In this embodiment of the invention, the neutron energy spectrum and direction measurement device of the nuclear power plant uses the shielding effect of cross-shaped high-density polyethylene on neutrons, and then the direction measurement module combines the technical differences of the four scintillators to back-calculate the incident angle.

[0034] refer to Figure 3 The present invention also provides a method for measuring the neutron energy spectrum and direction in a nuclear power plant. This method for measuring the neutron energy spectrum and direction in a nuclear power plant can be implemented using the nuclear power plant neutron energy spectrum and direction measurement system provided by the present invention.

[0035] Specifically, such as Figure 3 As shown, the neutron energy spectrum and direction measurement methods of this nuclear power plant include: Step S301: The first signal acquisition module 2 acquires the first group of flashing light signals.

[0036] Specifically, after the first set of flashing light signals is acquired by the first signal acquisition module 2, in order to improve the accuracy of signal acquisition, the first preprocessing module needs to preprocess the first set of flashing light signals, such as amplification and filtering.

[0037] Step S302: The second signal acquisition module 6 acquires the second set of flashing light signals.

[0038] Specifically, after the second set of flashing light signals is acquired by the second signal acquisition module 6, in order to improve the accuracy of signal acquisition, the second preprocessing module needs to preprocess the second set of flashing light signals, such as amplification and filtering.

[0039] Step S303: Process and invert the first set of scintillation signals and the second set of scintillation signals to obtain the neutron energy spectrum.

[0040] Specifically, in this step, the neutron energy spectrum is obtained as follows: First, energy calibration was performed using Cs-137, Na-22, and Am-Be sources. To control statistical error within the low count range of 9–11 MeV, at least 10-10 MeV accumulations were required. 5 The event refers to the cumulative neutron count in the 9-11 MeV range; the higher the count, the smaller the statistical error.

[0041] Secondly, the response matrix is ​​obtained by simulating the photon output distribution of monoenergetic neutrons (0.2–60 MeV step size 0.5 MeV) in the scintillator using the Monte Carlo method based on the accumulated neutron count.

[0042] Next, the optical output spectrum of the Am-Be neutron source was measured, and the spectrum was deciphered by combining the response matrix and the ISO reference spectrum. The energy distribution was inverted using an iterative algorithm (such as MAXED, but not limited to this) to obtain the neutron energy spectrum.

[0043] Step S304: Calculate the neutron direction based on the first set of scintillation signals and the second set of scintillation signals.

[0044] Specifically, in this step, counting is performed based on the first and second sets of scintillating light signals to obtain four scintillator counts, defined as (LT, RT, LB, RB), where LT represents the scintillator located at the upper left of the cross-shaped high-density polyethylene (i.e., the first scintillator 401), RT represents the scintillator located at the upper right of the cross-shaped high-density polyethylene (i.e., the second scintillator 402), LB represents the scintillator located at the lower left of the cross-shaped high-density polyethylene (i.e., the third scintillator 403), and RB represents the scintillator located at the upper right of the cross-shaped high-density polyethylene (i.e., the fourth scintillator 404). Neutron incident direction Defined as the angle with the horizontal axis. Where, when At that time, the LT and RT counts were similar, while the LB and RB counts decreased due to the high-density polyethylene shielding. At that time, RT has the highest count (direct incidence), LB has the lowest count (maximum shielding), and LT and RB have moderate counts due to partial shielding effects. Based on this principle, the normalized position vector is calculated according to the counts of the four scintillators (LT, RT, LB, RB). . The specific expression is as follows: (1); In the above formula, LT, RT, LB, and RB are the counts of the corresponding scintillators; , , , These represent the complete vectors of the corresponding scintillators. For example, LT The vector represents the length, and its value refers to the count of the first scintillator 401. <-1,1> indicates the direction of the vector, representing the coordinate system in which the vector is positioned. LT It is the upper left corner (i.e., the second quadrant).

[0045] Therefore, after calculating the normalized position vector according to equation (1), the neutron incident direction can be obtained by using the angle reconstruction formula. The angle reconstruction formula is as follows: (2); in, and for The coordinate components.

[0046] The various embodiments in this specification are described in a progressive manner, with each embodiment focusing on its differences from other embodiments. Similar or identical parts between embodiments can be referred to interchangeably. For the apparatus disclosed in the embodiments, since they correspond to the methods disclosed in the embodiments, the description is relatively simple; relevant parts can be referred to the method section.

[0047] Those skilled in the art will further recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of both. To clearly illustrate the interchangeability of hardware and software, the components and steps of the various examples have been generally described in terms of functionality in the foregoing description. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementations should not be considered beyond the scope of this invention.

[0048] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein can be implemented directly by hardware, a software module executed by a processor, or a combination of both. The software module can be located in random access memory (RAM), main memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art.

