Method, device, storage medium and electronic device for measuring radioactivity

Abstract

The present disclosure relates to a method, device, storage medium and electronic device for measuring radioactivity, the method comprising: obtaining an absorption factor of a shielding medium corresponding to each of a plurality of target radioactive objects in a target container and an absorption factor of the target container, the absorption factors representing absorption efficiencies of radioactive rays of the target radioactive objects; and determining radioactivity of the target radioactive objects according to the absorption factors of the shielding medium and the absorption factor of the target container. In this way, the radioactivity of the target radioactive objects is determined according to the absorption factors of the shielding medium and the absorption factor of the target container, thereby avoiding the problem of poor accuracy of the analysis result of the radioactivity due to non-uniform radioactivity of the plurality of target radioactive objects, and effectively improving the accuracy of the radioactivity measurement result when the plurality of target radioactive objects are non-uniform radioactive sources.

Description

TECHNICAL FIELD

[0001] The present disclosure relates to the technical field of radioactivity measurement, and in particular, to a radioactivity measurement method, device, storage medium and electronic equipment. BACKGROUND

[0002] With the development of the nuclear industry, a large amount of recoverable nuclear waste and nuclear waste is accumulated in the production process of nuclear facilities. In order to implement effective control of nuclear materials and sustainable development of nuclear technology, the radioactive waste barrels generated in the nuclear facilities must be reasonably treated and disposed. According to the requirements of national regulations, the activity analysis measurement must be completed before the waste barrels are disposed, and the analysis measurement data must be obtained for each material. However, due to the uneven distribution of such radioactive waste, it is difficult to ensure accuracy by using ordinary non-destructive analysis methods. SUMMARY

[0003] To solve the above problems, the present disclosure provides a radioactivity measurement method, device, storage medium and electronic equipment.

[0004] In a first aspect, the present disclosure provides a radioactivity measurement method, comprising:

[0005] obtaining an absorption factor of a shielding medium corresponding to each target radioactive material in a plurality of target radioactive materials in a target container and an absorption factor of the target container, the absorption factor representing the absorption efficiency of radioactive rays of the target radioactive material; and determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container.

[0006] Optionally, the obtaining of the absorption factor of the shielding medium of each target radioactive material in the plurality of target radioactive materials in the target container comprises: for each target radioactive material in the plurality of target radioactive materials, obtaining a linear absorption coefficient and a thickness of the shielding medium corresponding to the target radioactive material, the linear absorption coefficient of the shielding medium representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the shielding medium; and determining the absorption factor of the shielding medium of each target radioactive material according to the linear absorption coefficient and the thickness of the shielding medium.

[0007] Optionally, the obtaining of the absorption factor of the target container comprises: obtaining a linear absorption coefficient of the target container and a thickness of the target container, the linear absorption coefficient of the target container representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the material corresponding to the target container; and determining the absorption factor of the target container according to the linear absorption coefficient of the target container and the thickness of the target container.

[0008] Optionally, the determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container comprises: determining, by a preset detector, a full-energy peak net count rate of each of the plurality of target radioactive materials; obtaining a detection efficiency of the preset detector and a geometric factor of the target container, the geometric factor representing an influence coefficient of a shape of the container on a detection result; and determining the radioactivity of the target radioactive material according to the detection efficiency, the absorption factor of the shielding medium, the absorption factor of the target container, and the geometric factor of the target container.

[0009] Optionally, the method further comprises: obtaining masses of the plurality of target radioactive materials; and determining specific activities of the plurality of target radioactive materials according to the radioactivities and the masses of the plurality of target radioactive materials.

[0010] Optionally, the obtaining the masses of the plurality of target radioactive materials comprises: obtaining a total mass of the target radioactive material and the target container, and a mass of the target container; and determining the masses of the plurality of target radioactive materials according to the total mass and the mass of the target container.

[0011] In a second aspect, the present disclosure provides a device for measuring radioactivity, comprising:

[0012] an obtaining module configured to obtain an absorption factor of a shielding medium corresponding to each of a plurality of target radioactive materials in a target container and an absorption factor of the target container, the absorption factors representing absorption efficiencies of radioactive rays of the target radioactive materials;

[0013] a determining module configured to determine radioactivities of the target radioactive materials according to the absorption factor of the shielding medium and the absorption factor of the target container.

