Neutron dose evaluation method and system based on mobile phone neutron activation product analysis

Abstract

The application provides a neutron dose evaluation method and system based on mobile phone neutron activation product analysis. The neutron dose evaluation method based on mobile phone neutron activation product analysis of the application is characterized in that: an equivalent medium model is constructed to replace a real mobile phone, and a mobile phone activation product is used to solve a neutron energy spectrum. The neutron energy spectrum can be reconstructed on site in daily scenes such as villages, streets and shopping malls without professional equipment, so that the individual dose uncertainty is reduced to the level of a laboratory spectrometer, the dependence on a multi-sphere spectrometer, a TOF spectrometer and professionals is completely eliminated, the rapid and accurate measurement of the neutron energy spectrum is realized, and large-scale population dose evaluation is realized, which provides a basis for delineating the influence range of a nuclear event, determining the event level of a nuclear event and formulating a graded medical rescue scheme.

Description

Technical Field

[0001] This invention relates to the technical field of nuclear technology applications, and more specifically, to a neutron dose assessment method and system based on the analysis of neutron activation products in mobile phones. Background Technology

[0002] In the event of a nuclear accident or disaster, rapid and accurate assessment of the neutron dose to exposed individuals is crucial for determining radiation damage and guiding medical treatment.

[0003] Neutron dose assessment is based on the principle of neutron activation. When a substance is irradiated by neutrons, its nuclides undergo reactions such as (n,γ), (n,p), and (n,α) to generate induced radionuclides. By measuring the activity of these induced radionuclides and combining this with the neutron energy spectrum, reaction cross section, irradiation history, and geometric conditions, the neutron fluence and individual dose equivalent can be deduced based on the neutron dose conversion coefficients given in ICRP Publication 74 or ISO 8529-3. In the human body, induced radioactivity is generated simultaneously from both inherent nuclides within the body and from personal items. Among the inherent nuclides, sodium in human tissues... -23 When an element is irradiated by a neutron, it will produce the radioactive element sodium. -24 By using sodium -24 Analysis of the content can assess the neutron dose in the human body. However, there are drawbacks to performing biosampling of the human body itself or using a whole-body counter (WBC) or scanning bed detector array to perform in-situ whole-body measurements on the irradiated subject: 1) The sampling and measurement process is easily constrained by the on-site radiation environment, background level, spatial geometry, and time window; 2) The irradiated subject must cooperate closely and maintain a prescribed position or undergo invasive sampling, and their compliance directly affects the data quality; 3) In accident scenarios, if there is combined irradiation, surface contamination, or medical treatment interference, the uncertainty can be further increased and the measurement cycle can be prolonged. The drawbacks of carrying items are as follows: 1) Keys and watches are not essential for everyone, and their materials and shapes vary greatly, making it difficult to collect sufficient samples in a short period of time after an accident, which can easily lead to statistical omissions; 2) Keychains and watches are often placed in bags, on tabletops, or on parts of the body far from the torso, and their exposure angle and shielding thickness are inconsistent with the human torso, resulting in significant deviations in neutron energy spectrum and fluence distribution, making it impossible to represent the whole-body dose equivalently; 3) Keys and watches are mostly made of single alloys, with limited types of neutron activation products and a lack of multi-nucleon and multi-energy region responses; in cases where low-energy neutrons are dominant or the energy spectrum is complex, the number of resolvable characteristic peaks is insufficient, making it difficult to reconstruct the neutron energy spectrum using the multi-nucleon ratio method.

[0004] Therefore, there is an urgent need for a neutron dose assessment method applicable to everyday settings. Summary of the Invention

[0005] In view of the above problems, the purpose of this invention is to provide a neutron dose assessment method and system based on the analysis of neutron activation products in mobile phones, so as to solve at least one problem existing in the prior art.

[0006] In a first aspect, the present invention provides a neutron dose assessment method based on the analysis of neutron activation products in mobile phones, applied to electronic devices, including obtaining a mobile phone sample carried by an irradiated person and confirming the mobile phone model and type of the mobile phone sample; The activation measurement of the mobile phone sample was performed using a gamma spectrometer to determine the type of neutron activation products used for neutron despectroscopy in the mobile phone sample, thereby obtaining the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation and the measured activation reaction rate of each activation product. Using a particle transport simulation program, the activation reaction rate of each element in the equivalent medium model corresponding to the mobile phone model type of the mobile phone sample is simulated and calculated under a certain assumed neutron source irradiation condition; the calculated activation reaction rate of each element is compared with the measured activation reaction rate to obtain the ratio of the measured activation reaction rate to the calculated activation reaction rate. Based on the ratio of the measured activation reaction rate to the calculated activation reaction rate, the preset neutron energy spectrum corresponding to the preset neutron source irradiation conditions is corrected to obtain the corrected neutron energy spectrum; the final neutron energy spectrum is obtained based on the corrected neutron energy spectrum. Based on the final neutron energy spectrum, the neutron dose of the person irradiated corresponding to the mobile phone sample is obtained.

[0007] In addition, an optional technical solution is that the method for obtaining the equivalent medium model corresponding to the mobile phone model type of the mobile phone sample includes, We obtained mobile phone samples of various models and used a gamma spectrometer to obtain the background radiation data of the mobile phone samples of various models. Based on the background radiation data of the mobile phone sample and the pre-acquired peak areas of the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample, the net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample after neutron irradiation is obtained; wherein, the method for obtaining the peak area of ​​the gamma-ray characteristic peaks of the neutron-activated products of the mobile phone sample includes measuring the gamma energy spectrum of the pre-irradiated mobile phone sample using a gamma spectrometer, determining the type of neutron-activated product of each model of mobile phone sample by characteristic gamma-ray energy, and recording the peak area of ​​the characteristic peaks of the neutron-activated products; the pre-irradiated mobile phone sample is the mobile phone sample irradiated with a neutron source with known energy spectrum distribution and intensity. Measure the geometric parameters of the mobile phone sample and establish a geometric three-dimensional model of the mobile phone sample; Based on the types of neutron activation products of the mobile phone sample, the elemental types of the mobile phone sample are determined; and an initial content is assigned to each element of the mobile phone sample. Using a particle transport simulation program, an equivalent medium model of the mobile phone sample is established based on the geometric three-dimensional model of the mobile phone sample, the elements of the mobile phone sample, and the initial content of the elements.

[0008] In addition, alternative technical solutions are: The equivalent medium model is used as the initial equivalent medium model; Using a particle transport simulation program, the initial equivalent medium model of the mobile phone sample was simulated to be irradiated by a neutron source with the same energy spectrum distribution and intensity as the pre-irradiated mobile phone sample. Using a particle transport simulation program, the initial equivalent medium model after simulated irradiation was measured using a gamma spectrometer; and the peak areas of the gamma-ray characteristic peaks of each neutron activation product of the initial equivalent medium model were obtained. The initial equivalent medium model is modified based on the ratio of the peak area of ​​the gamma-ray characteristic peak of each neutron-activated product in the initial equivalent medium model to the net peak area of ​​the gamma-ray characteristic peak of each neutron-activated product in the neutron-irradiated mobile phone sample, thereby obtaining a modified initial equivalent medium model; the final equivalent medium model of the mobile phone sample is obtained based on the modified initial equivalent medium model.

