Spectrum analysis method and computer equipment suitable for self-powered neutron spectrum detection components

Abstract

The embodiments of the present application relate to the research field of neutron energy spectrum detection, and specifically to a spectrum interpretation method and computer equipment suitable for a self-powered neutron energy spectrum detection component. A specific implementation method of the method includes: placing the energy spectrum measurement component into the neutron radiation field to be measured, obtaining the corresponding radiation current measurement value; performing data acquisition and processing on the energy spectrum measurement component; determining the energy zone energy spectrum ratio combination information set; determining the radiation current combination information; screening and processing the radiation current combination information set; determining the root mean square value of the radiation current; and determining the neutron radiation field energy spectrum information corresponding to the neutron radiation field to be measured. This implementation method can cooperate with the self-powered neutron energy spectrum detection component to realize the detection of the neutron energy spectrum, and by analyzing the current signal output by the detector, the energy spectrum to be measured can be solved, and the neutron energy spectrum interpretation can be accurately completed under conditions that are more in line with physical reality.

Description

Technical Field

[0001] The embodiments of the present application relate to the research field of neutron spectrum detection, and more particularly to a spectrum interpretation method and computer equipment applicable to a self-powered neutron spectrum detection component. Background Art

[0002] Neutron spectrum has always been a crucial parameter in reactor design and physical analysis. Numerous methods exist for measuring neutron spectra. For off-reactor neutron spectrum measurements, a multi-sphere spectrometer can be used. For in-core neutron spectrum measurements, multiple activated foils of known cross-sections are placed in the neutron field to be measured. However, given the complex conditions of high temperature and pressure in the core and the confined space of the fuel assembly, a multi-sphere spectrometer system is too large to detect in-core neutrons, and activated foils cannot be used for online measurements.

[0003] Therefore, a spectrum measurement system composed of self-powered neutron detectors is crucial for measuring the neutron spectrum in the reactor core. Commonly used systems consist of multiple self-powered neutron detectors, which analyze the current signals output by the detectors to determine the energy spectrum. However, many existing spectrum analysis methods are not suitable for self-powered neutron detector spectrum measurement systems, making the design of a spectrum analysis method suitable for self-powered neutron spectrum detection components particularly important.

[0004] The self-powered neutron spectrum detection assembly places multiple self-powered detectors in the core neutron field. Neutrons interact with the emitter in the probe to generate radioactive nuclides. The radioactive nuclides decay, and the remaining positive charge in the emitter material forms a positive potential between the emitter and the collector, generating a current signal. The electronics system analyzes this current signal to obtain neutron fluence data. After a self-powered neutron detector reaches stable operating conditions, the current output by the corresponding electronics system satisfies the following current equation:

[0005]

[0006] Where I is the current output by the detector. R(E) is the detector response coefficient when the neutron energy is E. φ(E) is the neutron flux rate at the point with energy E. The above current equation is an energy integral equation. For different self-powered detectors, different I values ​​can be measured and output. Combined with R(E), the neutron energy spectrum Φ(E) can be calculated. However, for practical solutions, this continuous integral equation needs to be discretized, corresponding to the partitions in the energy spectrum:

[0007]

[0008] Where n represents the energy range number of the neutron energy spectrum. When multiple self-powered neutron detectors form a detection system, the following equation is obtained:

[0009]

[0010] Where m represents the serial number of the detector.

[0011] For the multiple currents I output by the self-powered neutron spectrum detection component m Can be measured in actual environment, Φ n Indicates the neutron flux rate in the nth energy region in the neutron energy spectrum, R mn It represents the response coefficient of the mth self-powered neutron detector in the nth energy range, which can be obtained through simulation calculation. The neutron energy spectrum Φ(E) can be solved using the currents and response coefficients of multiple detectors.

[0012] However, in actual engineering applications, there are many methods for this solution process, and many existing methods cannot be directly applied to self-powered neutron spectrum measurement components. Summary of the Invention

[0013] The content of this application is used to briefly introduce concepts that will be described in detail in the detailed description section below. The content of this application is not intended to identify key features or essential features of the technical solution for which protection is sought, nor is it intended to limit the scope of the technical solution for which protection is sought.

[0014] Some embodiments of the present application propose a spectrum interpretation method, a computer device, and a computer-readable storage medium applicable to a self-powered neutron spectrum detection component to solve one or more of the technical problems mentioned in the above background technology section.