[0014] Optionally, the obtaining module is configured to, for each of the plurality of target radioactive materials, obtain a linear absorption coefficient and a thickness of the shielding medium corresponding to the target radioactive material, the linear absorption coefficient of the shielding medium representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the shielding medium; and determine the absorption factor of the shielding medium of the target radioactive material according to the linear absorption coefficient and the thickness of the shielding medium.

[0015] Optionally, the obtaining module is configured to obtain a linear absorption coefficient of the target container and a thickness of the target container, the linear absorption coefficient of the target container representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by a material corresponding to the target container; and determine the absorption factor of the target container according to the linear absorption coefficient of the target container and the thickness of the target container.

[0016] Optionally, the determining module is configured to determine a full-energy peak net count rate of each target radioactive material in the plurality of target radioactive materials by using a preset detector; obtain a detection efficiency of the preset detector and a geometric factor of the target container, the geometric factor representing an influence coefficient of a shape of the target container on a detection result; and determine the radioactivity of the target radioactive material according to the detection efficiency, an absorption factor of the shielding medium, an absorption factor of the target container, and the geometric factor of the target container.

[0017] Optionally, the obtaining module is further configured to obtain the mass of the plurality of target radioactive materials.

[0018] The determining module is further configured to determine the specific activity of the plurality of target radioactive materials according to the radioactivity and the mass of the plurality of target radioactive materials.

[0019] Optionally, the obtaining module is configured to obtain a total mass of the target radioactive material and the target container, and a mass of the target container; and determine the mass of the plurality of target radioactive materials according to the total mass and the mass of the target container.

[0020] In a third aspect, the present application provides a non-transitory computer readable storage medium having a computer program stored thereon, the program being executed by a processor to implement the steps of the above method.

[0021] In a fourth aspect, the present application provides an electronic device, comprising:

[0022] a memory having a computer program stored thereon;

[0023] a processor configured to execute the computer program in the memory to implement the steps of the above method.

[0024] With the above technical solution, the absorption factor of the shielding medium corresponding to each target radioactive material in the plurality of target radioactive materials in the target container and the absorption factor of the target container are obtained, the absorption factor representing the absorption efficiency of the radioactive rays of the target radioactive material; and the radioactivity of the target radioactive material is determined according to the absorption factor of the shielding medium and the absorption factor of the target container. In this way, by determining the absorption factor corresponding to each target radioactive material in the plurality of target radioactive materials, and determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container, the problem of poor accuracy of the radioactivity analysis result caused by the non-uniform radioactivity of the plurality of target radioactive materials is avoided, and the accuracy of the radioactivity measurement result when the plurality of target radioactive materials are non-uniform radioactive sources can be effectively improved.

[0025] Other features and advantages of the present disclosure will be described in detail in the following detailed description section. BRIEF DESCRIPTION OF DRAWINGS

[0026] The accompanying drawings are included to provide a further understanding of the present disclosure and are incorporated in and constitute a part of the specification, illustrate embodiments of the present disclosure and serve to explain the principles of the present disclosure, but are not intended to limit the present disclosure. In the drawings:

[0027] Figure 1 is a flow chart of a method of radioactivity measurement according to an exemplary embodiment;

[0028] Figure 2 is a block diagram of a device of radioactivity measurement according to an exemplary embodiment;

[0029] Figure 3 is a block diagram of an electronic device according to an exemplary embodiment. DETAILED DESCRIPTION

[0030] The specific embodiments of the present disclosure will be described below in detail with reference to the accompanying drawings. It should be understood that the specific embodiments described herein are merely intended to illustrate and explain the present disclosure, and are not intended to limit the present disclosure.

[0031] It should be noted that all actions of acquiring signals, information or data in the present disclosure are carried out in compliance with the corresponding data protection regulations and policies of the country where the device is located, and with the authorization given by the corresponding device owner.