[0009] In addition, alternative technical solutions are: Based on a multi-parameter global optimization algorithm, the content of each element in the modified initial equivalent medium model is corrected using a particle transport simulation program to obtain the final equivalent medium model of the mobile phone sample.

[0010] In addition, alternative technical solutions are: A method for correcting the initial equivalent medium model based on the ratio of the peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product in the initial equivalent medium model to the net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product in the neutron-irradiated mobile phone sample includes the following: set up ,in, The peak area of ​​the gamma-ray characteristic peaks of each neutron activation product in the initial equivalent medium model; The net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample after neutron irradiation. When 0.99≤r≤1.01, the initial equivalent medium model is determined to meet the error requirements of the element content of the equivalent medium model; the initial equivalent medium model is used as the equivalent medium model of the final mobile phone sample. When r>1.01 or r<0.99, it is determined that the initial equivalent medium model does not meet the error requirements of the element content of the equivalent medium model; the initial content of each element in the initial equivalent medium model is corrected by the following formula to obtain the content of each element, and then the corrected initial equivalent medium model is obtained. .

[0011] In addition, alternative technical solutions are: The initial total activity of all types of neutron activation products of the mobile phone sample at the end of neutron irradiation was obtained by the following formula:

[0012] in, The initial total activity of all types of neutron activation products in the mobile phone sample at the moment the neutron irradiation ends; The mobile phone sample carried by the person being irradiated; Indicates the phone model type; The moment when the person being irradiated by neutrons ends; t 1 ＇ The moment when the measurement of the mobile phone sample begins; t 2 ＇ This refers to the moment when the measurement of the mobile phone sample ends; For record t 2 ＇— t 1 ＇ The mobile phone samples obtained during the time period were measured. Phone(i)' Counting of gamma-ray characteristic peaks of neutron-activated products; λ j For the first j The decay constant of each activated product; R j For the first j The branching ratio of the gamma rays of the activated product to be tested; k j For the gamma spectrometer to the first j The detection efficiency of the gamma rays to be tested for each activated product; The end time of irradiation Then, at the measurement time t 2 ＇— t 1 ＇ The proportion of activated products that decreases due to the decay of activated products over a period of time.

[0013] In addition, alternative technical solutions are: The activation reaction rate is obtained by the following formula:

[0014] in, To measure the activation reaction rate; The initial total activity of all types of neutron activation products in the mobile phone sample at the moment the neutron irradiation ends; The content of each element in the equivalent medium model; For elements x atomic weight.

[0015] Secondly, the present invention also provides a neutron dose assessment system based on the analysis of neutron activation products in mobile phones. The system includes: a sample acquisition unit for acquiring a mobile phone sample carried by an irradiated person and confirming the mobile phone model and type of the mobile phone sample. The energy spectrum acquisition unit is used to perform activation measurements on the mobile phone sample using a gamma spectrometer, determine the types of neutron activation products used for neutron spectroscopy in the mobile phone sample, and then obtain the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation and the measured activation reaction rate of each activation product; using a particle transport simulation program, it simulates and calculates the activation reaction rate of each element in an equivalent medium model corresponding to a pre-set mobile phone model type of the mobile phone sample under a certain hypothetical neutron source irradiation condition; compares the calculated activation reaction rate of each element with the measured activation reaction rate to obtain the ratio of the measured activation reaction rate to the calculated activation reaction rate; based on the ratio of the measured activation reaction rate to the calculated activation reaction rate, it corrects the pre-set neutron energy spectrum corresponding to the pre-set neutron source irradiation condition to obtain the corrected neutron energy spectrum; and obtains the final neutron energy spectrum based on the corrected neutron energy spectrum. The neutron dose acquisition unit is used to obtain the neutron dose of the person being irradiated corresponding to the mobile phone sample based on the final neutron energy spectrum.

[0016] Thirdly, the present invention provides an electronic device, the electronic device including a memory, a processor, and a neutron dose assessment program based on mobile phone neutron activation product analysis stored in the memory and executable on the processor, wherein when the neutron dose assessment program based on mobile phone neutron activation product analysis is executed by the processor, the neutron dose assessment method based on mobile phone neutron activation product analysis as described above is implemented.

[0017] Fourthly, the present invention provides a computer-readable storage medium storing a computer program, which, when executed by a processor, implements the neutron dose assessment method based on mobile phone neutron activation product analysis as described above.

[0018] This invention discloses a neutron dose assessment method, system, and storage medium based on the analysis of neutron activation products in mobile phones. The method, which constructs an equivalent medium model to replace a real mobile phone and uses the activation products to solve for the neutron spectrum, allows for on-site reconstruction of neutron spectra in everyday settings without specialized equipment, such as rural areas, streets, and shopping malls. This reduces individual dose uncertainty to a level comparable to laboratory spectrometers, completely eliminating reliance on multi-sphere spectrometers, TOF spectrometers, and professional personnel, enabling rapid and accurate measurement of neutron spectra. Furthermore, by constructing equivalent medium models for various mobile phone models, the method determines the elemental composition and activation reaction cross-section of each model in one step. This eliminates the need for disassembly and quantification, accurately reproducing the entire process of neutron moderation, absorption, and subsequent activation, providing a unified and reusable model foundation for spectrum interpretation. Additionally, it allows for parallel and rapid large-scale population dose assessment, providing a basis for delineating the impact range of nuclear events, determining the event level, and developing tiered medical rescue plans.

[0019] To achieve the foregoing and related objectives, one or more aspects of the invention include the features that will be described in detail below. The following description and accompanying drawings illustrate certain exemplary aspects of the invention. However, these aspects indicate only a few of the various ways in which the principles of the invention can be used. Furthermore, the invention is intended to encompass all such aspects and their equivalents. Attached Figure Description

[0020] Other objects and results of the invention will become more apparent and readily understood with reference to the following description taken in conjunction with the accompanying drawings. In the drawings: Figure 1 This is a flowchart illustrating a neutron dose assessment method based on mobile phone neutron activation product analysis according to an embodiment of the present invention. Figure 2-1 shows the gamma spectrum of the activated product after irradiating the iPhone 15 Pro Max mobile phone sample with a californium-252 neutron source in Example 1. Figure 2-2 shows the gamma spectrum of the activated product after irradiating the mobile phone sample xiaomin14 with the Californium-252 neutron source in Example 1. Figure 3 This is a comparison diagram of the reconstructed energy spectrum and the actual neutron energy spectrum in Embodiment 1 of the present invention; Figure 4 This is a schematic diagram of the modules of a neutron dose assessment system based on mobile phone neutron activation product analysis provided in an embodiment of the present invention; Figure 5 This is a schematic diagram of the internal structure of an electronic device that implements a neutron dose assessment method based on the analysis of neutron activation products in a mobile phone, according to an embodiment of the present invention.

[0021] In all the accompanying drawings, the same reference numerals indicate similar or corresponding features or functions. Detailed Implementation

[0022] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, 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, 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.

