Method, device, medium and equipment for verifying accuracy of in-situ gamma spectrometer detection efficiency of nuclear power plant

Abstract

The present application relates to a nuclear power plant in-situ gamma spectrometer detection efficiency accuracy verification method, device, medium and equipment, comprising: obtaining the basic geometric parameters and physical parameters of the detector; determining the detection efficiency accuracy verification item; measuring according to the verification item using the standard point source, obtaining the corresponding test measurement efficiency; according to the radiation source information of the standard point source and the detector model, calculating the theoretical detection efficiency under each verification item; according to the test measurement efficiency and the theoretical detection efficiency, the accuracy of the sourceless efficiency calibration is evaluated. The verification item designed by the present application can comprehensively evaluate the accuracy of the sourceless efficiency calibration of the nuclear power plant system deposition source item investigation spectrometer, the verification process is standardized and standardized, and the verification results of different laboratories are comparable. At the same time, the present application uses standard point source for actual field simulation verification, which not only solves the problem that the current industry cannot evaluate the measurement accuracy, but also ensures the comprehensiveness and reliability of the verification.

Description

Technical Field

[0001] This invention relates to the technical field of nuclear radiation monitoring, and more specifically, to a method, apparatus, medium, and equipment for verifying the detection efficiency and accuracy of an on-site gamma spectrometer at a nuclear power plant. Background Technology

[0002] In-situ (referring to measurements conducted in non-laboratory environments, such as within nuclear power plant buildings or on equipment) gamma spectrometers, as core analytical instruments for nuclear radiation monitoring, play an irreplaceable role in fields such as nuclear power plant radiation monitoring and radioactive waste management. In gamma spectral analysis, the accuracy of detection efficiency is crucial for obtaining reliable measurement results. Detection efficiency is defined as the ratio of the gamma ray count recorded by the detector to the number of gamma rays emitted by the radiation source. Its value is closely related to various factors such as detector type, gamma ray energy, geometry of the object being measured, medium composition, and source-detector distance. Therefore, establishing an accurate and efficient detection efficiency calibration method is fundamental to ensuring the accuracy of nuclear power plant radiation monitoring data, especially in complex and variable measurement environments.

[0003] Traditional efficiency calibration mainly relies on active efficiency calibration, which uses a standard radioactive source with known activity (such as...). 137 Cs、 60 Co、 152 Eu et al. conducted experimental measurements and fitted efficiency curves. Although this method has high accuracy, it has obvious limitations in practical applications: the cost of purchasing and disposing of standard sources of various energy sources is high; standard sources are limited by their half-life and need to be replaced regularly; in particular, the sediment source term investigation objects of the main systems of nuclear power plants are non-standard geometries and require on-site measurement, making it difficult to match completely consistent standard sources.

[0004] Passive efficiency calibration technology is a novel efficiency calibration method developed in recent years. Its core idea is to calculate detection efficiency using Monte Carlo simulation or numerical integration methods without the need for actual measurement using a radioactive standard source. This method, by establishing a precise physical model of the detector and combining it with the theory of gamma-ray-matter interaction, enables the calculation of detection efficiency under different energies and geometric conditions without the need for a physical standard source. However, verifying the accuracy of passive efficiency calibration technology faces several challenges. Current verification methods mainly fall into two categories: one is verification using standard sources, but the types of standard sources are limited, making it difficult to cover the diverse geometric conditions in practical applications; the other is single-point verification using point sources, resulting in sparse verification points and difficulty in comprehensively evaluating the model's accuracy at different spatial locations and energies. These problems make it difficult to fully verify the reliability of passive efficiency calibration results, limiting its application depth in high-precision applications. Summary of the Invention

[0005] The technical problem to be solved by the present invention is to provide a method, apparatus, medium and equipment for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant, addressing the problems existing in the prior art.

[0006] The technical solution adopted by this invention to solve its technical problem is: constructing a method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant, comprising: Step S10: Obtain the basic geometric and physical parameters of the detector; Step S20: Determine the verification items for detection efficiency and accuracy based on the basic geometric parameters, physical parameters, and uncertainty sources of the detector; Step S30: Use a standard point source to perform measurements according to the verification items to obtain the corresponding test measurement efficiency; Step S40: Calculate the theoretical detection efficiency for each verification item based on the radiation source information and detector model of the standard point source. Step S50: Evaluate the accuracy of the passive efficiency calibration based on the experimental measurement efficiency and the theoretical detection efficiency.