[0015] In a first aspect, some embodiments of the present application provide a spectrum interpretation method applicable to a self-powered neutron energy spectrum detection component, the method comprising: placing the energy spectrum measurement component into a neutron radiation field to be measured, and acquiring corresponding radiation current measurement values ​​from each self-powered neutron detector included in the energy spectrum measurement component to obtain a radiation current measurement value set, wherein the above-mentioned energy spectrum measurement component is composed of at least one self-powered neutron detector; performing data acquisition and processing on the above-mentioned energy spectrum measurement component to obtain a neutron radiation energy zone information set to be measured and a detector response coefficient group set; based on the above-mentioned neutron radiation energy zone information set to be measured, determining an energy zone energy spectrum ratio combination information set; based on the above-mentioned detector response coefficient group set, determining the energy zone energy spectrum ratio combination information set for each energy zone in the above-mentioned energy zone energy spectrum ratio combination information. The radiation current combination information corresponding to the energy spectrum proportion combination information is used to obtain a radiation current combination information set, wherein the radiation current combination information in the above-mentioned radiation current combination information set includes: a radiation current combination value set; the above-mentioned radiation current combination information set is screened to obtain a radiation current screening information set; for each radiation current screening information in the above-mentioned radiation current screening information set, the radiation current combination value set included in the above-mentioned radiation current screening information and the root mean square value of the above-mentioned radiation current measurement value set are determined as the radiation current root mean square value; the energy zone energy spectrum proportion combination information corresponding to the smallest radiation current root mean square value among the determined radiation current root mean square values ​​is determined as the neutron radiation field energy spectrum information corresponding to the above-mentioned neutron radiation field to be measured.

[0016] In a second aspect, the present application also provides a computer device, comprising a processor, a memory, and a computer program stored in the memory and executable by the processor, wherein when the computer program is executed by the processor, it implements the method described in any implementation of the first aspect.

[0017] In a third aspect, the present application further provides a computer-readable storage medium, on which a computer program is stored, wherein when the computer program is executed by a processor, the method described in any implementation of the first aspect is implemented.

[0018] The above-described embodiments of the present application have the following beneficial effects: Through the spectrum decomposition methods applicable to self-powered neutron spectrum detection assemblies in some embodiments of the present application, the spectrum decomposition work for core neutron spectrum detection can be accurately completed under conditions that are more consistent with physical reality. Specifically, the difficulty in accurately completing the spectrum decomposition work for core neutron spectrum detection under conditions that are more consistent with physical reality is that the spectrum decomposition work for core neutron spectrum detection is difficult to accurately complete under conditions that are more consistent with physical reality. Existing spectrum decomposition methods are not suitable for self-powered neutron detector spectrum measurement systems that use multiple self-powered neutron detectors to analyze and operate on the current signals output by the detectors to achieve the energy spectrum to be measured. Based on this, the spectrum decomposition methods applicable to self-powered neutron spectrum detection assemblies in some embodiments of the present application first place the spectrum measurement assembly into the neutron radiation field to be measured, and obtain corresponding radiation current measurement values ​​from each self-powered neutron detector included in the spectrum measurement assembly to obtain a set of radiation current measurement values. Secondly, data acquisition and processing are performed on the spectrum measurement assembly to obtain a set of information about the neutron radiation energy range to be measured and a set of detector response coefficients. In this way, the data required for neutron spectrum decomposition can be collected. Then, based on the aforementioned neutron radiation energy region information set to be measured, an energy region energy spectrum ratio combination information set is determined. Then, based on the aforementioned detector response coefficient set, the radiation current combination information corresponding to each energy region energy spectrum ratio combination information in the aforementioned energy region energy spectrum ratio combination information is determined to obtain a radiation current combination information set. Thus, through energy region division and scanning calculation, assumed current values ​​for various assumed energy spectrum partitioning scenarios can be obtained. Next, the aforementioned radiation current combination information set is filtered to obtain a radiation current screening information set. Subsequently, for each radiation current screening information in the aforementioned radiation current screening information set, the root mean square value of the radiation current combination value set included in the aforementioned radiation current screening information and the aforementioned radiation current measurement value set is determined as the radiation current root mean square value. Finally, the energy region energy spectrum ratio combination information corresponding to the smallest radiation current root mean square value among the determined radiation current root mean square values ​​is determined as the neutron radiation field energy spectrum information corresponding to the neutron radiation field to be measured. Thus, one energy spectrum partitioning scenario can be selected from the various assumed energy spectrum partitioning scenarios as the neutron radiation field energy spectrum information. Therefore, some of the spectrum decomposition methods applicable to self-powered neutron energy spectrum detection components of this application can use physical formulas to strictly follow the physical laws to perform calculations in each step, which has a theoretical basis and is more in line with physical reality. The calculation of the entire energy range can also be achieved through full energy spectrum scanning, and the data is complete as a whole. The accuracy of each scan can be determined by setting the scanning step size, and the user can determine the size of the step size value according to the actual situation, and the final solution is more accurate. In addition, a method for eliminating pathological data is added, and the basis for determining data elimination when the total proportion of each energy zone is not the preset value (100%) is given.Therefore, through the spectrum decomposition method applicable to the self-powered neutron energy spectrum detection component, the current signal output by the detector is analyzed and operated to achieve the solution of the energy spectrum to be measured, and the neutron energy spectrum decomposition can be accurately completed under conditions that are more in line with physical reality. BRIEF DESCRIPTION OF THE DRAWINGS