[0023] The technical solutions in the embodiments of this application will be clearly and thoroughly described below with reference to the accompanying drawings. In the description of the embodiments of this application, unless otherwise stated, the word "and / or" in the text is merely a description of the relationship between related objects, indicating that three relationships can exist. For example, A and / or B can represent: A existing alone, A and B existing simultaneously, and B existing alone.

[0024] Hereinafter, the terms "first" and "second" are used for descriptive purposes only and should not be construed as implying or suggesting relative importance or implicitly indicating the number of indicated technical features. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. Furthermore, in the description of embodiments in this application, "multiple" refers to two or more.

[0025] References to "one embodiment" or "some embodiments" as described in this specification mean that one or more embodiments of this application include a specific feature, structure, or characteristic described in connection with that embodiment. Therefore, the phrases "in one embodiment," "in some embodiments," "in other embodiments," "in still other embodiments," etc., appearing in different parts of this specification do not necessarily refer to the same embodiment, but rather mean "one or more, but not all, embodiments," unless otherwise specifically emphasized. The terms "comprising," "including," "having," and variations thereof mean "including but not limited to," unless otherwise specifically emphasized.

[0026] To provide a detailed description of the neutron dose assessment method, system, and storage medium based on mobile phone neutron activation product analysis of the present invention, specific embodiments of the present invention will be described in detail below with reference to the accompanying drawings.

[0027] A gamma-ray spectrometer is a measurement system consisting of a radiation detector, a charge-sensitive preamplifier, a main amplifier, a multichannel pulse amplitude analyzer (MCA), and energy and efficiency calibration software. It records and analyzes the pulse amplitude spectrum of gamma rays (including characteristic X-rays) in the energy range of 0.01–10 MeV, thereby enabling nuclide identification and activity quantification. Detector types include, but are not limited to: coaxial high-purity germanium (HPGe), planar low-energy germanium (LEGe), cadmium zinc telluride (CZT) semiconductor arrays, lanthanum bromide (LaBr3:Ce), and lanthanum chloride (LaCl3:Ce) inorganic scintillators. It should be noted that when used for activation product analysis, a standard source (such as...) must be used. 152 Eu、 60 Co、 137 The energy-efficiency scale is performed using Cs, and cascade coincidence additive correction is considered. In this invention, a high-purity germanium detector is preferably selected for the gamma spectrometer.

[0028] Particle transport simulation programs: These are computer software programs that solve linear Boltzmann transport equations based on Monte Carlo or deterministic methods. They can track the motion, scattering, absorption, and secondary particle generation processes of neutrons, photons, electrons, protons, and other heavy ions in complex three-dimensional geometries, outputting physical quantities such as fluence, energy deposition, and dose equivalent. Common and experimentally validated programs include MCNP®6, PHITS3, Geant4, FLUKA, Serpent, and OpenMC.

[0029] The technical drawbacks of using existing technologies to measure neutron dose based on mobile phones are as follows: 1) The types and contents of metal elements in different mobile phone models vary significantly, and the types and yields of neutron activation products produced by different metal element types and contents are also different; therefore, it is necessary to disassemble the mobile phone and quantify it first by means of mass spectrometry, spectroscopy or chemical titration, which is a cumbersome and costly process; 2) The slowing down and absorption of neutrons by different models are different, causing the internal neutron energy spectrum to deviate from the incident spectrum, making it difficult to uniformly correct the self-absorption effect; that is, if the neutron energy spectrum of the incident neutron is solved by the content of activation products of the mobile phone, it is difficult to quantify and correct the different degrees of neutron self-absorption for different mobile phone models, which increases the uncertainty of neutron dose assessment; 3) The self-shielding of activated gamma rays by the mobile phone structure also varies with the elemental composition and gamma energy, which cannot be accurately corrected, all of which significantly increase the uncertainty of dose assessment.

[0030] This invention presents a neutron dose assessment method based on the analysis of neutron activation products in mobile phones. Through neutron irradiation experiments and particle transport simulations, an equivalent medium model is constructed to replace the actual mobile phone. This model determines the elemental composition and activation reaction cross-section of each phone model in one step, eliminating the need for disassembly and quantification, and accurately reproducing the entire process of neutron moderation, absorption, and subsequent activation. This provides a unified and reusable model foundation for spectral analysis. Furthermore, the neutron energy spectrum is solved using the activation products of the mobile phone. Based on pre-established equivalent medium models of different mobile phone models, particle transport simulation is used to perform repeated simulations and calculations, and the final neutron energy spectrum is determined through certain evaluation criteria. Unlike iterative principles, this method comprehensively considers the generation process of activation products in different mobile phone models under different neutron irradiation conditions, including the self-absorption of neutrons and the self-shielding effect on the gamma rays emitted by the activation products. This solves the problem of the difficulty in quantifying the self-absorption and self-shielding effects in the neutron spectral analysis process using mobile phone activation products.

[0031] Example 1 Figure 1 A flowchart of a neutron dose assessment method based on mobile phone neutron activation product analysis according to an embodiment of the present invention is shown.

[0032] like Figure 1 As shown, the neutron dose assessment method based on mobile phone neutron activation product analysis in this embodiment of the invention includes steps S110-S150.

[0033] Specifically, S110: Obtain a mobile phone sample carried by the person being irradiated, and confirm the mobile phone model and type of the mobile phone sample.

[0034] Obtain mobile phone samples after neutron irradiation; that is, obtain mobile phones worn close to the body that can reflect the degree of individual exposure during a nuclear event. Record the mobile phone samples carried by the irradiated individuals. in, i This indicates the mobile phone model type. Specifically, it utilizes the principle that induced gamma rays (i.e., neutron activation reactions) are generated by the interaction of neutrons of different energies with matter. Neutron energy spectrum reconstruction is performed by measuring the characteristic energy and intensity of induced gamma rays from the material at the location of the irradiated person (in this embodiment, the material is a metal element in the mobile phone capable of generating an activation reaction). Nuclear event, in the IAEA International Nuclear and Radiation Event Scale (INES), is a broad term encompassing deviations from Level 0 ("no safety significance"), major nuclear accidents of ≥ Level 4 (INES), and catastrophic nuclear disasters of Level 7 (INES).

[0035] In the specific implementation process, the mobile phone model can be iPhone 14 Pro, Samsung Galaxy S23, Huawei Mate 50 Pro, Xiaomi 13, OPPO Find X6, etc.

[0036] It should be noted that mobile phones have four major advantages, making them ideal "portable activation detectors" for assessing human neutron dose in nuclear accident scenarios: 1) Standardized specifications: Mobile phones of the same model have highly consistent size, elemental composition, and content, facilitating accurate measurement of activation products. 2) High availability: Mobile phones are portable devices that can be obtained immediately after a disaster. 3) Personal representation: The energy spectrum reconstructed using a portable mobile phone directly reflects an individual's exposure environment, providing a more realistic dose assessment. 4) Multi-element response: Elements such as Fe, Al, Ti, Co, Ni, Cu, Li, and Mn cover multiple activation reactions from thermal neutrons to the MeV energy range, allowing for simultaneous analysis of information from various energy segments of the energy spectrum.