[0007] In the method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant as described in this invention, the verification items include: axial distance verification, lateral offset verification, and composite geometric condition verification. The axial distance verification is used to evaluate the accuracy of the detector model when the distance between the standard point source and the detector varies; The lateral offset verification is used to evaluate the accuracy of the change in the lateral position of the detector model relative to the standard point source; The composite geometry condition verification is used to evaluate the overall accuracy of the detector model under complex geometric conditions.

[0008] In the method for verifying the accuracy of on-site gamma spectrometer detection efficiency in nuclear power plants according to the present invention, the experimental measurement efficiency is calculated by the following formula: ; In the formula, For the sake of experimental measurement efficiency, Count the γ-ray total energy peaks of this nuclide. This is the standard point source activity value after half-life correction. For the live time measured in the experiment, This represents the branching ratio corresponding to the energy emitted by a certain nuclide.

[0009] In the method for verifying the accuracy of on-site gamma spectrometer detection efficiency in nuclear power plants described in this invention, the theoretical detection efficiency is calculated using the following formula: ; In the formula, For theoretical detection efficiency, The set number of emitted gamma particles, This represents the number of γ particles received at the corresponding energy level.

[0010] In the method for verifying the accuracy of on-site gamma spectrometer detection efficiency in nuclear power plants according to the present invention, step S50, which evaluates the accuracy of passive efficiency calibration based on the experimentally measured efficiency and the theoretical detection efficiency, includes: For each verification item, the relative deviation at each verification point is calculated; the relative deviation is the relative deviation between the experimental measurement efficiency and the theoretical detection efficiency. The accuracy of the passive efficiency calibration is evaluated based on the relative deviation of each verification point.

[0011] In the method for verifying the accuracy of on-site gamma spectrometer detection efficiency in nuclear power plants according to the present invention, the step of evaluating the accuracy of passive efficiency calibration based on the relative deviation of each verification point includes: For axial distance verification and lateral offset verification, the relative deviation of each verification point is less than the first set value; for complex geometric condition verification, the relative deviation of each verification point is less than the second set value, and the sign of the relative deviation within the same item is irregular. If all the above conditions are met, it is determined that the detection efficiency and accuracy are satisfied under the measurement scenario set in the verification project; otherwise, it is determined that the detection efficiency and accuracy are not satisfied under the measurement scenario set in the verification project.

[0012] In the method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant according to the present invention, the relative deviation is calculated by the following formula: ; In the formula, This is a relative deviation. For theoretical detection efficiency, To measure the efficiency of the experiment.

[0013] This invention also provides a device for verifying the detection efficiency and accuracy of an on-site gamma spectrometer at a nuclear power plant, comprising: The parameter acquisition unit is used to acquire the basic geometric and physical parameters of the detector. The verification item determination unit is used to determine the verification items for detection efficiency and accuracy based on the basic geometric parameters, physical parameters and uncertainty sources of the detector. The test efficiency measurement unit is used to perform measurements according to the verification items using a standard point source to obtain the corresponding test measurement efficiency. The theoretical detection efficiency calculation unit is used to calculate the theoretical detection efficiency for each verification item based on the radiation source information of the standard point source and the detector model. An accuracy evaluation unit is used to evaluate the accuracy of the passive efficiency scale based on the experimental measurement efficiency and the theoretical detection efficiency.

[0014] The present invention also provides a storage medium storing a computer program adapted for loading by a processor to perform the steps of the method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant as described in any of the preceding claims.

[0015] The present invention also provides an electronic device, including a memory and a processor, wherein the memory stores a computer program, and the processor executes the steps of the method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant as described in any of the preceding claims by calling the computer program stored in the memory.

