Spectrum unfolding method suitable for self-powered neutron spectrum detection assembly and computer equipment

Abstract

The embodiment of the invention relates to the field of neutron spectrum detection research, in particular to a spectrum unfolding method suitable for a self-powered neutron spectrum detection assembly and computer equipment. A specific implementation mode of the method comprises the following steps: putting an energy spectrum measurement assembly into a neutron radiation field to be measured, and obtaining a corresponding radiation current measurement value; carrying out data acquisition processing on the energy spectrum measurement assembly; determining an energy region energy spectrum proportion combination information set; radiation current combination information is determined; performing screening processing on the radiation current combination information set; determining a radiation current root-mean-square value; and determining neutron radiation field energy spectrum information corresponding to the to-be-detected neutron radiation field. The implementation mode can be matched with a self-powered neutron energy spectrum detection assembly to achieve neutron energy spectrum detection, analysis operation is carried out on the current signal output by the detector, solving of the energy spectrum to be detected is achieved, and neutron energy spectrum unfolding can be accurately completed under the condition better conforming to physical reality.

Description

Technical Field

[0001] The embodiments of the present application relate to the research field of neutron spectrum detection, and in particular to a spectrum analysis method and a computer device suitable for a self-powered neutron spectrum detection component. Background Art

[0002] Neutron spectrum has always been an important parameter in reactor design and physical analysis. There are many methods to measure neutron spectrum. For neutron spectrum measurement outside the reactor, a multi-sphere spectrometer can be used for detection; for core neutron spectrum measurement, multiple activated foils with known cross-sections can be used and placed in the neutron field to be measured for irradiation. Considering the complex conditions of high temperature and high pressure in the core and the small space of the fuel assembly, the multi-sphere spectrometer system is too large to realize core neutron detection, and the activated foil cannot realize online measurement.

[0003] Therefore, the energy spectrum measurement system composed of self-powered neutron detectors is of great significance for the measurement of core neutron energy spectrum. The commonly used device includes multiple self-powered neutron detectors, which analyze and operate the current signals output by the detectors to solve the energy spectrum to be measured. The existing spectrum analysis methods are not suitable for the self-powered neutron detector spectrum measurement system. It is particularly important to design a spectrum analysis method suitable for the self-powered neutron spectrum detection component.

[0004] The self-powered neutron spectrum detection assembly is to place multiple self-powered detectors into the core neutron field. Neutrons interact with the emitter of the probe to generate radioactive nuclides. The radioactive nuclides decay. The remaining positive charge of the decayed emitter material forms a positive potential between the emitter and the collector, generating a current signal. The electronic system can obtain neutron injection data by analyzing the current signal. After a self-powered neutron detector reaches a stable working condition, the current output by the corresponding electronic system satisfies the following current equation:

[0005]

[0006] Among them, I is the current value output by the detector. R(E) is the response coefficient of the detector when the neutron energy is E. φ(E) is the neutron injection rate at the point with energy E. The above current equation belongs to 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 obtained. However, for the actual solution, the continuous integral equation needs to be discretized, corresponding to the partition in the energy spectrum:

[0007]

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

[0009]

[0010] Wherein, m represents the serial number of the detector.

[0011] For the multiple currents I output by the self-powered neutron spectrum detection component m It can be measured in the actual environment, Φ n It represents 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 by using the currents of multiple detectors and the response coefficients of multiple detectors.

[0012] However, in actual engineering applications, there are many methods for the 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 introduce concepts in a brief form, which will be described in detail in the detailed implementation section below. The content of this application is not intended to identify the key features or essential features of the technical solution claimed for protection, nor is it intended to limit the scope of the technical solution claimed for protection.