[0037] S120. Activation measurements are performed on the mobile phone sample using a gamma spectrometer to determine the types of neutron activation products used for neutron spectroscopy in the mobile phone sample. This yields the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation, as well as the measured activation reaction rate of each activation product. The measured activation reaction rate of each element is the initial total activity of each activation product in the mobile phone sample divided by the number of atoms of the corresponding activation element in the equivalent medium model corresponding to the mobile phone model.

[0038] In the process of determining the types of neutron activation products used for neutron spectrum interpretation by performing activation measurements on the mobile phone sample using a gamma spectrometer, a high-purity germanium detector is used to analyze the collected mobile phone sample to determine the types of activation products used for neutron spectrum interpretation; that is, for the mobile phone sample... Phone(i)' Gamma spectroscopy measurements are performed, and based on the characteristic peak energies, automatic peak finding and nuclide identification are conducted to identify and quantify the types (categories) of neutron activation products used for neutron spectrum interpretation.

[0039] Specifically, assuming the start time of the neutron irradiation on the irradiated person is 0, the end time of the neutron irradiation on the irradiated person is... The time when the mobile phone sample began measurement was... t 1 ＇ The time when the measurement of the mobile phone sample ended was... t 2 ＇ ;Record t 2 ＇— t 1 ＇ During the time period, the mobile phone sample Phone(i)' Counting of gamma-ray characteristic peaks of neutron-activated products It should be noted that the count of the gamma-ray characteristic peaks of the neutron-activated products is the net area obtained using a high-purity germanium detector.

[0040] The initial total activity of all types of neutron activation products of the mobile phone sample at the end of neutron irradiation was obtained. This can be achieved through the following formula:

[0041] The mobile phone sample carried by the person being irradiated; λ j For the first j The decay constant of each activated product; R j For the first j The branching ratio of the gamma rays of the activated product to be tested; k j For the gamma spectrometer to the first j The detection efficiency of the gamma rays to be tested for each activated product; The end time of irradiation Then, at the measurement time t 2 ＇— t 1 ＇ The proportion of activated products that decreases due to the decay of activated products over a period of time.

[0042] S130. Using a particle transport simulation program, simulate and calculate the activation reaction rate of each element in the equivalent medium model corresponding to the mobile phone model type of the mobile phone sample under a certain assumed neutron source irradiation condition; compare the calculated activation reaction rate of each element with the measured activation reaction rate to obtain the ratio of the measured activation reaction rate to the calculated activation reaction rate.

[0043] Different mobile phone models have significant differences in the types and contents of metal elements, and the types and yields of neutron activation products produced by these differences also vary. Therefore, it is necessary to first disassemble the mobile phone and quantify it using mass spectrometry, spectroscopy, or chemical titration, which is a cumbersome and costly technical problem. This invention constructs an equivalent medium model to replace the real mobile phone through neutron irradiation experiments and particle transport simulation, which determines the elemental composition and activation reaction cross section of each model in one go. This not only saves the need for disassembly and quantification, but also accurately reproduces the entire process of neutron moderation, absorption, and subsequent activation, providing a unified and reusable model basis for spectral interpretation.

[0044] The method for obtaining the equivalent medium model corresponding to the mobile phone model type of the mobile phone sample includes the following steps: S1301. Obtain mobile phone samples of various mobile phone models and use a gamma spectrometer to obtain the background radiation data of each mobile phone sample.

[0045] Collect mobile phone samples of different models; different models of mobile phone samples are used for... Phone(i) Let i = 1, 2, ..., p represent the values ​​of i, 2, ..., p. i This indicates the type of mobile phone model.

[0046] A mobile phone sample was measured using a high-purity germanium detector. Phone(i) Background radiation data B K （i） , i=1,2,…p; where, i This indicates the mobile phone model. The duration of the background radiation measurement is... t b .

[0047] It should be noted that the self-shielding effect of gamma rays emitted by mobile phone activation products varies depending on the elemental composition, density, and gamma energy of the phone model, making it difficult to uniformly correct. Specifically, the gamma rays emitted by the activation products of mobile phones are shielded by the phone itself, resulting in a self-shielding effect. This self-shielding effect is directly related to the differences in elemental types and densities caused by different phone models, as well as the energy of the gamma rays emitted by the activation products. Based on the construction of equivalent medium models corresponding to various mobile phone models, this invention further improves the accuracy of these models by using background radiation data to correct the self-shielding effect for different mobile phone models.

[0048] S1302. Based on the background radiation data of the mobile phone sample and the peak areas of the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample obtained in advance, the net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample after neutron irradiation is obtained; wherein, the method for obtaining the peak area of ​​the gamma-ray characteristic peaks of the neutron-activated products of the mobile phone sample includes measuring the gamma energy spectrum of the pre-irradiated mobile phone sample using a gamma spectrometer, determining the type of neutron-activated product of each model of mobile phone sample by characteristic gamma-ray energy, and recording the peak area of ​​the characteristic peaks of the neutron-activated products; the pre-irradiated mobile phone sample is the mobile phone sample irradiated with a neutron source with known energy spectrum distribution and intensity.

[0049] S13021. The mobile phone sample is irradiated with a neutron source with known energy spectrum distribution and intensity to obtain a pre-irradiated mobile phone sample Phone(i). The start time of the neutron irradiation of mobile phone sample Phone(i) is... The end time of neutron irradiation is The irradiation geometry of neutron irradiation is denoted as Geometry(i).

[0050] S13022. Using a high-purity germanium detector, the measurement of a mobile phone sample Phone(i) begins at time t2(i) and ends at time t3(i), where t3(i) - t2(i) = t b .

[0051] S13023. Based on the gamma energy spectrum of the mobile phone sample Phone(i) after neutron irradiation measured using a high-purity germanium detector, the types of neutron activation products of different mobile phone models are determined by the characteristic gamma ray energies; and the peak area Area(phone(i),j) of the gamma ray characteristic peak of the neutron activation product of each mobile phone model is recorded.

[0052] For example, elements in a mobile phone can obtain corresponding neutron-activated products through activation reactions; the types of activation products can be: 58Fe(n,γ)59Fe, 56Fe(n,p)56Mn, 54Fe(n,p)54Mn, 27Al(n,γ)28Al, 27Al(n,α)24Na, 47Ti(n,p)47Sc, 59Co(n,γ)60Co, 59Co(n,a)56Mn, 60Ni(n,p)60Co, 65Cu(n,γ)66Cu, 63Cu(n,γ)64Cu, 63Cu(n,a)60Co, 7Li(n,γ)8Li, 55Mn(n,γ)56Mn.

[0053] Area(phone(i),j) represents the area after neutron irradiation, within a measurement time period (t). b Within the range, the peak area of ​​the gamma-ray characteristic peak of the j-th neutron-activated product of the mobile phone sample phone(i) is Area(phone(i),j), where j=1,2,……n.