[0049] The above embodiments are only for illustrating the technical concept and features of the present invention, and are intended to enable those skilled in the art to understand the content of the present invention and implement it accordingly. They do not limit the scope of protection of the present invention. All equivalent changes and modifications made within the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A device for measuring the neutron energy spectrum and direction in a nuclear power plant, characterized in that, include: Encapsulation shell; The encapsulation housing includes an upper housing and a lower housing; The detection module is disposed between the upper housing and the lower housing; The detection module includes a support member and multiple plastic scintillators; the support member is used to fix the multiple plastic scintillators and separate them to shield neutrons; The first signal acquisition module is disposed between the upper housing and the detection module, and is used to acquire the first set of scintillating light signals generated by the plurality of plastic scintillators near the end of the upper housing; The second signal acquisition module is located between the detection module and the lower housing, and is used to acquire the second set of flashing light signals generated by the plurality of plastic scintillators near one end of the lower housing.

2. The neutron energy spectrum and direction measurement device for nuclear power plants according to claim 1, characterized in that, The support member has a cross-shaped structure, and the plurality of plastic scintillators include: a first scintillator, a second scintillator, a third scintillator, and a fourth scintillator; The first scintillator, the second scintillator, the third scintillator, and the fourth scintillator are fixed to the support in a cross shape.

3. The neutron energy spectrum and direction measuring device for nuclear power plants according to claim 1, characterized in that, The support component is a cross-shaped high-density polyethylene.

4. The neutron energy spectrum and direction measuring device for nuclear power plants according to claim 1, characterized in that, Each of the aforementioned plastic scintillators has an elongated strip-shaped structure; Each of the plastic scintillators is covered with a reflective film, which is used to reflect the fluorescence emitted by the plastic scintillator.

5. The neutron energy spectrum and direction measuring device for nuclear power plants according to claim 2, characterized in that, The first signal acquisition module includes: a first circuit board and a first detector, a second detector, a third detector and a fourth detector fixed on the first circuit board; The first circuit board includes a first opening, a second opening, a third opening, and a fourth opening; the first opening, the second opening, the third opening, and the fourth opening are respectively disposed corresponding to the ends of the first scintillator, the second scintillator, the third scintillator, and the fourth scintillator facing the upper housing. The first detector, the second detector, the third detector, and the fourth detector are respectively fixed in the first opening, the second opening, the third opening, and the fourth opening; The first detector is used to detect the scintillating light signal generated by the first scintillator towards the end of the upper housing; The second detector is used to detect the scintillating light signal generated by the second scintillator towards the end of the upper housing; The third detector is used to detect the scintillating light signal generated by the third scintillator toward the end of the upper housing; The fourth detector is used to detect the scintillating light signal generated by the fourth scintillator towards the end of the upper housing.

6. The neutron energy spectrum and direction measuring device for nuclear power plants according to claim 5, characterized in that, The second signal acquisition module includes: a second circuit board and a fifth detector, a sixth detector, a seventh detector and an eighth detector fixed on the second circuit board; The second circuit board includes a fifth opening, a sixth opening, a seventh opening, and an eighth opening; the fifth opening, the sixth opening, the seventh opening, and the eighth opening are respectively disposed corresponding to the ends of the first scintillator, the second scintillator, the third scintillator, and the fourth scintillator facing the lower housing; The fifth detector, the sixth detector, the seventh detector, and the eighth detector are respectively fixed in the fifth opening, the sixth opening, the seventh opening, and the eighth opening; The fifth detector is used to detect the scintillating light signal generated by the first scintillator toward the end of the lower housing; The sixth detector is used to detect the scintillating light signal generated by the second scintillator toward the end of the lower housing; The seventh detector is used to detect the scintillating light signal generated by the third scintillator toward the end of the lower housing; The eighth detector is used to detect the scintillating light signal generated by the fourth scintillator towards the end of the lower housing.

7. The neutron energy spectrum and direction measuring device for nuclear power plants according to claim 6, characterized in that, The first detector, the second detector, the third detector, the fourth detector, the fifth detector, the sixth detector, the seventh detector, and the eighth detector are all silicon photomultiplier tubes.

8. The neutron energy spectrum and direction measuring device for nuclear power plants according to any one of claims 1-7, characterized in that, Also includes: First preprocessing module and second preprocessing module; The first preprocessing module is connected to the first signal acquisition module and is used to preprocess the first group of flashing light signals; The second preprocessing module is connected to the second signal acquisition module and is used to preprocess the second set of flashing light signals.

9. A neutron energy spectrum and direction measurement system for a nuclear power plant, characterized in that, include: The energy spectrum measurement module, the direction measurement module, and the neutron energy spectrum and direction measurement device for nuclear power plants as described in any one of claims 1-8; The energy spectrum measurement module is used to collect the first set of scintillation signals and the second set of scintillation signals, and to process and invert the neutron energy spectrum based on the first set of scintillation signals and the second set of scintillation signals. The direction measurement module is used to collect the first set of scintillation signals and the second set of scintillation signals, and to calculate the neutron direction based on the first set of scintillation signals and the second set of scintillation signals.

10. A method for measuring the neutron energy spectrum and direction in a nuclear power plant, applied to the neutron energy spectrum and direction measurement system of claim 9, characterized in that, include: The first signal acquisition module acquires the first set of flashing light signals; The second signal acquisition module acquires the second set of flashing light signals; The neutron energy spectrum is obtained by processing and inversion calculation based on the first set of scintillation signals and the second set of scintillation signals. The neutron direction is obtained by calculation based on the first set of scintillation signals and the second set of scintillation signals.

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