[0014] Some embodiments of the present application propose a spectrum analysis 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 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 proportion combination information set; based on the above-mentioned detector response coefficient group set, determining each energy zone in the above-mentioned energy zone energy spectrum proportion combination information The radiation current combination information corresponding to the energy spectrum proportion combination information is obtained 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-mentioned embodiments of the present application have the following beneficial effects: through the spectrum decomposition method applicable to the self-powered neutron spectrum detection component of some embodiments of the present application, the spectrum decomposition work of the core neutron spectrum detection can be accurately completed under conditions that are more in line with physical reality. Specifically, the reason why it is difficult to accurately complete the spectrum decomposition work of the core neutron spectrum detection under conditions that are more in line with physical reality is that: using multiple self-powered neutron detectors, the current signal output by the detector is analyzed and operated to achieve the solution of the energy spectrum to be measured, and the existing multiple spectrum decomposition methods are not applicable to the self-powered neutron detector spectrum measurement system. Based on this, the spectrum decomposition method applicable to the self-powered neutron spectrum detection component of some embodiments of the present application, first, put 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 to obtain the radiation current measurement value set. Secondly, the above-mentioned spectrum measurement component is subjected to data acquisition processing to obtain the neutron radiation energy zone information set to be measured and the detector response coefficient group set. In this way, the data required for the neutron spectrum decomposition can be collected. Then, based on the above-mentioned neutron radiation energy zone information set to be measured, an energy zone energy spectrum ratio combination information set is determined. Then, based on the above-mentioned detector response coefficient set, the radiation current combination information corresponding to each energy zone energy spectrum ratio combination information in the above-mentioned energy zone energy spectrum ratio combination information is determined to obtain a radiation current combination information set. Thus, the assumed current values ​​under various assumed energy spectrum partitioning conditions can be obtained by means of energy zone division and scanning calculation. Next, the above-mentioned radiation current combination information set is screened to obtain a radiation current screening information set. Subsequently, 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. Finally, the energy zone 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 above-mentioned neutron radiation field to be measured. Thus, an energy spectrum partitioning condition can be selected from each assumed energy spectrum partitioning condition as the neutron radiation field energy spectrum information. Therefore, some spectrum decomposition methods applicable to self-powered neutron spectrum detection components of the present application can use physical formulas to strictly follow the physical laws to calculate each step, have a theoretical basis, and are more in line with physical reality. The calculation of the entire energy zone can also be realized 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 length, and the user can determine the size of the step length 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 judging the elimination of data when the sum of the proportions of each energy zone is not the preset value (100%) is given.Therefore, through the spectrum analysis method suitable for 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 analysis 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 embodiments of the present application will become more apparent with reference to the following detailed description in conjunction with the accompanying drawings. Throughout the accompanying drawings, the same or similar reference numerals represent the same or similar elements. It should be understood that the drawings are schematic and that components and elements 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 component 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] Embodiments of the present application will be described in more detail below 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 set forth 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 only for exemplary purposes 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 the present application can be combined with each other.

[0024] It should be noted that the concepts such as "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 "plurality" mentioned in the present application are illustrative rather than restrictive, and those skilled in the art should understand that unless otherwise clearly indicated in the context, it 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 The flowchart 100 of some embodiments of the spectrum analysis method applicable to the self-powered neutron spectrum detection component according to the present application is shown. The spectrum analysis method applicable to the self-powered neutron spectrum detection component includes the following steps:

[0029] Step 101 : 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.

[0030] In some embodiments, the execution subject of the spectrum interpretation method applicable to the 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. Among them, 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 electronics 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 preset detector value may 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 subject may perform 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.

[0035] In some optional implementations of some embodiments, the execution subject performs 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, which may include the following steps:

[0036] The first step is to obtain the neutron radiation field area information corresponding to the neutron radiation field to be measured. The neutron radiation field area information 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 neutron radiation field area information. The neutron radiation field area information can characterize the radiation area of ​​the neutron radiation field to be measured.

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

[0038] For example, the number of self-powered neutron detectors included in the energy spectrum measurement component can be determined as the number of neutron energy region divisions to be measured. A preset division number value can also 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 and process the above-mentioned regional information of the neutron radiation field to be measured based on the number of divisions of the above-mentioned neutron energy zones to be measured, and obtain a set of information on the neutron radiation energy zones to be measured. Wherein, the above-mentioned regional information of the neutron radiation field to be measured is divided and processed based on the number of divisions of the above-mentioned neutron energy zones to be measured, and obtain a set of information on the neutron radiation energy zones to be measured. It can be: first, the neutron radiation field to be measured corresponding to the above-mentioned regional information of the neutron radiation field to be measured is evenly divided into the number of neutron radiation energy zones to be measured that are divided into the above-mentioned neutron energy zones to be measured, and the regional information corresponding to each of the divided neutron radiation energy zones to be measured is determined as the neutron radiation energy zone information to be measured. Then, the determined information on each neutron radiation energy zone to be measured is determined as a set of information on the neutron radiation energy zones to be measured. Here, the regional information corresponding to the above-mentioned neutron radiation energy zone to be measured can represent the radiation area of ​​the above-mentioned neutron radiation energy zone to be measured.

[0041] In the fourth step, for each self-powered neutron detector included in the energy spectrum measurement component, the self-powered neutron detector is simulated to generate a detector response coefficient to obtain a detector response coefficient group. The detector response coefficient group in the detector response coefficient group corresponds to the neutron radiation energy zone information to be measured in the neutron radiation energy zone information set to be measured. Specifically, the self-powered neutron detector can be simulated to generate a detector response coefficient by a simulation algorithm.

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

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

[0044] Step 103, based on the energy range information set of the neutron radiation to be measured, determine the energy range energy spectrum ratio combination information set.