[0019] The above and other features, advantages, and aspects of the various embodiments of the present application will become more apparent with reference to the following detailed description in conjunction with the accompanying drawings. Throughout the drawings, the same or similar reference numerals represent the same or similar elements. It should be understood that the drawings are schematic and that the elements and components are not necessarily drawn to scale.

[0020] Figure 1 is a flow chart of some embodiments of a spectrum decomposition method applicable to a self-powered neutron spectrum detection assembly according to the present application;

[0021] Figure 2 It is a schematic diagram of the structure of a computer device suitable for implementing some embodiments of the present application. DETAILED DESCRIPTION

[0022] The following will describe embodiments of the present application in more detail with reference to the accompanying drawings. Although certain embodiments of the present application are shown in the accompanying drawings, it should be understood that the present application can be implemented in various forms and should not be construed as being limited to the embodiments described herein. On the contrary, these embodiments are provided to provide a more thorough and complete understanding of the present application. It should be understood that the drawings and embodiments of the present application are for illustrative purposes only and are not intended to limit the scope of protection of the present application.

[0023] It should also be noted that, for ease of description, only the parts related to the invention are shown in the drawings. In the absence of conflict, the embodiments and features in the embodiments of this application can be combined with each other.

[0024] It should be noted that the concepts of "first" and "second" mentioned in this application are only used to distinguish different devices, modules or units, and are not used to limit the order or interdependence of the functions performed by these devices, modules or units.

[0025] It should be noted that the modifications of "one" and "multiple" mentioned in this application are illustrative rather than restrictive. Those skilled in the art should understand that unless otherwise clearly indicated in the context, they should be understood as "one or more".

[0026] The names of the messages or information exchanged between multiple devices in the embodiments of the present application are only used for illustrative purposes and are not used to limit the scope of these messages or information.

[0027] The present application will be described in detail below with reference to the accompanying drawings and in combination with embodiments.

[0028] Figure 1 A process 100 of some embodiments of a spectrum decomposition method applicable to a self-powered neutron spectrum detection assembly according to the present application is shown. The spectrum decomposition method applicable to a self-powered neutron spectrum detection assembly includes the following steps:

[0029] Step 101 : placing an energy spectrum measurement component into a neutron radiation field to be measured, and acquiring corresponding radiation current measurement values ​​from each self-powered neutron detector included in the energy spectrum measurement component to obtain a radiation current measurement value set.

[0030] In some embodiments, the execution subject of the spectrum interpretation method applicable to a self-powered neutron spectrum detection component can place the spectrum measurement component into the neutron radiation field to be measured, and obtain the corresponding radiation current measurement value from each self-powered neutron detector included in the spectrum measurement component through a wired connection or a wireless connection to obtain a radiation current measurement value set. The above-mentioned spectrum measurement component can be composed of at least one self-powered neutron detector. The above-mentioned self-powered neutron detector can detect irradiation and generate current in the back-end electronic system. The current value of the generated current is the above-mentioned radiation current measurement value. The number of self-powered neutron detectors in the above-mentioned spectrum measurement component can be a preset detector value.

[0031] As an example, the above-mentioned preset detector value can be but is not limited to at least one of the following: 4, 7 or 16.

[0032] It should be noted that the above-mentioned wireless connection methods may include but are not limited to 3G / 4G connection, WiFi connection, Bluetooth connection, WiMAX connection, Zigbee connection, UWB (ultra wideband) connection, and other wireless connection methods currently known or to be developed in the future.

[0033] Step 102 : performing data acquisition processing on the energy spectrum measurement component to obtain a set of information on the neutron radiation energy range to be measured and a set of detector response coefficients.

[0034] In some embodiments, the execution entity may perform data acquisition and processing on the energy spectrum measurement component to obtain a set of information on the neutron radiation energy range to be measured and a set of detector response coefficients.