[0032] First, the application scenario of the present application is described. The present application is applied to the scene of radioactivity measurement of radioactive substances. In this scene, the existing measurement method is to calculate the radioactivity by the linear attenuation coefficient of water. For non-uniformly distributed waste barrels and nuclear waste samples to be disposed of, two high-purity germanium detectors are used to measure the waste barrels to improve the accuracy of the analysis, and the linear attenuation coefficient of the medium in the barrel is calculated by multiplying the linear attenuation coefficient of water by the density. In particular, for the case where there are many types of shielding media in the target container, the linear attenuation coefficient of water is usually used, and the linear attenuation coefficient of the shielding medium is determined by multiplying the linear attenuation coefficient of water by the density of the target radioactive material. Then, the thickness of the shielding medium is determined by the radius of the target container and the distance between the target radioactive material and the axis of the target container. Finally, the radioactivity is determined by the linear attenuation coefficient and the thickness of the shielding medium.

[0033] However, the inventors have found that in the related art, the attenuation coefficient of the shielding medium is determined by the linear attenuation coefficient of water, and the thickness of the shielding medium is determined by the radius of the target container, which usually has a large error and low accuracy, resulting in poor accuracy of the finally measured radioactivity.

[0034] To solve the above problems, the present application provides a method and device for measuring radioactivity, a storage medium and an electronic device, comprising: obtaining an absorption factor of a shielding medium corresponding to each target radioactive material in a plurality of target radioactive materials in a target container and an absorption factor of the target container, the absorption factor representing the absorption efficiency of radioactive rays of the target radioactive material; determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container. In this way, by determining the absorption factor corresponding to each target radioactive material in a plurality of target radioactive materials, and determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container, the problem of poor accuracy of radioactivity analysis results caused by non-uniform radioactivity of the plurality of target radioactive materials is avoided, and the accuracy of the radioactivity measurement results when the plurality of target radioactive materials are non-uniform radioactive sources can be effectively improved.

[0035] The present disclosure will be described in detail below with reference to specific embodiments.

[0036] Figure 1 A method for measuring radioactivity according to an exemplary embodiment is shown in FIG. 1. Figure 1 The method comprises:

[0037] S101, obtaining an absorption factor of a shielding medium corresponding to each target radioactive material in a plurality of target radioactive materials in a target container and an absorption factor of the target container.

[0038] The absorption factor represents the absorption efficiency of radioactive rays of the target radioactive material, the absorption factor of the shielding medium is related to the linear absorption coefficient of the material of the shielding medium and the thickness of the shielding medium, and the absorption factor of the target container is related to the linear absorption coefficient of the material of the target container and the thickness of the target container.

[0039] In some embodiments, the absorption factor of the shielding medium of each target radioactive material can be determined by respectively obtaining the linear absorption coefficient and the thickness of the shielding medium corresponding to each target radioactive material.

[0040] For example, for each target radioactive material in the plurality of target radioactive materials, the linear absorption coefficient and the thickness of the shielding medium corresponding to the target radioactive material are obtained, the linear absorption coefficient of the shielding medium representing the linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the shielding medium; the absorption factor of the shielding medium of each target radioactive material is determined according to the linear absorption coefficient and the thickness of the shielding medium.

[0041] For example, the absorption factor ε1 of the shielding medium can be determined by the following formula:

[0042]

[0043] wherein ε1 is the absorption factor of the shielding medium, e is a natural constant, μ 介 is the linear absorption coefficient of the medium material of the shielding medium, the linear absorption coefficient is an inherent attribute of the material corresponding to the shielding medium, and can be obtained through a preset material-linear absorption coefficient correspondence relationship, d 介 is the thickness of the shielding medium, and the absorption factor of the shielding medium corresponding to the target radioactive material can be determined through the above formula.

[0044] In some other embodiments, the absorption factor of the target container can be determined by obtaining the linear absorption coefficient and the thickness of the target container.

[0045] For example, the linear absorption coefficient of the target container and the thickness of the target container are obtained, the linear absorption coefficient of the target container characterizes the linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the material corresponding to the target container; and the absorption factor of the target container is determined according to the linear absorption coefficient of the target container and the thickness of the target container.

[0046] For example, the absorption factor ε2 of the target container can be determined by the following formula:

[0047]

[0048] wherein ε2 is the absorption factor of the target container, μ 容 is the linear absorption coefficient of the material corresponding to the target container, and the linear absorption coefficient can be obtained through a preset material-linear absorption coefficient correspondence relationship, d 容 is the thickness of the target container, and the absorption factor of the shielding medium corresponding to the target radioactive material can be determined through the above formula. For example, in the case of a standard waste barrel, the barrel wall material of the waste barrel is stainless steel, so the μ 容 may be the linear absorption coefficient of iron, and the barrel wall thickness is generally between 0.8mm-2mm, and 2mm is used for calculation here, that is, the absorption factor of the target container is:

[0049]

[0050] In this way, by respectively calculating the absorption factor of the shielding medium of the target radioactive material and the absorption factor of the target container, the accuracy of determining the radioactivity of the target radioactive material is improved.