[0016] The method, apparatus, medium, and equipment for verifying the accuracy of on-site gamma spectrometer detection efficiency in nuclear power plants according to the present invention have the following beneficial effects: They include: acquiring the basic geometric and physical parameters of the detector; determining verification items; using a standard point source to perform measurements according to the verification items to obtain the corresponding experimental measurement efficiency; calculating the theoretical detection efficiency for each verification item based on the radioactive source information of the standard point source and the detector model; and evaluating the accuracy of the passive efficiency calibration based on the experimental measurement efficiency and the theoretical detection efficiency. The verification items designed in this invention can comprehensively evaluate the accuracy of the passive efficiency calibration of the deposition source term survey spectrometer in nuclear power plant systems. The verification process is standardized and regulated, and the verification results from different laboratories are comparable. Furthermore, the present invention uses a standard point source for actual on-site simulation verification, which not only solves the current industry problem of being unable to assess measurement accuracy but also ensures the comprehensiveness and reliability of the verification. Attached Figure Description

[0017] The present invention will be further described below with reference to the accompanying drawings and embodiments. In the accompanying drawings: Figure 1 This is a flowchart illustrating the method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant, as provided by this invention. Figure 2 This is a schematic diagram of the axial distance verification measurement provided by the present invention; Figure 3 This is a measurement schematic diagram of the lateral offset verification provided by the present invention; Figure 4 This is a measurement schematic diagram of the composite geometric condition verification provided by the present invention; Figure 5 This is a logic block diagram of the nuclear power plant on-site gamma spectrometer detection efficiency and accuracy verification device provided by the present invention. Detailed Implementation

[0018] The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0019] To address the current issues in verifying the accuracy of passive efficiency calibration, this invention provides a method for verifying the accuracy of passive efficiency calibration using an on-site gamma spectrometer at a nuclear power plant. This method is a systematic approach to verifying the accuracy of passive efficiency calibration using an on-site gamma spectrometer at a nuclear power plant. The on-site gamma spectrometer used here refers to a deposition source term survey spectrometer for nuclear power plant systems. This method comprehensively evaluates the accuracy of the passive efficiency calibration model under different geometric conditions and energy ranges through point source-by-point simulation verification, providing reliable quality assurance for the analysis of deposition source terms in nuclear power plant systems.

[0020] refer to Figure 1 In a preferred embodiment, the method for verifying the detection efficiency and accuracy of the on-site gamma spectrometer at the nuclear power plant includes steps S10, S20, S30, S40, and S50.

[0021] Step S10: Obtain the basic geometric and physical parameters of the detector.

[0022] In this embodiment of the invention, the detector refers to the detector used in the deposition source term survey spectrometer of the nuclear power plant system. Its basic geometric and physical parameters include: crystal diameter, crystal length, dead layer thickness, encapsulation material type and thickness, etc.

[0023] Step S20: Determine the verification items for detection efficiency and accuracy based on the basic geometric parameters, physical parameters, and uncertainty sources of the detector.

[0024] In this embodiment of the invention, by analyzing the characteristics of the acquired basic geometric and physical parameters of the detector, and combining this with the uncertainty sources of the deposition source term investigation spectrometer in a nuclear power plant system, a systematic verification project for the detection efficiency and accuracy is designed. Preferably, the systematic verification project designed in this invention includes three verification projects: axial distance verification, lateral offset verification, and composite geometric condition verification. Each verification project verifies the accuracy of the detector model in one or more parameters of the detector model through standard point source measurements.

[0025] This invention, through the design of the aforementioned verification items, allows for adaptive adjustments to the verification test parameters based on the passive efficiency calibration application scenario (such as detector detection efficiency, sample distance, and standard point source activity level). The specific verification items are as follows: Axial distance verification: The axial distance verification is used to evaluate the accuracy of the detector model when the distance between the standard point source and the detector varies. This verification project mainly tests the accuracy of the detector crystal size parameters (especially crystal length) and dead layer thickness parameters. Figure 2 As shown, the standard point source is rotated on the detector axis, and measurements are taken at different distances from the detector cap (such as 5cm, 10cm, 15cm, and 20cm) to obtain the theoretical detection efficiency and experimental measurement efficiency of each distance point (i.e., each verification point).

[0026] Lateral offset verification: The lateral offset verification is used to evaluate the accuracy of the change in the lateral position of the detector model relative to the standard point source. This verification project mainly examines the accuracy of the detector crystal diameter parameters and crystal position parameters. Specifically, such as... Figure 3 As shown, the standard point source is rotated to a fixed height (e.g., 10cm above the detector cap) and moved radially along the detector (e.g., offset by 0cm, 2cm, 4cm, 6cm). The theoretical detection efficiency and experimental measurement efficiency of each location point (i.e., each verification point) are measured.