[0035] In some optional implementations of some embodiments, the execution subject performs data acquisition and processing on the energy spectrum measurement component to obtain a set of information on the neutron radiation energy range to be measured and a set of detector response coefficients, which may include the following steps:

[0036] The first step is to obtain information about the neutron radiation field region to be measured corresponding to the neutron radiation field to be measured. The information about the neutron radiation field region to be measured corresponding to the neutron radiation field to be measured can be obtained from a storage terminal. The storage terminal can be a terminal for storing the information about the neutron radiation field region to be measured. The information about the neutron radiation field region to be measured can represent the radiation region of the neutron radiation field to be measured.

[0037] The second step is to determine the number of neutron energy regions to be measured based on the number of self-powered neutron detectors included in the energy spectrum measurement component.

[0038] For example, the number of self-powered neutron detectors included in the energy spectrum measurement assembly can be determined as the number of neutron energy region divisions to be measured. Alternatively, a preset number of divisions can be determined as the number of neutron energy region divisions to be measured.

[0039] As an example, the preset number of divisions may be, but is not limited to, at least one of the following: 4, 16, or 69.

[0040] The third step is to divide the region information of the neutron radiation field to be measured based on the number of neutron energy region divisions to be measured to obtain a set of neutron radiation energy region information to be measured. Partitioning the region information of the neutron radiation field to be measured based on the number of neutron energy region divisions to be measured to obtain a set of neutron radiation energy region information to be measured can be accomplished by first evenly dividing the neutron radiation field to be measured corresponding to the region information of the neutron radiation field to be measured into the number of neutron radiation energy region divisions to be measured, and determining the region information corresponding to each divided neutron radiation energy region to be measured as the neutron radiation energy region information to be measured. Then, determining each determined neutron radiation energy region information to be measured as the set of neutron radiation energy region information to be measured. Here, the region information corresponding to the neutron radiation energy region to be measured can represent the radiation area of ​​the neutron radiation energy region to be measured.

[0041] In the fourth step, for each self-powered neutron detector included in the energy spectrum measurement assembly, simulation processing is performed on the self-powered neutron detector to generate detector response coefficients, thereby obtaining a detector response coefficient group. The detector response coefficient groups in the detector response coefficient group correspond one-to-one with the neutron radiation energy range information to be measured in the neutron radiation energy range information set to be measured. Specifically, the self-powered neutron detectors can be simulated using a simulation algorithm to generate the detector response coefficients.

[0042] As an example, the above-mentioned simulation algorithm may be a Geant4 (GEometry And Tracking) program.

[0043] In the fifth step, the generated detector response coefficient groups are determined as a detector response coefficient group set.

[0044] Step 103 : determining an energy range energy spectrum ratio combination information set based on the neutron radiation energy range information set to be measured.

[0045] In some embodiments, the execution entity may determine an energy range and spectrum ratio combination information set based on the neutron radiation energy range information set to be measured.

[0046] In some optional implementations of some embodiments, the execution subject determines the energy range energy spectrum proportion combination information set based on the neutron radiation energy range information set to be measured, which may include the following steps:

[0047] The first step is to generate an energy range spectrum ratio value group corresponding to each neutron radiation energy range information to be measured in the above-mentioned neutron radiation energy range information set to obtain an energy range spectrum ratio value group set.

[0048] In the second step, the energy spectrum ratio values ​​in the energy spectrum ratio value group set are permuted and combined to generate energy spectrum ratio combination information, thereby obtaining an energy spectrum ratio combination information set. A preset permutation and combination algorithm can be used to permutate and combine the energy spectrum ratio values ​​in the energy spectrum ratio value group set to generate energy spectrum ratio combination information, thereby obtaining an energy spectrum ratio combination information set. The energy spectrum ratio combination information may include: an energy spectrum ratio combination value set. The energy spectrum ratio combination values ​​in the energy spectrum ratio combination value set correspond one-to-one to the energy spectrum ratio value groups in the energy spectrum ratio value group set.

[0049] As an example, the above-mentioned preset permutation and combination algorithm may be, but is not limited to, at least one of the following: a cyclic enumeration algorithm, a recursive enumeration algorithm, or a pre-order traversal depth-first search algorithm.

[0050] In some optional implementations of some embodiments, the execution entity generating the energy range spectrum ratio value group corresponding to each piece of neutron radiation energy range information to be measured in the neutron radiation energy range information set to be measured may include the following steps:

[0051] The first step is to determine the first preset value as the upper limit of the neutron energy spectrum ratio.

[0052] As an example, the first preset value may be 90%.

[0053] In the second step, the second preset value is determined as the lower limit value of the neutron energy spectrum ratio.

[0054] As an example, the second preset value may be 10%.

[0055] In the third step, the third preset value is determined as the proportion update step value.