[0051] S102, determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container.

[0052] In one possible implementation, the net count rate of the full-energy peak of each of the multiple target radioactive materials can first be determined by a preset detector; then the detection efficiency of the preset detector and the geometric factor of the target container are obtained, the geometric factor being a coefficient representing the influence of the shape of the container on the detection results; finally, the radioactivity of the target radioactive material is determined based on the detection efficiency, the absorption factor of the shielding medium, the absorption factor of the target container, and the geometric factor of the target container.

[0053] The preset detector has different detection efficiencies for each of the multiple target radioactive objects. The detection efficiency can be determined by a preset correspondence between target radioactive objects and detection efficiency. The geometric factor is determined by the shape of the target container. Different shapes correspond to different geometric factors. The geometric factor can be determined by a preset correspondence between geometric factors. For example, for a standard cylindrical 200L waste bin with a fixed shape, the geometric factor is 0.823.

[0054] For example, the radioactivity of the target radioactive material can be determined using the following formula:

[0055]

[0056] Among them, A i Characterizing the radioactivity of the i-th target radioactive material among the multiple target radioactive materials, the n i The full-energy peak net count rate of the i-th target radioactive object among the multiple target radioactive objects is represented by B, which represents the branching ratio of the γ-rays emitted by the target radioactive object. The γ-ray branching ratio of the target radioactive object is determined by the nuclide of the target radioactive object. Different nuclides correspond to different γ-ray branching ratios, which are inherent properties of the target radioactive object and can be determined by a preset γ-ray branching ratio correspondence. ε1 represents the absorption factor of the shielding medium corresponding to the target radioactive object. ε2 represents the absorption factor of the target container. ε3 represents the detection efficiency of the preset detector for the target radioactive object. f represents the geometric factor of the target container.

[0057] The absorption factor of the shielding medium corresponding to each target radioactive material in the plurality of target radioactive materials in the target container and the absorption factor of the target container are obtained by the above method, the absorption factor representing the absorption efficiency of the radioactive rays of the target radioactive material; and the radioactivity of the target radioactive material is determined according to the absorption factor of the shielding medium and the absorption factor of the target container. In this way, by determining the absorption factor corresponding to each target radioactive material in the plurality of target radioactive materials, and determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container, the problem of poor accuracy of the radioactivity analysis result caused by the non-uniform radioactivity of the plurality of target radioactive materials is avoided, and the accuracy of the radioactivity measurement result when the plurality of target radioactive materials are non-uniform radioactive sources can be effectively improved.

[0058] In addition, after determining the radioactivity of each target radioactive material in the plurality of target radioactive materials in the target container, the total radioactivity of the plurality of target radioactive materials can also be determined to further improve the accuracy of the measurement.

[0059] In some embodiments, the total radioactivity of the plurality of target radioactive materials can be determined by the specific activity of the plurality of target radioactive materials.

[0060] For example, the mass of the plurality of target radioactive materials can be obtained; and the specific activity of the plurality of target radioactive materials is determined according to the radioactivity and mass of the plurality of target radioactive materials.

[0061] For example, the specific activity of the plurality of target radioactive materials can be calculated by the following formula:

[0062]

[0063] wherein the A 总 is the sum of the radioactivity of the plurality of target radioactive materials, and the m is the mass of the plurality of target radioactive materials.

[0064] wherein the sum of the radioactivity of the plurality of target radioactive materials can be calculated by the following formula:

[0065] A 总 = A1+A2+…+A n

[0066] wherein the A1 to A n respectively represent the radioactivity of the first target radioactive material to the radioactivity of the nth target radioactive material;

[0067] The mass of the plurality of target radioactive materials can be obtained by obtaining the total mass of the target radioactive material and the container, and the mass of the container; and the mass of the target radioactive material is determined according to the total mass and the mass of the container.