[0054] S13024, Based on the background radiation data B of the mobile phone sample K (i) and the peak area Area(phone(i),j) of each neutron-activated product of the pre-acquired mobile phone sample, to obtain the net peak area of ​​each neutron-activated product of the mobile phone sample after neutron irradiation.

[0055] The net peak area of ​​the gamma-ray characteristic peaks of each activation product in the phone sample Phone(i) after neutron irradiation is obtained using the following formula: Area'(phone(i),j). Where Area'(phone(i),j) = Area(phone(i),j) - B K (i).

[0056] S1303. Measure the geometric parameters of the mobile phone sample and establish a geometric three-dimensional model of the mobile phone sample.

[0057] The length, width, and height of the mobile phone sample Phone(i) are measured to establish a geometric model Size(i) for the mobile phone sample. The geometric 3D model refers to a 3D solid mesh or CSG model that can be used for particle transport calculations, reconstructed using CAD or Monte Carlo preprocessing software by acquiring characteristic dimensions on the outer contour of the actual mobile phone sample using mathematical surfaces (planes, cylinders, spheres, NURBS, etc.) to perform preprocessing. This model provides unique and repeatable geometric input for gamma-ray self-shielding correction and neutron spectrum dissection.

[0058] S1304. Determine the element types of the mobile phone sample based on the types of neutron activation products of the mobile phone sample; and assign an initial content to each element of the mobile phone sample.

[0059] Based on the gamma spectrum of the phone sample Phone(i) after neutron irradiation measured using a high-purity germanium detector in step S13023, the type of neutron activation product Element(phone(i),x) of different models of phone samples is determined by the characteristic gamma ray energy. Here, Element(phone(i),x) represents the x-th element of the phone sample Phone(i); x=1,2,……

[0060] Assign initial weights to each element of Element(phone(i), x). [0] (phone(i),x) represents the initial content of the x-th element in the phone sample Phone(i).

[0061] S1305. Using a particle transport simulation program, based on the geometric three-dimensional model of the mobile phone sample, the elements of the mobile phone sample, and the initial content of the elements, establish an equivalent medium model of the mobile phone sample.

[0062] Based on the geometric three-dimensional model Size(i) of the mobile phone sample, the x-th element Element(phone(i),x) of the mobile phone sample Phone(i), and the initial content Weight of the x-th element of the mobile phone sample Phone(i). [0] (phone(i),x) is used to establish an equivalent medium model of the mobile phone sample Phone(i) using a particle transport simulation program.

[0063] In one specific embodiment, in order to further improve the accuracy of the equivalent medium model, the influence of the content of a single element on the peak area of ​​the gamma-ray characteristic peak of the corresponding activation product was considered, and the element content of the mobile phone sample was adjusted; specifically, the equivalent medium model was corrected through the following steps.

[0064] S13061. The equivalent medium model is used as the initial equivalent medium model. The initial equivalent medium model Model(0) of the mobile phone sample Phone(i) is Model(i). [0] { phone(i), Size(i), Weight [0] (phone(i),x)}.

[0065] S13062. Using a particle transport simulation program, simulate the initial equivalent medium model of the mobile phone sample being irradiated by a neutron source with the same energy spectrum distribution and intensity as the pre-irradiated mobile phone sample. The energy spectrum distribution and intensity of the neutron irradiation are the same as those in the step of measuring the gamma spectrum of the pre-irradiated mobile phone sample using a gamma spectrometer and determining the types of neutron activation products for each model of mobile phone sample through characteristic gamma ray energy.

[0066] Using a particle transport simulation program, the initial equivalent medium model of the mobile phone sample Phone(i) was simulated. [0] {phone(i), Size(i), Weight [0] The phone sample (phone(i),x)} is irradiated by a neutron source with the same irradiation conditions as in step S1321. That is, the start time of neutron irradiation for the phone sample Phone(i) is t0, and the end time of neutron irradiation is t1. The irradiation geometry of the neutron irradiation is Geometry(i).

[0067] S13063. Using a particle transport simulation program, the initial equivalent medium model after simulated irradiation is measured using a simulated gamma spectrometer; and the peak areas of the gamma-ray characteristic peaks of each neutron activation product of the initial equivalent medium model are obtained.

[0068] Using a particle transport simulation program, the initial equivalent medium model after irradiation was simulated using a high-purity germanium detector. [0] { phone(i), Size(i), Weight [0] The measurement is performed on (phone(i),x)} under the same conditions as in step S1322. Specifically, the measurement of the mobile phone sample Phone(i) using a high-purity germanium detector begins at time t2(i) and ends at time t3(i), where t3(i) - t2(i) = t b .

[0069] Based on the simulation results above, record the peak areas of the gamma-ray characteristic peaks of each neutron activation product in the initial equivalent medium model Model(0): Area [0] (phone(i),j).

[0070] S13064. Based on the ratio of the peak area of ​​the gamma-ray characteristic peak of each neutron-activated product in the initial equivalent medium model to the net peak area of ​​the gamma-ray characteristic peak of each neutron-activated product in the mobile phone sample after neutron irradiation, the initial equivalent medium model is corrected to obtain a corrected initial equivalent medium model; based on the corrected initial equivalent medium model, the final equivalent medium model of the mobile phone sample is obtained.

[0071] Specifically, the method for correcting the initial equivalent medium model based on the ratio of the peak area of ​​the gamma-ray characteristic peak of each neutron-activated product of the initial equivalent medium model to the net peak area of ​​the gamma-ray characteristic peak of each neutron-activated product of the mobile phone sample after neutron irradiation, includes the following steps.

[0072] set up ,in, The peak area of ​​the gamma-ray characteristic peaks of each neutron activation product in the initial equivalent medium model; This represents the net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample after neutron irradiation. Area'(phone(i),j) In step S1324, the net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample after neutron irradiation is obtained.

[0073] When 0.99≤r≤1.01, the initial equivalent medium model is determined to meet the error requirements of the element content of the equivalent medium model; the initial equivalent medium model is used as the equivalent medium model of the final mobile phone sample.

[0074] When r>1.01 or r<0.99, it is determined that the initial equivalent medium model does not meet the error requirements of the element content of the equivalent medium model; the initial content of each element in the initial equivalent medium model is corrected by the following formula to obtain the content of each element, and then the corrected initial equivalent medium model is obtained. .

[0075] In other words, the existing weight [0] The value of (phone(i),x) is corrected to: Weight [0] (phone(i),x) / r, and reassign the corrected value to Weight. [0] (phone(i),x) is used to obtain the corrected initial equivalent medium model. The corrected initial equivalent medium model is then used as the final equivalent medium model Model(i) for the mobile phone sample.

[0076] As a further improvement to this embodiment, it also includes S13065, using a multi-parameter global optimization algorithm and a particle transport simulation program to correct the content of each element in the modified initial equivalent medium model, thereby obtaining the final equivalent medium model of the mobile phone sample.