[0056] As an example, the third preset value may be, but is not limited to, at least one of the following: 5% or 10%.

[0057] In the fourth step, based on the lower limit of the neutron energy spectrum ratio and the ratio update step value, the following update sub-steps are performed:

[0058] In the first sub-step, the lower limit value of the neutron energy spectrum ratio is determined as the energy range energy spectrum ratio value.

[0059] In the second sub-step, the sum of the neutron energy spectrum ratio lower limit value and the ratio update step value is determined as the updated neutron energy spectrum ratio lower limit value.

[0060] In the fifth step, in response to determining that the upper limit value of the neutron energy spectrum ratio and the lower limit value of the updated neutron energy spectrum ratio are not equal, the updated lower limit value of the neutron energy spectrum ratio is determined as the lower limit value of the neutron energy spectrum ratio for executing the updating sub-step again.

[0061] In the sixth step, the generated energy spectrum proportion values ​​of each energy region are determined as an energy spectrum proportion value group.

[0062] Step 104 : Based on the detector response coefficient set, radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information is determined to obtain a radiation current combination information set.

[0063] In some embodiments, the execution entity may determine, based on the detector response coefficient set, radiation current combination information corresponding to each energy range energy spectrum ratio combination information in the energy range energy spectrum ratio combination information to obtain a radiation current combination information set. The radiation current combination information in the radiation current combination information set includes a radiation current combination value set.

[0064] In some optional implementations of some embodiments, the execution entity determines, based on the detector response coefficient set, the radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information, which may include the following steps:

[0065] In the first step, for each detector response coefficient group in the above detector response coefficient group set, a radiation current combination value is generated based on the above energy range energy spectrum ratio combination information. The above radiation current combination value can be determined by the following formula:

[0066] I m =R m1 Φ1+R m2 Φ2+…+R mn Φ n .

[0067] Wherein, I represents the current value. m represents the sequence number. n represents the number of energy region energy spectrum ratio combination values ​​in the energy region energy spectrum ratio combination value set included in the above energy region energy spectrum ratio combination information. m It represents the mth radiation current combination value in the radiation current combination value set. R represents the detector response coefficient. m1 Indicates the first detector response coefficient in the mth detector response coefficient group in the detector response coefficient group set. R m2 Represents the second detector response coefficient in the mth detector response coefficient group in the detector response coefficient group set. R mn Indicates the nth detector response coefficient in the mth detector response coefficient group in the detector response coefficient group set. Φ represents the energy range energy spectrum ratio combination value. Φ1 represents the first energy range energy spectrum ratio combination value in the energy range energy spectrum ratio combination value set included in the energy range energy spectrum ratio combination information. Φ2 represents the second energy range energy spectrum ratio combination value in the energy range energy spectrum ratio combination value set included in the energy range energy spectrum ratio combination information. Φ n It represents the nth energy range energy spectrum ratio combination value in the energy range energy spectrum ratio combination value set included in the energy range energy spectrum ratio combination information.

[0068] In the second step, the determined radiation current combination values ​​are determined as a radiation current combination value set.

[0069] The third step is to fuse the energy range energy spectrum ratio combination information and the radiation current combination value set to obtain the radiation current combination information. The fusing of the energy range energy spectrum ratio combination information and the radiation current combination value set to obtain the radiation current combination information may include: determining the energy range energy spectrum ratio combination information and the radiation current combination value set as the energy range energy spectrum ratio combination information and the radiation current combination value set included in the radiation current combination information.

[0070] Step 105 , screening the radiation current combination information set to obtain a radiation current screening information set.

[0071] In some embodiments, the execution entity may perform screening processing on the radiation current combination information set to obtain a radiation current screening information set.

[0072] In some optional implementations of some embodiments, the execution entity determines, based on the detector response coefficient set, the radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information, which may include the following steps:

[0073] In the first step, for each radiation current combination information in the above radiation current combination information set, the sum of the radiation energy range energy spectrum proportion values ​​of each radiation energy range in the radiation energy range energy spectrum proportion value set included in the above radiation current combination information is determined as the total radiation energy range energy spectrum proportion value.

[0074] In the second step, for each determined total energy spectrum proportion value of the radiation energy zone, in response to determining that the total energy spectrum proportion value of the radiation energy zone is not equal to the preset proportion value, the radiation current combination information corresponding to the above total energy spectrum proportion value of the radiation energy zone is deleted from the radiation current combination information set.

[0075] As an example, the preset ratio value may be 100%.

[0076] In the third step, the deleted radiation current combination information set is determined as the radiation current screening information set.