[0068] For example, the mass of the plurality of target radioactive materials can be calculated by the following formula:

[0069] m = m 总 -m 容器

[0070] wherein the m is the mass of the plurality of target radioactive materials, the m 总 is the total mass of the target radioactive material and the container, the m 容器 is the mass of the target container.

[0071] In this way, by determining the sum of the mass and the radioactivity of the plurality of target radioactive materials respectively by the above method, and further determining the specific activity of the plurality of target radioactive materials, the accuracy of the measurement result can be effectively improved.

[0072] In order to further illustrate the above embodiment, according to the actual production situation, the application further provides an embodiment:

[0073] An IGS (Integral Gamma Scanning) is used to analyze a 200L radioactive waste barrel with a total weight of 299.3kg. The barrel wall of the waste barrel is stainless steel with a wall thickness of 2mm. A high-purity germanium detector is used to measure that 137 the 661KeV full-energy peak count of Cs is n0, then 137 The radioactivity of Cs can be calculated according to the following formula:

[0074]

[0075] wherein n0 is the measured value 57.68cps, the value of B is 137 the branching ratio of Cs at 661KeV is 0.851, ε3 is the intrinsic detection efficiency of the source to the detector, which is simulated by MCNP (Monte Carlo N Particle Transport Code, a general software package based on the Monte Carlo method for calculating neutron, photon, electron or coupled neutron / photon / electron transport problems in three-dimensional complex geometric structures) and the value is 4.07E-05, ε2 is the absorption factor of the barrel wall, which is calculated by using the linear attenuation coefficient of iron and the above formula of ε2, and the value is 1.36, f is the geometric factor of the standard shape of the radioactive waste barrel, and ε1 is the absorption factor of the shielding medium, which is calculated according to the linear attenuation coefficient of the preset medium and the above formula of ε1, and the value is 5.74. According to the specific activity formula, the following Table 1 can be obtained:

[0076]

[0077] Table 1

[0078] As can be seen from Table 1, the radioactive activity measurement method according to the present scheme has smaller relative deviation of radioactive activity and specific activity than related art, and is more accurate.

[0079] Figure 2 Fig. 2 shows a device 200 for measuring radioactive activity according to an example embodiment, which comprises: Figure 2

[0080] The acquisition module 201 is configured to acquire an absorption factor of a shielding medium corresponding to each target radioactive material in the target container and an absorption factor of the target container, the absorption factor representing absorption efficiency of radioactive rays of the target radioactive material.

[0081] The determination module 202 is configured to determine the radioactive activity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container.

[0082] Optionally, the acquisition module 201 is configured to acquire a linear absorption coefficient of the shielding medium corresponding to each target radioactive material in the target container and a thickness of the shielding medium, the linear absorption coefficient of the shielding medium representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the shielding medium; and determine the absorption factor of the shielding medium of each target radioactive material according to the linear absorption coefficient and the thickness of the shielding medium.

[0083] Optionally, the acquisition module 201 is configured to acquire a linear absorption coefficient of the target container and a thickness of the target container, the linear absorption coefficient of the target container representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the material corresponding to the target container; and determine the absorption factor of the target container according to the linear absorption coefficient and the thickness of the target container.

[0084] Optionally, the determination module 202 is configured to determine a full-energy peak net count rate of each target radioactive material in the target container by using a preset detector; acquire a detection efficiency of the preset detector and a geometric factor of the target container, the geometric factor representing an influence coefficient of the shape of the container on the detection result; and determine the radioactive activity of the target radioactive material according to the detection efficiency, the absorption factor of the shielding medium, the absorption factor of the target container, and the geometric factor of the target container.

[0085] Optionally, the acquisition module 201 is further configured to acquire the mass of the target radioactive material.

[0086] The determination module 202 is further configured to determine specific activity of the target radioactive material according to the radioactive activity and the mass of the target radioactive material.

[0087] ​Optionally, the acquisition module 201 is configured to acquire a total mass of the target radioactive material and the target container, and a mass of the target container; and determine the mass of the plurality of target radioactive materials according to the total mass and the mass of the target container.