[0045] In some embodiments, the execution subject may determine an energy range and spectrum ratio combination information set based on the energy range information set of the neutron radiation 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 energy range information set of the neutron radiation to be measured, which may include the following steps:

[0047] The first step is to generate an energy range energy 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 energy spectrum ratio value group set.

[0048] The second step is to perform permutation and combination processing on each energy zone energy spectrum ratio value in the above energy zone energy spectrum ratio value group set to generate energy zone energy spectrum ratio combination information, and obtain an energy zone energy spectrum ratio combination information set. Among them, the energy zone energy spectrum ratio values ​​in the above energy zone energy spectrum ratio value group set can be permuted and combined by a preset permutation and combination algorithm to generate energy zone energy spectrum ratio combination information, and obtain an energy zone energy spectrum ratio combination information set. The above energy zone energy spectrum ratio combination information may include: an energy zone energy spectrum ratio combination value set. The energy zone energy spectrum ratio combination values ​​in the above energy zone energy spectrum ratio combination value set correspond one-to-one to the energy zone energy spectrum ratio value groups in the above energy zone 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 loop 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 subject generates an energy range energy spectrum ratio value group corresponding to each neutron radiation energy range information to be measured in the neutron radiation energy range information set to be measured, which 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] The third step is to determine the third preset value 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] The fourth step is to update the step value based on the lower limit value of the neutron energy spectrum ratio and the ratio, and perform the following update sub-steps:

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

[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 range are determined as an energy spectrum proportion value group of the energy range.

[0062] Step 104 , based on the detector response coefficient set, determine the radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information, and obtain the radiation current combination information set.

[0063] In some embodiments, the execution subject may determine the radiation current combination information corresponding to each energy range energy spectrum ratio combination information in the energy range energy spectrum ratio combination information based on the detector response coefficient set 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 subject determines the radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information based on the detector response coefficient set, 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 region energy spectrum proportion 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 energy region energy spectrum ratio combination information. m represents the mth radiation current combination value in the radiation current combination value set. R represents the detector response coefficient. m1 Represents 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 indicates the energy range energy spectrum ratio combination value. Φ1 indicates 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 indicates 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 proportion combination value in the energy range energy spectrum proportion combination value set included in the energy range energy spectrum proportion 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 above energy range energy spectrum ratio combination information and the above radiation current combination value set to obtain the above radiation current combination information. The above fusion processing of the above energy range energy spectrum ratio combination information and the above radiation current combination value set to obtain the above radiation current combination information can be: determining the above energy range energy spectrum ratio combination information and the above radiation current combination value set as the energy range energy spectrum ratio combination information and the radiation current combination value set included in the above 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 subject determines the radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information based on the detector response coefficient set, 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 zone energy spectrum proportion values ​​in the radiation energy zone energy spectrum proportion value set included in the above radiation current combination information is determined as the total radiation energy zone 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 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 proportion value may be 100%.

[0076] In the third step, the deleted radiation current combination information set is determined as the above-mentioned 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 included in the radiation current screening information and the radiation current measurement value set as the radiation current root mean square value.

[0078] In some embodiments, the execution subject may determine, for each radiation current screening information in the radiation current screening information set, 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 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 Represents 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 I represents 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 range energy spectrum ratio combination information corresponding to the smallest 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 energy spectrum ratio combination information corresponding to the smallest radiation current root mean square value among the determined radiation current root mean square values ​​as the neutron radiation field energy spectrum information corresponding to the neutron radiation field to be measured.

[0083] The above-mentioned embodiments of the present application have the following beneficial effects: through the spectrum decomposition method applicable to the self-powered neutron spectrum detection component of some embodiments of the present application, the spectrum decomposition work of the core neutron spectrum detection can be accurately completed under conditions that are more in line with physical reality. Specifically, the reason why it is difficult to accurately complete the spectrum decomposition work of the core neutron spectrum detection under conditions that are more in line with physical reality is that: using multiple self-powered neutron detectors, the current signal output by the detector is analyzed and operated to achieve the solution of the energy spectrum to be measured, and the existing multiple spectrum decomposition methods are not applicable to the self-powered neutron detector spectrum measurement system. Based on this, the spectrum decomposition method applicable to the self-powered neutron spectrum detection component of some embodiments of the present application, first, put 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 to obtain the radiation current measurement value set. Secondly, the above-mentioned spectrum measurement component is subjected to data acquisition processing to obtain the neutron radiation energy zone information set to be measured and the detector response coefficient group set. In this way, the data required for the neutron spectrum decomposition can be collected. Then, based on the above-mentioned neutron radiation energy zone information set to be measured, an energy zone energy spectrum ratio combination information set is determined. Then, based on the above-mentioned detector response coefficient set, the radiation current combination information corresponding to each energy zone energy spectrum ratio combination information in the above-mentioned energy zone energy spectrum ratio combination information is determined to obtain a radiation current combination information set. Thus, the assumed current values ​​under various assumed energy spectrum partitioning conditions can be obtained by means of energy zone division and scanning calculation. Next, the above-mentioned radiation current combination information set is screened to obtain a radiation current screening information set. Subsequently, 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. Finally, the energy zone 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 above-mentioned neutron radiation field to be measured. Thus, an energy spectrum partitioning condition can be selected from each assumed energy spectrum partitioning condition as the neutron radiation field energy spectrum information. Therefore, some spectrum decomposition methods applicable to self-powered neutron spectrum detection components of the present application can use physical formulas to strictly follow the physical laws to calculate each step, have a theoretical basis, and are more in line with physical reality. The calculation of the entire energy zone can also be realized 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 length, and the user can determine the size of the step length 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 judging the elimination of data when the sum of the proportions of each energy zone is not the preset value (100%) is given.Therefore, through the spectrum analysis method suitable for 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 analysis can be accurately completed under conditions that are more in line with physical reality.