[0077] Step 106 : For each radiation current screening information in the radiation current screening information set, determine the root mean square value of the radiation current combination value set and the radiation current measurement value set included in the radiation current screening information as the radiation current root mean square value.

[0078] In some embodiments, the execution entity may determine, for each piece of radiation current screening information in the radiation current screening information set, a root mean square value of the radiation current combination value set included in the radiation current screening information and the radiation current measurement value set as the radiation current root mean square value. The root mean square value of the radiation current combination value set included in the radiation current screening information and the radiation current measurement value set may be determined by the following formula:

[0079]

[0080] Wherein, RMS represents the root mean square value. 1计算 Indicates the first radiation current combination value in the above radiation current combination value set. I 1实测 Represents the first radiation current measurement value in the above radiation current measurement value set. I 2计算 Indicates the second radiation current combination value in the above radiation current combination value set. 2实测 I represents the second radiation current measurement value in the above radiation current measurement value set. s represents the number of radiation current measurement values ​​in the above radiation current measurement value set. s计算 I represents the sth radiation current combination value in the above radiation current combination value set. s实测 represents the sth radiation current measurement value in the above radiation current measurement value set.

[0081] Step 107 : determining the energy spectrum ratio combination information of the energy range corresponding to the minimum radiation current RMS value among the determined radiation current RMS values ​​as the neutron radiation field energy spectrum information corresponding to the neutron radiation field to be measured.

[0082] In some embodiments, the execution entity may determine the energy range spectrum ratio combination information corresponding to the smallest radiation current RMS value among the determined radiation current RMS values ​​as the neutron radiation field spectrum information corresponding to the neutron radiation field to be measured.

[0083] The above-described embodiments of the present application have the following beneficial effects: Through the spectrum decomposition methods applicable to self-powered neutron spectrum detection assemblies in some embodiments of the present application, the spectrum decomposition work for core neutron spectrum detection can be accurately completed under conditions that are more consistent with physical reality. Specifically, the difficulty in accurately completing the spectrum decomposition work for core neutron spectrum detection under conditions that are more consistent with physical reality is that the spectrum decomposition work for core neutron spectrum detection is difficult to accurately complete under conditions that are more consistent with physical reality. Existing spectrum decomposition methods are not suitable for self-powered neutron detector spectrum measurement systems that use multiple self-powered neutron detectors to analyze and operate on the current signals output by the detectors to achieve the energy spectrum to be measured. Based on this, the spectrum decomposition methods applicable to self-powered neutron spectrum detection assemblies in some embodiments of the present application first place the spectrum measurement assembly into the neutron radiation field to be measured, and obtain corresponding radiation current measurement values ​​from each self-powered neutron detector included in the spectrum measurement assembly to obtain a set of radiation current measurement values. Secondly, data acquisition and processing are performed on the spectrum measurement assembly to obtain a set of information about the neutron radiation energy range to be measured and a set of detector response coefficients. In this way, the data required for neutron spectrum decomposition can be collected. Then, based on the aforementioned neutron radiation energy region information set to be measured, an energy region energy spectrum ratio combination information set is determined. Then, based on the aforementioned detector response coefficient set, the radiation current combination information corresponding to each energy region energy spectrum ratio combination information in the aforementioned energy region energy spectrum ratio combination information is determined to obtain a radiation current combination information set. Thus, through energy region division and scanning calculation, assumed current values ​​for various assumed energy spectrum partitioning scenarios can be obtained. Next, the aforementioned radiation current combination information set is filtered to obtain a radiation current screening information set. Subsequently, for each radiation current screening information in the aforementioned radiation current screening information set, the root mean square value of the radiation current combination value set included in the aforementioned radiation current screening information and the aforementioned radiation current measurement value set is determined as the radiation current root mean square value. Finally, the energy region energy spectrum ratio combination information corresponding to the smallest radiation current root mean square value among the determined radiation current root mean square values ​​is determined as the neutron radiation field energy spectrum information corresponding to the neutron radiation field to be measured. Thus, one energy spectrum partitioning scenario can be selected from the various assumed energy spectrum partitioning scenarios as the neutron radiation field energy spectrum information. Therefore, some of the spectrum decomposition methods applicable to self-powered neutron energy spectrum detection components of this application can use physical formulas to strictly follow the physical laws to perform calculations in each step, which has a theoretical basis and is more in line with physical reality. The calculation of the entire energy range can also be achieved through full energy spectrum scanning, and the data is complete as a whole. The accuracy of each scan can be determined by setting the scanning step size, and the user can determine the size of the step size value according to the actual situation, and the final solution is more accurate. In addition, a method for eliminating pathological data is added, and the basis for determining data elimination when the total proportion of each energy zone is not the preset value (100%) is given.Therefore, through the spectrum decomposition method applicable to the self-powered neutron energy spectrum detection component, the current signal output by the detector is analyzed and operated to achieve the solution of the energy spectrum to be measured, and the neutron energy spectrum decomposition can be accurately completed under conditions that are more in line with physical reality.