[0088] With the above device, the absorption factor of the shielding medium corresponding to each of the plurality of target radioactive materials in the target container and the absorption factor of the target container are acquired, the absorption factor representing the absorption efficiency of the radioactive rays of the target radioactive material; and the radioactivity of the target radioactive material is determined according to the absorption factor of the shielding medium and the absorption factor of the target container. In this way, by determining the absorption factor corresponding to each of the plurality of target radioactive materials, and determining the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container, the problem of poor accuracy of the analysis result of the radioactivity due to the non-uniform radioactivity of the plurality of target radioactive materials is avoided, and the accuracy of the measurement result of the radioactivity when the plurality of target radioactive materials are non-uniform radioactive sources can be effectively improved.

[0089] As to the device in the above embodiments, the specific manner in which each module performs operations has been described in detail in the embodiments of the method, and will not be described in detail here.

[0090] Figure 3 is a block diagram of an electronic device 300 according to an example embodiment. As shown in Figure 3 the electronic device 300 can include a processor 301 and a memory 302. The electronic device 300 can also include one or more of a multimedia component 303, an input / output (I / O) interface 304, and a communication component 305.

[0091] The processor 301 is configured to control overall operations of the electronic device 300 to complete all or part of the steps of the above radioactive activity measurement method. The memory 302 is configured to store various types of data to support operations of the electronic device 300, which can include, for example, instructions for any application or method operating on the electronic device 300, and application-related data, such as contact data, sent and received messages, pictures, audio, video, and the like. The memory 302 can be implemented by any type of volatile or non-volatile storage device or a combination thereof, such as a static random access memory (SRAM), an electrically erasable programmable read-only memory (EEPROM), an erasable programmable read-only memory (EPROM), a programmable read-only memory (PROM), a read-only memory (ROM), a magnetic memory, a flash memory, a magnetic disk, or an optical disk. The multimedia component 303 can include a screen and an audio component. The screen can be, for example, a touch screen, and the audio component is configured to output and / or input audio signals. For example, the audio component can include a microphone configured to receive external audio signals. The received audio signals can be further stored in the memory 302 or transmitted through the communication component 305. The audio component also includes at least one speaker configured to output audio signals. The I / O interface 304 provides an interface between the processor 301 and other interface modules, which can be a keyboard, a mouse, a button, and the like. The buttons can be virtual buttons or physical buttons. The communication component 305 is configured to perform wired or wireless communication between the electronic device 300 and other devices. The wireless communication, such as Wi-Fi, Bluetooth, near field communication (NFC), 2G, 3G, 4G, NB-IOT, eMTC, or other 5G, and the like, or a combination of one or more of them, is not limited herein. Therefore, the corresponding communication component 305 can include a Wi-Fi module, a Bluetooth module, an NFC module, and the like.

[0092] In an exemplary embodiment, the electronic device 300 can be implemented by one or more Application Specific Integrated Circuit (ASIC), Digital Signal Processor (DSP), Digital Signal Processing Device (DSPD), Programmable Logic Device (PLD), Field Programmable Gate Array (FPGA), controller, microcontroller, microprocessor or other electronic elements for performing the above-mentioned method of measuring radioactivity.

[0093] In another exemplary embodiment, a computer readable storage medium including program instructions is also provided, which, when executed by a processor, implement the steps of the above-mentioned method of measuring radioactivity. For example, the computer readable storage medium can be the above-mentioned memory 302 including program instructions, which can be executed by the processor 301 of the electronic device 300 to complete the above-mentioned method of measuring radioactivity.

[0094] In another exemplary embodiment, a computer program product is also provided, which contains a computer program capable of being executed by a programmable device, and the computer program has code portions for executing the above-mentioned method of measuring radioactivity when executed by the programmable device.

[0095] The preferred embodiments of the present disclosure are described in detail above with reference to the accompanying drawings, but the present disclosure is not limited to the specific details in the above-described embodiments. Within the technical concept of the present disclosure, various simple modifications can be made to the technical solutions of the present disclosure, and these simple modifications all belong to the protection scope of the present disclosure.

[0096] In addition, it should be noted that each specific technical feature described in the above-described specific embodiments can be combined in any appropriate manner without contradiction, and in order to avoid unnecessary repetition, the present disclosure will not further describe various possible combinations.

[0097] Furthermore, any combination of the various different embodiments of the present disclosure can also be made, as long as it does not deviate from the idea of the present disclosure, and it should also be considered as disclosed by the present disclosure.