[0027] Verification of composite geometric conditions: The composite geometry condition verification is used to evaluate the overall accuracy of the detector model under complex geometric conditions. This verification project comprehensively examines the synergistic effects of various parameters of the detector model.

[0028] For radiation monitoring in nuclear power plants, the samples to be tested are generally placed in containers or inside equipment pipes, and are generally simplified to be uniformly distributed in the subspace. Therefore, point sources are placed at various locations inside the containers or equipment pipes to simulate the contribution of a single radioactive element to the detector's detection efficiency.

[0029] Because the samples being tested are quite complex, simplified containers or pipes can be used. There are generally several verification points, including 0° close-range, large-angle close-range, 0° far-range, and large-angle far-range. The large angle refers to the angle between the edge of the sample and the detector, typically greater than 60°.

[0030] The following explanation uses a pipeline as an example.

[0031] like Figure 4As shown, during typical pipeline measurements, the detector is aligned with the center point of the pipeline, and the detector is equidistant from both ends of the pipeline. Four verification points are set up: A, B, C, and D. Points A and B are on a straight line with the detector center. Point A is closest to the detector, touching the inner surface of the pipeline. Point B is also closest to the detector, touching the inner surface of the pipeline and opposite to point A, but furthest from the detector in the vertical direction. Point C is also closest to the detector, touching the inner surface of the pipeline at one end, and furthest from the detector in the vertical direction. Point D is also furthest to the detector, touching the inner surface of the pipeline at one end, opposite to point C.

[0032] Step S30: Use a standard point source to perform measurements according to the verification items to obtain the corresponding test measurement efficiency.

[0033] Optionally, in this embodiment of the invention, a traceable standard point source is used, and measurements are performed according to the aforementioned designed verification items. In this invention, to ensure that the verification items essentially cover the energy range of gamma energy in nuclear power plants, the standard point source should cover a relatively wide energy range (e.g., 50 keV to 2000 keV), and the use of [specific standard point source name] is recommended. 241 Am (59.5keV) 57 Co (122.1keV) 137 Cs (661.7keV) 60 Nuclide such as Co (1173.2 keV and 1332.5 keV).

[0034] Sufficient statistical counts must be ensured during measurement; the statistical uncertainty of the full-energy peak count should be less than 1%. The measurement distance can be adjusted appropriately based on the standard point source activity and pipe length. Data to be recorded during measurement includes: the standard point source activity value A (in Bq) after half-life correction, the measured activity time t (in seconds), the γ full-energy peak count N of the nuclide, and the branching ratio y corresponding to that energy of the nuclide. It should be noted that a standard point source contains one or more internuclear pairs, such as... 60 Co. A nuclide can emit one or more gamma energies, such as 60 Co emits at 1173.2 keV and 1332.5 keV. Different energies correspond to different branching ratios, resulting in varying detection efficiencies. Therefore, the energy and branching ratio must be specified when determining detection efficiency. The branching ratio represents the proportion of a particular decay mode to the total decay probability, usually expressed as a percentage.

[0035] In each verification project, the experimental measurement efficiency obtained from the experimental measurements at each verification point is as follows: It can be obtained by calculation using the following formula: ; In the formula, For the sake of experimental measurement efficiency, Count the γ-ray total energy peaks of this nuclide. This is the standard point source activity value after half-life correction. For the live time measured in the experiment, This represents the branching ratio corresponding to the energy emitted by a certain nuclide.

[0036] Step S40: Calculate the theoretical detection efficiency for each verification item based on the radiation source information and detector model of the standard point source.

[0037] In this embodiment of the invention, the detector model can be established in the Monte Carlo model based on the basic geometric and physical parameters of the detector obtained in step S10; or, if the nuclear power plant system deposition source term investigation spectrometer (such as a gamma spectrometer) is already equipped with model building software, the model building software can be directly called for calculation.

[0038] Specifically, first, obtain the radioactive source information of the detector model and the standard point source; then, establish the corresponding geometric model and source distribution settings according to the verification project designed in step S20, or directly set the radioactive source information of the standard point source and the sample container information in the model building software; next, run the Monte Carlo software or model building software to calculate the theoretical detection efficiency corresponding to the energy emitted by each standard point source. In each verification project, the theoretical detection efficiency at each verification point is calculated using the following formula: ; In the formula, For theoretical detection efficiency, The set number of emitted gamma particles, This represents the number of γ particles received at the corresponding energy level.