[0084] This application also provides a computer device 200. Figure 2 As shown, computer device 200 includes: bus 201, processor 202, memory 203, and communication interface 204. Processor 202, memory 203, and communication interface 204 communicate with each other via bus 201. Computer device 200 can be a server or a terminal device. It should be understood that this application does not limit the number of processors and memories in computer device 200.

[0085] The bus 201 may be a peripheral component interconnect (PCI) bus or an extended industry standard architecture (EISA) bus. The bus may be divided into an address bus, a data bus, a control bus, etc. For ease of representation, Figure 2 The bus 201 may include a path for transmitting information between various components of the computer device 200 (eg, the memory 203, the processor 202, and the communication interface 204).

[0086] The processor 202 may include any one or more processors such as a central processing unit (CPU), a graphics processing unit (GPU), a microprocessor (MP), or a digital signal processor (DSP).

[0087] The memory 203 may include a volatile memory, such as a random access memory (RAM). The memory 203 may also include a non-volatile memory, such as a read-only memory (ROM), a flash memory, a hard disk drive (HDD), or a solid state drive (SSD).

[0088] Memory 203 stores executable program code, which processor 202 executes to implement the functions of the aforementioned acquisition module, sampling module, determination module, and mixing module, thereby implementing the aforementioned spectrum interpretation method applicable to a self-powered neutron spectrum detection component. Specifically, memory 203 stores instructions for executing the aforementioned spectrum interpretation method applicable to a self-powered neutron spectrum detection component.

[0089] The communication interface 204 uses a transceiver module such as, but not limited to, a network interface card or a transceiver to implement communication between the computer device 200 and other devices or a communication network.

[0090] An embodiment of the present application further provides a chip, which includes a processor and a data interface. The processor reads instructions stored in a memory through the data interface to execute the above-mentioned spectrum decomposition method applicable to the self-powered neutron energy spectrum detection component.

[0091] Embodiments of the present application also provide a computer-readable storage medium. The computer-readable storage medium can be any available medium capable of being stored by a computing device, or a data storage device such as a data center that contains one or more available media. The available medium can be a magnetic medium (e.g., a floppy disk, a hard disk, a magnetic tape), an optical medium (e.g., a DVD), or a semiconductor medium (e.g., a solid-state drive). The computer-readable storage medium includes instructions that instruct the computing device to execute the above-described spectrum decomposition method applicable to a self-powered neutron spectrum detection assembly.

[0092] The technical features of the above embodiments can be combined arbitrarily. In order to make the description concise, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0093] The above embodiments are only used to illustrate the technical solutions of the present application, rather than to limit them. Although the present application has been described in detail with reference to the aforementioned embodiments, those skilled in the art should understand that they can still modify the technical solutions described in the aforementioned embodiments, or make equivalent replacements for some of the technical features therein. However, these modifications or replacements do not deviate the essence of the corresponding technical solutions from the protection scope of the technical solutions of the embodiments of the present application.

Claims

1. A spectrum interpretation method applicable to a self-powered neutron spectrum detection component, comprising: placing an energy spectrum measurement assembly into a neutron radiation field to be measured, and acquiring corresponding radiation current measurement values ​​from each self-powered neutron detector included in the energy spectrum measurement assembly to obtain a radiation current measurement value set, wherein the energy spectrum measurement assembly is composed of at least one self-powered neutron detector; Performing data acquisition and processing on the energy spectrum measurement component to obtain a set of information on the neutron radiation energy range to be measured and a set of detector response coefficients; Based on the neutron radiation energy range information set to be measured, determining an energy range energy spectrum ratio combination information set; Based on the detector response coefficient set, determining radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information, to obtain a radiation current combination information set, wherein the radiation current combination information in the radiation current combination information set includes: a radiation current combination value set; screening the radiation current combination information set to obtain a radiation current screening information set; For each piece of radiation current screening information in the radiation current screening information set, determining a root mean square value of a radiation current combination value set included in the radiation current screening information and the radiation current measurement value set as a radiation current root mean square value; The energy spectrum ratio combination information of the energy region corresponding to the smallest radiation current root mean square value among the determined radiation current root mean square values ​​is determined as the neutron radiation field energy spectrum information corresponding to the neutron radiation field to be measured.