Claims

1. A method of measuring radioactivity, characterized in that, The method comprises: obtaining an absorption factor of a shielding medium corresponding to each of a plurality of target radioactive materials in a target container and an absorption factor of the target container, the absorption factor representing absorption efficiency of radioactive rays of the target radioactive material; determining radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container; the absorption factor of the shielding medium is determined according to a linear absorption coefficient of a material of the shielding medium and a thickness of the shielding medium, and the absorption factor of the target container is determined according to a linear absorption coefficient of a material of the target container and a thickness of the target container; the determining of the radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container comprises: determining a full-energy peak net count rate of each of the plurality of target radioactive materials by a preset detector; obtaining a detection efficiency of the preset detector and a geometric factor of the target container, the geometric factor representing an influence coefficient of a shape of the container on a detection result; determining the radioactivity of the target radioactive material according to the detection efficiency, the absorption factor of the shielding medium, the absorption factor of the target container and the geometric factor of the target container.

2. The method of claim 1, wherein, the obtaining of the absorption factor of the shielding medium of each of the plurality of target radioactive materials in the target container comprises: for each of the plurality of target radioactive materials, obtaining a linear absorption coefficient of the shielding medium corresponding to the target radioactive material and a thickness of the shielding medium, the linear absorption coefficient of the shielding medium representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by the shielding medium; determining the absorption factor of the shielding medium of each of the target radioactive materials according to the linear absorption coefficient and the thickness of the shielding medium.

3. The method of claim 1, wherein, the obtaining of the absorption factor of the target container comprises: obtaining a linear absorption coefficient of the target container and a thickness of the target container, the linear absorption coefficient of the target container representing a linear attenuation coefficient of the radioactive rays of the target radioactive material caused by a corresponding material of the target container; determining the absorption factor of the target container according to the linear absorption coefficient of the target container and the thickness of the target container.

4. The method according to any one of claims 1 to 3, characterized in that, The method further comprises: obtaining masses of the plurality of target radioactive materials; determining specific activities of the plurality of target radioactive materials according to the radioactivity and the masses of the plurality of target radioactive materials.

5. The method of claim 4, wherein, the obtaining of the masses of the plurality of target radioactive materials comprises: obtaining a total mass of the target radioactive materials and the target container and a mass of the target container; determining the masses of the plurality of target radioactive materials according to the total mass and the mass of the target container.

6. A device for measuring radioactivity, characterized in that The device comprises: an obtaining module, configured to obtain an absorption factor of a shielding medium corresponding to each of a plurality of target radioactive materials in a target container and an absorption factor of the target container, the absorption factor representing absorption efficiency of radioactive rays of the target radioactive material; a determining module, configured to determine radioactivity of the target radioactive material according to the absorption factor of the shielding medium and the absorption factor of the target container. The absorption factor of the shielding medium is determined according to a linear absorption coefficient of a material of the shielding medium and a thickness of the shielding medium, and the absorption factor of the target container is determined according to a linear absorption coefficient of a material of the target container and a thickness of the target container. The determination module is further configured to determine a full-energy peak net count rate of each target radioactive material in the plurality of target radioactive materials by using a preset detector; acquire a detection efficiency of the preset detector and a geometric factor of the target container, the geometric factor representing an influence coefficient of a shape of the container on a detection result; and determine the radioactivity of the target radioactive material according to the detection efficiency, the absorption factor of the shielding medium, the absorption factor of the target container, and the geometric factor of the target container.

7. The apparatus of claim 6, wherein The acquisition module is configured to, for each target radioactive material in the plurality of target radioactive materials, acquire a linear absorption coefficient and a thickness of the shielding medium corresponding to the target radioactive material, the linear absorption coefficient of the shielding medium representing a linear attenuation coefficient of radioactive rays of the target radioactive material caused by the shielding medium. The absorption factor of the shielding medium of each target radioactive material is determined according to the linear absorption coefficient and the thickness of the shielding medium.

8. A non-transitory computer-readable storage medium having stored thereon a computer program, characterized in that, The program is executed by the processor to implement the steps of the method of any one of claims 1-5.

9. An electronic device, comprising: The program is executed by the processor to implement the steps of the method of any one of claims 1-5. The program is executed by the processor to implement the steps of the method of any one of claims 1-5. The program is executed by the processor to implement the steps of the method of any one of claims 1-5. The program is executed by the processor to implement the steps of the method of any one of claims 1-5.

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