[0039] Step S50: Evaluate the accuracy of the passive efficiency calibration based on the experimental measurement efficiency and the theoretical detection efficiency.

[0040] In this embodiment of the invention, step S50, which evaluates the accuracy of the passive efficiency calibration based on the experimental measurement efficiency and the theoretical detection efficiency, includes: calculating the relative deviation of each verification point for each verification item; the relative deviation being the relative deviation between the experimental measurement efficiency and the theoretical detection efficiency; and evaluating the accuracy of the passive efficiency calibration based on the relative deviation of each verification point.

[0041] The accuracy assessment of the passive efficiency scale based on the relative deviation of each verification point includes: for axial distance verification and lateral offset verification, the relative deviation of each verification point is less than a first preset value; for complex geometric condition verification, the relative deviation of each verification point is less than a second preset value, and the signs of the relative deviations within the same item are irregular; if all the above conditions are met, the detection efficiency is determined to be reliable under the measurement scenario set in the verification item (i.e., the accuracy of the passive efficiency scale is reliable); otherwise, the detection efficiency accuracy is determined to be unsatisfactory under the measurement scenario set in the verification item. Preferably, the first preset value is 10%, and the second preset value is 20%. It should be noted that the specific values ​​of the first and second preset values ​​can be adjusted appropriately according to the detector type, measurement accuracy requirements, etc.

[0042] In this embodiment of the invention, the relative deviation is calculated using the following formula: ; In the formula, This is a relative deviation. For theoretical detection efficiency, To measure the efficiency of the experiment.

[0043] By calculating the theoretical detection efficiency and experimental measurement efficiency, the relative deviation is calculated, and the accuracy of the detector model under various verification projects is evaluated based on the relative deviation. Specifically, for each verification project, the relative deviation at each verification point is calculated according to the aforementioned formula. The accuracy of the detector model under each verification item is then evaluated according to the accuracy evaluation criteria provided by this invention. The accuracy evaluation criteria are as follows: For axial distance verification and lateral offset verification, the relative deviation of each verification point should be less than 10%. For verification under complex geometric conditions, the relative deviation of each verification point should be less than 20%. Within the same verification project, the sign of the relative deviation should not have a clear regularity (i.e., it should not show a systematic high or low deviation).

[0044] The following table, taking the axial distance verification of the detector as an example, shows the relative deviation of each verification point obtained by calculation.

[0045] Table 1 As can be seen from Table 1, the relative deviations are all less than 10%, proving that the detector model is relatively accurate within the radial distance of 20~30cm between the standard point source and the detector. This passive efficiency calibration method has accuracy and adaptability at this measurement distance.

[0046] refer to Figure 5The present invention also provides a device for verifying the accuracy and efficiency of an on-site gamma spectrometer in a nuclear power plant. This device can be applied to the method for verifying the accuracy and efficiency of an on-site gamma spectrometer in a nuclear power plant disclosed in the embodiments of the present invention.

[0047] Specifically, such as Figure 5 As shown, the on-site gamma spectrometer detection efficiency and accuracy verification device at this nuclear power plant includes: The parameter acquisition unit 501 is used to acquire the basic geometric and physical parameters of the detector.

[0048] The verification item determination unit 502 is used to determine the verification items for detection efficiency and accuracy based on the basic geometric parameters, physical parameters and uncertainty sources of the detector.

[0049] The test efficiency measurement unit 503 is used to perform measurements according to the verification items using a standard point source to obtain the corresponding test measurement efficiency.

[0050] The theoretical detection efficiency calculation unit 504 is used to calculate the theoretical detection efficiency for each verification item based on the radiation source information of the standard point source and the detector model.

[0051] The accuracy evaluation unit 505 is used to evaluate the accuracy of the passive efficiency scale based on the experimental measurement efficiency and the theoretical detection efficiency.

[0052] Specifically, the specific operational procedures between the various units in the on-site gamma spectrometer detection efficiency and accuracy verification device for nuclear power plants can be referred to in the above-mentioned method for verifying the on-site gamma spectrometer detection efficiency and accuracy, and will not be repeated here.