2. The spectrum interpretation method applicable to the self-powered neutron spectrum detection component according to claim 1, wherein: The data acquisition and processing of the energy spectrum measurement component to obtain a set of information on the neutron radiation energy range to be measured and a set of detector response coefficients includes: Acquiring information of a neutron radiation field region to be measured corresponding to the neutron radiation field to be measured; Determining the number of neutron energy regions to be measured based on the number of self-powered neutron detectors included in the energy spectrum measurement component; Based on the number of divisions of the neutron energy region to be measured, the information of the neutron radiation field to be measured is divided and processed to obtain an information set of the neutron radiation energy region to be measured; For each self-powered neutron detector included in the energy spectrum measurement assembly, performing simulation processing on the self-powered neutron detector to generate a detector response coefficient to obtain a detector response coefficient group, wherein the detector response coefficient groups in the detector response coefficient group correspond one-to-one to the neutron radiation energy range information to be measured in the neutron radiation energy range information set to be measured; The generated detector response coefficient groups are determined as a detector response coefficient group set.

3. The spectrum interpretation method applicable to the self-powered neutron spectrum detection component according to claim 1, wherein: The determining of the energy range energy spectrum ratio combination information set based on the neutron radiation energy range information set to be measured includes: generating an energy range spectrum ratio value group corresponding to each piece of neutron radiation energy range information to be measured in the neutron radiation energy range information set to obtain an energy range spectrum ratio value group set; The energy range energy spectrum proportion values ​​in the energy range energy spectrum proportion value group set are permuted and combined to generate energy range energy spectrum proportion combination information, thereby obtaining an energy range energy spectrum proportion combination information set.

4. The spectrum interpretation method applicable to the self-powered neutron spectrum detection component according to claim 3, wherein: The generating of the energy range energy spectrum ratio value group corresponding to each piece of neutron radiation energy range information to be measured in the neutron radiation energy range information set to be measured comprises: Determine the first preset value as the upper limit of the neutron energy spectrum ratio; Determine the second preset value as the lower limit value of the neutron energy spectrum ratio; Determine the third preset value as the proportion update step value; Based on the lower limit of the neutron spectrum ratio and the ratio update step value, perform the following update steps: The lower limit value of the neutron energy spectrum ratio is determined as the energy spectrum ratio value of the energy region; The sum of the neutron energy spectrum ratio lower limit value and the ratio update step value is determined as the updated neutron energy spectrum ratio lower limit value; In response to determining that the neutron energy spectrum ratio upper limit value and the updated neutron energy spectrum ratio lower limit value are not equal, determining the updated neutron energy spectrum ratio lower limit value as the neutron energy spectrum ratio lower limit value for performing the updating step again; The generated energy spectrum ratio values ​​of each energy range are determined as an energy spectrum ratio value group.

5. The spectrum interpretation method applicable to the self-powered neutron spectrum detection component according to claim 1, wherein: The determining, based on the detector response coefficient set, radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information includes: For each detector response coefficient group in the detector response coefficient group set, generating a radiation current combination value based on the energy range and energy spectrum proportion combination information; Determining the determined radiation current combination values ​​as a radiation current combination value set; The energy range energy spectrum proportion combination information and the radiation current combination value set are fused to obtain the radiation current combination information.

6. The spectrum interpretation method applicable to the self-powered neutron spectrum detection component according to claim 1, wherein: The radiation current combination information in the radiation current combination information set includes: energy range energy spectrum ratio combination information, and the energy range energy spectrum ratio combination information includes: a radiation energy range energy spectrum ratio value set; and the radiation current combination information set is filtered to obtain a radiation current filtering information set, including: For each piece of radiation current combination information in the radiation current combination information set, the sum of the radiation energy range energy spectrum proportion values ​​of each radiation energy range in the radiation energy range energy spectrum proportion value set included in the radiation current combination information is determined as the total radiation energy range energy spectrum proportion value; For each determined total energy spectrum ratio of the radiation energy zone, in response to determining that the total energy spectrum ratio of the radiation energy zone is not equal to the preset ratio, deleting the radiation current combination information corresponding to the total energy spectrum ratio of the radiation energy zone from the radiation current combination information set; The deleted radiation current combination information set is determined as the radiation current screening information set.

7. A computer device, wherein: The computer device comprises a processor, a memory, and a computer program stored in the memory and executable by the processor, wherein when the computer program is executed by the processor, the steps of the method according to any one of claims 1 to 6 are implemented.

8. A computer-readable storage medium, wherein: The computer-readable storage medium stores a computer program, wherein when the computer program is executed by a processor, the steps of the method according to any one of claims 1 to 6 are implemented.

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