[0077] In other words, the methods in steps S13061-S13064 only roughly estimate the elemental content of the mobile phone sample; during the correction process, only the influence of the content of a single element on the peak area of ​​the corresponding activation product gamma-ray characteristic peak is considered, without considering the coupling effect between multiple elements. This coupling effect is mainly because changes in the content of a single element will cause changes in the density of the entire mobile phone medium, thereby affecting the neutron energy spectrum entering the mobile phone sample, which in turn affects the peak area of ​​the characteristic gamma-ray peaks of all activation products. Therefore, it is necessary to use a multi-parameter global optimization algorithm, combined with feedback from particle transport simulation calculations, to simultaneously adjust the content of each element in the mobile phone sample, so that the peak area of ​​the characteristic gamma-ray peaks of the activation products after irradiation of the equivalent medium model is as consistent as possible with that of the real mobile phone sample. In the specific implementation process, the equivalent medium model can be modified by steps S13061-S13064 alone, or the equivalent medium model can be modified by the multi-parameter global optimization algorithm based on S13065 alone. Alternatively, the equivalent medium model can be modified by steps S13061-S13064 first, and then the equivalent medium model can be further modified by the multi-parameter global optimization algorithm based on S13065.

[0078] It should be noted that multi-parameter global optimization algorithms can be implemented using genetic algorithms (GA), particle swarm optimization (PSO), simulated annealing (SA), differential evolution (DE), Bayesian optimization, covariance matrix adaptive evolution (CMA-ES), etc., to achieve global optimization of the element content of mobile phone samples, without specific limitations.

[0079] In summary, this invention constructs an equivalent medium model to replace a real mobile phone. Through joint calibration using neutron irradiation experiments and particle transport simulations, it determines the elemental composition and activation reaction cross-section of each phone model in one go. This eliminates the need for disassembly and quantitative analysis, and accurately reproduces the entire process of neutron moderation, absorption, and subsequent activation, providing a unified and reusable model foundation for spectral analysis. Constructing equivalent medium models for each mobile phone model provides a basis for solving neutron energy spectra and assessing neutron doses after a nuclear disaster, before such an event occurs.

[0080] After using the equivalent medium model Model(i) obtained in the above steps, the ratio of the calculated activation reaction rate to the measured activation reaction rate is obtained through steps S131-S133.

[0081] Specifically, the activation reaction rate is measured after the mobile phone is actually irradiated. First, the initial total activity of each activation product of the mobile phone is measured using a gamma spectrometer (since the initial total activity is obtained from actual measurement, it is called the measured activation reaction rate). Then, this is divided by the number of atoms of the activation element corresponding to each activation product in the mobile phone sample (the number of atoms is determined by the elemental content in the equivalent medium model and calculated using Avogadro's constant). The activation reaction rate is calculated using a particle transport simulation program, simulating the equivalent medium model being irradiated by a hypothetical neutron source (i.e., a hypothetical neutron source with a certain spectral distribution). Because iterative methods are used to obtain a neutron source that more closely approximates the actual irradiation, the calculated activation reaction rate under the hypothetical neutron source irradiation condition after each iteration is compared to the measured activation reaction rate. The energy spectrum of the neutron source with the closest measured activation reaction rate is taken as the final spectral result.

[0082] S131. Using the equivalent medium model Model(i) obtained in the above steps, determine the weight of each element. [0] After (phone(i),x), the measured activation reaction rate of each element is calculated.

[0083]

[0084] in, To measure the activation reaction rate; The initial total activity of all types of neutron activation products in the mobile phone sample at the moment the neutron irradiation ends; The content of each element in the equivalent medium model; For elements x atomic weight.

[0085] S132. Using a particle transport simulation program, simulate and calculate the activation reaction rate A of each element in the equivalent medium model corresponding to the mobile phone model type of the mobile phone sample under a certain assumed neutral source irradiation condition.c (Phone(i)',j).

[0086] The activation reaction rate of each element in the equivalent medium model corresponding to the mobile phone model type of the preset mobile phone sample under a certain assumed neutron source irradiation condition is calculated through the following steps.

[0087] S1321. Assume that the energy spectrum of a hypothetical neutron source is divided into m groups, and the energy interval between each group is... ,Let W k Let W be the weight of the k-th group, and W k = Let k = 1, 2, 3...m. Let σ... j,k The average nuclear reaction cross section of the j-th element in the k-th group neutron energy interval is defined in the equivalent medium model Model(i) corresponding to the mobile phone model type of the mobile phone sample.

[0088] S1322. Randomly select m numbers between (0,1) and assign them the value R. k k=1,2,3……m; generate random numbers R k Convert as follows: R k '=W k × R k k = 1, 2, 3...m; where R k ' represents the neutron energy spectrum of the hypothetical neutron source.

[0089] S1323. Using a particle transport simulation program, simulate the equivalent medium model Model(i) subjected to a neutron energy spectrum of R. k The neutron source irradiates at time t0, and the irradiation ends at time t0'.

[0090] S1324. Establish the geometric model of the equivalent medium model Model(i) measured by the high-purity germanium detector, simulate the measurement of the equivalent medium model Model(i) using the high-purity germanium detector, and obtain the calculated activation reaction rate of each element: A c (Phone(i)',j). Where the simulation starts at time t1' and ends at time t2'.

[0091] Specifically, for example, in Monte Carlo software, the equivalent medium model corresponding to the mobile phone sample is combined with the high-purity germanium detector to build a three-dimensional CAD / CSG mesh according to the actual measurement layout (sample-detector distance, orientation, dead layer, end cap size, cold finger, shielding chamber structure), which is used to calculate the transport and activation reaction rate of neutrons in the equivalent medium model.

[0092] S133. Compare the calculated activation reaction rate of each element with the measured activation reaction rate to obtain the ratio of the measured activation reaction rate to the calculated activation reaction rate.

[0093] Calculate and measure the activation reaction rate With activation reaction rate A c (Phone(i)',j) The ratio is N.

[0094]

[0095] m represents the energy spectrum of the neutron source, which is divided into m groups, and n represents the number of neutron activation products; The numerator of the equation represents the summation of the measured activation rates for all activated products. Wherein, This represents the summation of the calculated activation rates for all activated products; where, Let be the average nuclear reaction cross section of the j-th element within the neutron energy interval of the k-th group. Neutron flux share of the kth energy group. The activation reaction rate of the j-th element is calculated under neutron irradiation conditions in all energy groups.

[0096] S140. Based on the ratio of the measured activation reaction rate to the calculated activation reaction rate, the preset neutron energy spectrum corresponding to the preset neutron source irradiation conditions is corrected to obtain the corrected neutron energy spectrum; the final neutron energy spectrum is obtained based on the corrected neutron energy spectrum.

[0097] Using the ratio N of the measured activation rate to the calculated activation rate, the neutron energy spectrum R of the hypothetical neutron source is analyzed. k After correction, the corrected neutron energy spectrum Φ(E)' is obtained. And Φ(E)' = N × R k ' / W k .

[0098] In the specific implementation process, in order to further improve the accuracy of the neutron energy spectrum, different Φ(E)' were obtained by repeated simulation calculations, and according to the evaluation criteria, the Φ(E)' that is closest to the actual neutron energy spectrum distribution of a nuclear accident or nuclear disaster was selected as the final neutron energy spectrum Φ(E).