[0053] The method and apparatus for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant, as described in this invention, have the following advantages compared to existing technologies: The verification projects are comprehensive and systematic: This invention designs three verification projects: axial distance verification, lateral offset verification, and composite geometric condition verification. These projects simulate the actual distribution of deposition source terms in a nuclear power plant system. The system covers the influencing factors of various parameters of the detector model and can comprehensively evaluate the accuracy of the deposition source term survey spectrometer in a nuclear power plant system.

[0054] The verification method is scientific and standardized: This invention provides clear and detailed verification experimental methods, data processing methods and accuracy evaluation standards, which standardizes and normalizes the verification process and makes the verification results of different laboratories comparable.

[0055] This invention solves the current industry problem of being unable to evaluate measurement accuracy: It uses a standard point source for actual field simulation verification, which, compared with the standard volume source verification method, ensures the comprehensiveness and reliability of the verification.

[0056] Furthermore, an electronic device of the present invention includes a memory and a processor; the memory is used to store a computer program; the processor is used to execute the computer program to implement the method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant as described above. Specifically, according to embodiments of the present invention, the processes described above with reference to the flowchart can be implemented as computer software programs. For example, embodiments of the present invention include a computer program product comprising a computer program carried on a computer-readable medium, the computer program containing program code for performing the methods shown in the flowchart. In such embodiments, when the computer program is downloaded, installed, and executed by an electronic device, it performs the functions defined above in the methods of the embodiments of the present invention. The electronic device in the present invention can be a terminal such as a laptop, desktop computer, tablet computer, or smartphone, or it can be a server.

[0057] Furthermore, one type of storage medium of the present invention stores a computer program thereon, which, when executed by a processor, implements the method for verifying the accuracy of on-site gamma spectrometer detection efficiency in nuclear power plants, as described above. Specifically, it should be noted that the storage medium described above in the present invention can be a computer-readable signal medium or a computer-readable storage medium, or any combination thereof. A computer-readable storage medium can be, for example, but not limited to, an electrical, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or any combination thereof. More specific examples of a computer-readable storage medium may include, but are not limited to: an electrical connection having one or more wires, a portable computer disk, a hard disk, random access memory (RAM), read-only memory (ROM), erasable programmable read-only memory (EPROM or flash memory), optical fiber, portable compact disk read-only memory (CD-ROM), optical storage device, magnetic storage device, or any suitable combination thereof. In the present invention, a computer-readable storage medium can be any tangible medium containing or storing a program that can be used by or in conjunction with an instruction execution system, apparatus, or device. In this invention, a computer-readable signal medium may include a data signal propagated in baseband or as part of a carrier wave, carrying computer-readable program code. This propagated data signal may take various forms, including but not limited to electromagnetic signals, optical signals, or any suitable combination thereof. The computer-readable signal medium may also be any computer-readable medium other than a computer-readable storage medium, capable of sending, propagating, or transmitting a program for use by or in conjunction with an instruction execution system, apparatus, or device. The program code contained on the computer-readable medium may be transmitted using any suitable medium, including but not limited to: wires, optical fibers, RF (radio frequency), etc., or any suitable combination thereof.

[0058] The aforementioned computer-readable medium may be included in the aforementioned electronic device; or it may exist independently and not assembled into the electronic device.

[0059] The various embodiments in this specification are described in a progressive manner, with each embodiment focusing on its differences from other embodiments. Similar or identical parts between embodiments can be referred to interchangeably. For the apparatus disclosed in the embodiments, since they correspond to the methods disclosed in the embodiments, the description is relatively simple; relevant parts can be referred to the method section.

[0060] Those skilled in the art will further recognize that the units and algorithm steps of the various examples described in conjunction with the embodiments disclosed herein can be implemented in electronic hardware, computer software, or a combination of both. To clearly illustrate the interchangeability of hardware and software, the components and steps of the various examples have been generally described in terms of functionality in the foregoing description. Whether these functions are implemented in hardware or software depends on the specific application and design constraints of the technical solution. Those skilled in the art can use different methods to implement the described functions for each specific application, but such implementations should not be considered beyond the scope of this invention.

[0061] The steps of the methods or algorithms described in conjunction with the embodiments disclosed herein can be implemented directly by hardware, a software module executed by a processor, or a combination of both. The software module can be located in random access memory (RAM), main memory, read-only memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, removable disk, CD-ROM, or any other form of storage medium known in the art.