[0084] The present application also provides a computer device 200. Figure 2 As shown, the computer device 200 includes: a bus 201, a processor 202, a memory 203 and a communication interface 204. The processor 202, the memory 203 and the communication interface 204 communicate with each other through the bus 201. The computer device 200 can be a server or a terminal device. It should be understood that the present application does not limit the number of processors and memories in the 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 is represented by only one line, but it does not mean that there is only one bus or one type of bus. The bus 201 may include a path for transmitting information between various components of the computer device 200 (for example, the memory 203, the processor 202, and the communication interface 204).

[0086] The processor 202 may include any one or more of 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] The memory 203 stores executable program codes, and the processor 202 executes the executable program codes to respectively implement the functions of the aforementioned acquisition module, sampling module, determination module, and mixing module, thereby implementing the above-mentioned spectrum decomposition method applicable to the self-powered neutron energy spectrum detection component. That is, the memory 203 stores instructions for executing the above-mentioned spectrum decomposition method applicable to the self-powered neutron energy 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 also 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] The embodiment of the present application also provides a computer-readable storage medium. The above-mentioned computer-readable storage medium can be any available medium that can be stored by a computing device or a data storage device such as a data center containing one or more available media. The above-mentioned available medium can be a magnetic medium (for example, a floppy disk, a hard disk, a tape), an optical medium (for example, a DVD), or a semiconductor medium (for example, a solid-state hard disk), etc. The computer-readable storage medium includes instructions, and the above-mentioned instructions instruct the computing device to execute the above-mentioned spectrum analysis method applicable to the self-powered neutron energy spectrum detection component.

[0092] The technical features of the above embodiments can be combined arbitrarily. 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, a person skilled in the art should understand that the technical solutions described in the aforementioned embodiments may still be modified, or some of the technical features may be replaced by equivalents. 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 analysis method applicable to a self-powered neutron spectrum detection component, 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 energy spectrum measurement component is composed of at least one self-powered neutron detector; 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; 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 group 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 is determined 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 radiation current screening information in the radiation current screening information set, determining a radiation current 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; The energy range 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.

2. The spectrum analysis 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 of the neutron radiation energy region to be measured and a set of detector response coefficients includes: Acquiring the neutron radiation field area information to be measured corresponding to the neutron radiation field to be measured; Determining the number of neutron energy zone divisions 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 zone to be measured, the neutron radiation field area information to be measured is divided and processed to obtain an information set of the neutron radiation energy zone to be measured; For each self-powered neutron detector included in the energy spectrum measurement component, a simulation process is performed 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 zone information to be measured in the neutron radiation energy zone information set to be measured; The generated detector response coefficient groups are determined as a detector response coefficient group set.

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

5. The spectrum analysis method applicable to the self-powered neutron spectrum detection component according to claim 1, wherein: The step of determining the radiation current combination information corresponding to each energy range energy spectrum proportion combination information in the energy range energy spectrum proportion combination information based on the detector response coefficient set includes: For each detector response coefficient group in the detector response coefficient group set, generating a radiation current combination value based on the energy region 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 analysis 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 proportion combination information, the energy range energy spectrum proportion combination information includes: radiation energy range energy spectrum proportion value set; and the radiation current combination information set is screened to obtain a radiation current screening information set, including: For each radiation current combination information in the radiation current combination information set, the sum of the radiation energy zone energy spectrum proportion values ​​of each radiation energy zone in the radiation energy zone energy spectrum proportion value set included in the radiation current combination information is determined as the total radiation energy zone 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, the radiation current combination information corresponding to the total energy spectrum ratio of the radiation energy zone is deleted 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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