[0099] S1401, Let H j This indicates the degree of difference between the calculated and measured values ​​of each activated product j. , j=1,2,3……n.

[0100] S1401. Let µ and ν represent the µ-th and v-th calculations, respectively. The condition for evaluating whether the µ-th calculation is closer to the actual neutron energy spectrum than the ν-th calculation is: [max| H j |] µ < [max |H j |] ν .

[0101] S1403. After multiple simulations and calculations, the final neutron energy spectrum Φ(E) is determined based on the evaluation conditions in step S1401.

[0102] Based on pre-established equivalent medium models of different mobile phone models, this method utilizes particle transport simulation to perform repeated simulations and calculates, then uses certain evaluation criteria to determine the final neutron energy spectrum. Unlike iterative methods, this approach comprehensively considers the generation process of activation products from different mobile phone models under neutron irradiation conditions of varying energies, including the self-absorption of neutrons and the self-shielding effect on the gamma rays emitted by the activation products. This solves the problem of quantifying the self-absorption and self-shielding effects during neutron spectrum interpretation using mobile phone activation products.

[0103] S150. Based on the final neutron energy spectrum, obtain the neutron dose of the person being irradiated corresponding to the mobile phone sample.

[0104] It should be noted that the neutron dose of the irradiated person corresponding to the machine sample can be obtained based on the neutron energy spectrum by using the fluence-dose conversion factor according to ICRP 74 or ISO 8529-3. Alternatively, the neutron energy spectrum Φ(E) can be input as a source term into an experimentally validated Monte Carlo program (MCNP / PHITS / Geant4) to calculate the dose equivalent at a depth of 10 mm on an ICRU sphere or voxel human model, and directly output the neutron dose.

[0105] Two mobile phone models, iPhone 15 Pro Max and Xiaomi 14, were irradiated with a californium-252 neutron source as neutron-irradiated phones. The initial total activity of each neutron activation product and the measured activation reaction rate of each activation product were measured using a high-purity germanium detector. Then, the energy spectrum was reconstructed using the neutron dose assessment method based on the analysis of mobile phone neutron activation products to obtain the neutron energy spectrum reconstructed based on iPhone 15 Pro Max and Xiaomi 14.

[0106] The neutron energy spectra reconstructed based on the iPhone 15 Pro Max and the Xiaomi 14 were compared with the actual neutron energy spectra. Figure 2-1 shows the gamma spectrum of the activated product after irradiating the iPhone 15 Pro Max sample with the californium-252 neutron source in Example 1; Figure 2-2 shows the gamma spectrum of the activated product after irradiating the Xiaomi 14 sample with the californium-252 neutron source in Example 1. Figure 3 The images shown are neutron spectra reconstructed from iPhone 15 Pro Max and Xiaomi 14 phones, compared with the original neutron spectra of Californium-252.

[0107] Through observation Figure 3 As can be seen, by measuring the activity of the neutron activation products of the two mobile phones and reconstructing the neutron energy spectrum, the trend of the actual neutron energy spectrum is basically consistent with that of the actual neutron energy spectrum, proving that the method proposed in this invention fully meets the accuracy requirements for neutron dose assessment under nuclear emergency situations.

[0108] The neutron dose assessment method based on mobile phone neutron activation product analysis of the present invention uses mobile phone as a "portable activation detector" to reconstruct neutron energy spectrum on-site in everyday scenarios without professional equipment, such as rural areas, streets, and shopping malls. This completely eliminates the dependence on multi-sphere spectrometers, TOF spectrometers, and professional personnel, and realizes rapid, accurate, and on-site measurement of neutron energy spectrum.

[0109] like Figure 4 As shown, this invention provides a neutron dose assessment system based on mobile phone neutron activation product analysis, which utilizes the previously described neutron dose assessment method based on mobile phone neutron activation product analysis. Depending on the functions implemented, the neutron dose assessment system 400 based on mobile phone neutron activation product analysis may include a sample acquisition unit 410, an energy spectrum acquisition unit 420, and a neutron dose acquisition unit 430. The unit in this invention can also be called a module, which refers to a series of computer program segments that can be executed by the processor of an electronic device and perform a fixed function, stored in the memory of the electronic device.

[0110] In this embodiment, the functions of each module / unit are as follows: The sample acquisition unit 410 is used to acquire a mobile phone sample carried by the irradiated person and to confirm the mobile phone model and type of the mobile phone sample. The energy spectrum acquisition unit 420 is used to perform activation measurements on the mobile phone sample using a gamma spectrometer, determine the types of neutron activation products used for neutron despectroscopy in the mobile phone sample, and then obtain the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation and the measured activation reaction rate of each activation product; using a particle transport simulation program, it simulates and calculates the activation reaction rate of each element in an equivalent medium model corresponding to a pre-set mobile phone model type of the mobile phone sample under a certain hypothetical neutron source irradiation condition; compares the calculated activation reaction rate of each element with the measured activation reaction rate to obtain the ratio of the measured activation reaction rate to the calculated activation reaction rate; based on the ratio of the measured activation reaction rate to the calculated activation reaction rate, it corrects the pre-set neutron energy spectrum corresponding to the pre-set neutron source irradiation condition to obtain the corrected neutron energy spectrum; and obtains the final neutron energy spectrum based on the corrected neutron energy spectrum. The neutron dose acquisition unit 430 is used to obtain the neutron dose of the person being irradiated corresponding to the mobile phone sample based on the final neutron energy spectrum.

[0111] The neutron dose assessment system based on mobile phone neutron activation product analysis of the present invention uses a mobile phone as a "portable activation detector" to reconstruct neutron energy spectrum on-site in everyday scenarios without professional equipment, such as rural areas, streets, and shopping malls. It completely eliminates the dependence on multi-sphere spectrometers, TOF spectrometers, and professional personnel, and realizes rapid and accurate measurement of neutron energy spectrum.

[0112] More specific implementations of the neutron dose assessment system based on mobile phone neutron activation product analysis can be found in the foregoing description of the embodiments of the neutron dose assessment method based on mobile phone neutron activation product analysis, and will not be detailed here.

[0113] like Figure 5 As shown, the present invention also provides an electronic device 1 based on a neutron dose assessment method for mobile phone neutron activation product analysis.

[0114] The electronic device 1 may include a processor 10, a memory 11, and a bus. It may also include a computer program stored in the memory 11 and executable on the processor 10, such as a neutron dose assessment program 12 based on mobile phone neutron activation product analysis. The memory 11 may include both internal storage units of the neutron dose assessment system based on mobile phone neutron activation product analysis and external storage devices. The memory 11 can be used not only to store application software and various types of data installed, such as the code of the neutron dose assessment program based on mobile phone neutron activation product analysis, but also to temporarily store data that has been output or will be output.