[0062] The above embodiments are only for illustrating the technical concept and features of the present invention, and are intended to enable those skilled in the art to understand the content of the present invention and implement it accordingly. They do not limit the scope of protection of the present invention. All equivalent changes and modifications made within the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A method for verifying the accuracy of the detection efficiency of an in-situ gamma spectrometer of a nuclear power plant, characterized in that, include: Step S10: Obtain the basic geometric and physical parameters of the detector; Step S20: Determine the verification items for detection efficiency and accuracy based on the basic geometric parameters, physical parameters, and uncertainty sources of the detector; Step S30: Use a standard point source to perform measurements according to the verification items to obtain the corresponding test measurement efficiency; Step S40: Calculate the theoretical detection efficiency for each verification item based on the radiation source information and detector model of the standard point source. Step S50: Evaluate the accuracy of the passive efficiency calibration based on the experimental measurement efficiency and the theoretical detection efficiency.

2. The method of claim 1, wherein, The verification items include: axial distance verification, lateral offset verification, and composite geometric condition verification; The axial distance verification is used to evaluate the accuracy of the detector model when the distance between the standard point source and the detector varies; The lateral offset verification is used to evaluate the accuracy of the change in the lateral position of the detector model relative to the standard point source; The composite geometry condition verification is used to evaluate the overall accuracy of the detector model under complex geometric conditions.

3. The method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant according to claim 1, characterized in that, The experimental measurement efficiency is calculated using the following formula: ； In the formula, For the sake of experimental measurement efficiency, Count the γ-ray total energy peaks of this nuclide. This is the standard point source activity value after half-life correction. For the live time measured in the experiment, This represents the branching ratio corresponding to the energy emitted by a certain nuclide.

4. The method of claim 1, wherein: The theoretical detection efficiency is calculated using the following formula: ； In the formula, is the theoretical detection efficiency, is the number of emitted gamma particles set, is the number of gamma particles received at the corresponding energy.

5. The method of claim 1, wherein: In step S50, the accuracy assessment of the passive efficiency calibration based on the experimental measurement efficiency and the theoretical detection efficiency includes: For each verification item, the relative deviation at each verification point is calculated; the relative deviation is the relative deviation between the experimental measurement efficiency and the theoretical detection efficiency. The accuracy of the passive efficiency calibration is evaluated based on the relative deviation of each verification point.

6. The method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant according to claim 5, characterized in that, The accuracy assessment of the passive efficiency scale based on the relative deviation of each verification point includes: For axial distance verification and lateral offset verification, the relative deviation of each verification point is less than the first set value; for complex geometric condition verification, the relative deviation of each verification point is less than the second set value, and the sign of the relative deviation within the same item is irregular. If all the above conditions are met, it is determined that the detection efficiency and accuracy are satisfied under the measurement scenario set in the verification project; otherwise, it is determined that the detection efficiency and accuracy are not satisfied under the measurement scenario set in the verification project.

7. The method of claim 5, wherein the method further comprises: The relative deviation is calculated using the following formula: ； wherein is the relative deviation, is the theoretical detection efficiency, is the experimental measurement efficiency.

8. A device for verifying the accuracy of the detection efficiency of an in-situ gamma spectrometer of a nuclear power plant, characterized in that, include: The parameter acquisition unit is used to acquire the basic geometric and physical parameters of the detector. The verification item determination unit is used to determine the verification items for detection efficiency and accuracy based on the basic geometric parameters, physical parameters and uncertainty sources of the detector. The test efficiency measurement unit is used to perform measurements according to the verification items using a standard point source to obtain the corresponding test measurement efficiency. The theoretical detection efficiency calculation unit is used to calculate the theoretical detection efficiency for each verification item based on the radiation source information of the standard point source and the detector model. An accuracy evaluation unit is used to evaluate the accuracy of the passive efficiency scale based on the experimental measurement efficiency and the theoretical detection efficiency.

9. A storage medium, characterized by The storage medium stores a computer program adapted for loading by a processor to perform the steps of the method for verifying the detection efficiency and accuracy of an on-site gamma spectrometer in a nuclear power plant as described in any one of claims 1 to 7.

10. An electronic device, comprising: The method comprises a memory and a processor, the memory stores a computer program, and the processor executes the steps of the method for verifying the detection efficiency accuracy of a nuclear power plant in-situ gamma spectrometer according to any one of claims 1 to 7 by calling the computer program stored in the memory.

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