[0115] The memory 11 includes at least one type of readable storage medium, including flash memory, portable hard drive, multimedia card, card-type memory (e.g., SD or DX memory), magnetic memory, magnetic disk, optical disk, etc. In some embodiments, the memory 11 can be an internal storage unit of the electronic device 1, such as a portable hard drive. In other embodiments, the memory 11 can be an external storage device of the electronic device 1, such as a plug-in portable hard drive, smart media card (SMC), secure digital card (SD), flash card, etc., equipped on the electronic device 1. Furthermore, the memory 11 can include both internal and external storage units of the electronic device 1. The memory 11 can be used not only to store application software and various types of data installed on the electronic device 1, such as code for a single mechanical component life prediction program for aircraft, but also to temporarily store data that has been output or will be output.

[0116] In some embodiments, the processor 10 may be composed of integrated circuits, such as a single packaged integrated circuit or multiple integrated circuits with the same or different functions, including combinations of one or more central processing units (CPUs), microprocessors, digital processing chips, graphics processors, and various control chips. The processor 10 is the control unit of the electronic device, connecting various components of the entire electronic device through various interfaces and lines. It executes programs or modules stored in the memory 11 (e.g., a neutron dose assessment program based on mobile phone neutron activation product analysis) and calls data stored in the memory 11 to perform various functions of the electronic device 1 and process data.

[0117] The bus can be a peripheral component interconnect (PCI) bus or an extended industry standard architecture (EISA) bus, etc. This bus can be divided into an address bus, a data bus, a control bus, etc. The bus is configured to enable communication between the memory 11 and at least one processor 10, etc.

[0118] Figure 5 Only electronic devices with components are shown; it will be understood by those skilled in the art that... Figure 5The structure shown does not constitute a limitation on the electronic device 1, and may include fewer or more components than shown, or combine certain components, or have different component arrangements.

[0119] For example, although not shown, the electronic device 1 may also include a power supply (such as a battery) to power the various components. Preferably, the power supply can be logically connected to the at least one processor 10 through a power management system, thereby enabling functions such as charging management, discharging management, and power consumption management through the power management system. The power supply may also include one or more DC or AC power supplies, recharging systems, power fault detection circuits, power converters or inverters, power status indicators, and other arbitrary components. The electronic device 1 may also include various sensors, Bluetooth modules, Wi-Fi modules, etc., which will not be described in detail here.

[0120] Furthermore, the electronic device 1 may also include a network interface. Optionally, the network interface may include a wired interface and / or a wireless interface (such as a Wi-Fi interface, a Bluetooth interface, etc.), which is typically used to establish communication connections between the electronic device 1 and other electronic devices.

[0121] Optionally, the electronic device 1 may further include a user interface, which may be a display, an input unit (such as a keyboard), and optionally, a standard wired interface or a wireless interface. Optionally, in some embodiments, the display may be an LED display, a liquid crystal display, a touch-sensitive liquid crystal display, or an OLED (Organic Light-Emitting Diode) touchscreen, etc. The display may also be appropriately referred to as a screen or display unit, used to display information processed in the electronic device 1 and to display a visual user interface.

[0122] It should be understood that the embodiments described are for illustrative purposes only and are not limited to this structure in the scope of the patent application.

[0123] The neutron dose assessment program 12 based on mobile phone neutron activation product analysis, stored in the memory 11 of the electronic device 1, is a combination of multiple instructions. When run in the processor 10, it can: acquire a mobile phone sample carried by the irradiated person and confirm the mobile phone model and type; perform activation measurement on the mobile phone sample using a gamma spectrometer to determine the type of neutron activation products used for neutron despectroscopy in the mobile phone sample, thereby obtaining the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation and the measured activation reaction rate of each activation product; and simulate and calculate the pre-neutron dose assessment program using a particle transport simulation program. The activation reaction rate of each element in the equivalent medium model corresponding to the mobile phone model type of the mobile phone sample under a certain hypothetical neutron source irradiation condition is determined. The calculated activation reaction rate of each element is compared with the measured activation reaction rate to obtain the ratio of the measured activation reaction rate to the calculated activation reaction rate. Based on the ratio of the measured activation reaction rate to the calculated activation reaction rate, the preset neutron energy spectrum corresponding to the preset neutron source irradiation condition is corrected to obtain the corrected neutron energy spectrum. The final neutron energy spectrum is obtained based on the corrected neutron energy spectrum. Based on the final neutron energy spectrum, the neutron dose of the irradiated person corresponding to the mobile phone sample is obtained.

[0124] Specifically, the processor 10's implementation method for the above instructions can be found in [reference needed]. Figure 1 The descriptions of the relevant steps in the corresponding embodiments are not repeated here. Furthermore, if the modules / units integrated in the electronic device 1 are implemented as software functional units and sold or used as independent products, they can be stored in a computer-readable storage medium. The computer-readable medium may include: any entity or system capable of carrying the computer program code, a recording medium, a USB flash drive, a portable hard drive, a magnetic disk, an optical disk, a computer memory, or a read-only memory (ROM).

[0125] This invention also provides a computer-readable storage medium, which may be non-volatile or volatile. The storage medium stores a computer program that, when executed by a processor, performs the following: acquiring a mobile phone sample carried by an irradiated person and confirming the mobile phone model; performing activation measurements on the mobile phone sample using a gamma spectrometer to determine the types of neutron activation products used for neutron spectroscopy in the mobile phone sample, thereby obtaining the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation and the measured activation reaction rate of each activation product; and using a particle transport simulation program to simulate... The process involves calculating the activation rates of each element in an equivalent medium model corresponding to a pre-defined mobile phone model type under a hypothetical neutron source irradiation condition; comparing the calculated activation rates of each element with the measured activation rates to obtain the ratio of the measured to the calculated activation rates; correcting the pre-defined neutron energy spectrum corresponding to the pre-defined neutron source irradiation condition based on the ratio of the measured to the calculated activation rates to obtain the corrected neutron energy spectrum; obtaining the final neutron energy spectrum based on the corrected neutron energy spectrum; and obtaining the neutron dose for the irradiated person corresponding to the mobile phone sample based on the final neutron energy spectrum.

[0126] Specifically, the specific implementation method of the computer program when executed by the processor can be referred to the description of the relevant steps in the embodiment of the neutron dose assessment method based on the analysis of neutron activation products in mobile phones, and will not be repeated here.

[0127] In the several embodiments provided by this invention, it should be understood that the disclosed devices, systems, and methods can be implemented in other ways. For example, the system embodiments described above are merely illustrative; for instance, the division of modules is only a logical functional division, and other division methods may be used in actual implementation.

[0128] The modules described as separate components may or may not be physically separate. The components shown as modules may or may not be physical units; that is, they may be located in one place or distributed across multiple network units. Some or all of the modules can be selected to achieve the purpose of this embodiment according to actual needs.

[0129] Furthermore, the functional modules in the various embodiments of the present invention can be integrated into one processing unit, or each unit can exist physically separately, or two or more units can be integrated into one unit. The integrated unit can be implemented in hardware or in the form of hardware plus software functional modules.

[0130] It will be apparent to those skilled in the art that the present invention is not limited to the details of the exemplary embodiments described above, and that the present invention can be implemented in other specific forms without departing from the spirit or essential characteristics of the present invention.

[0131] Therefore, the embodiments should be considered exemplary and non-limiting in all respects, and the scope of the invention is defined by the appended claims rather than the foregoing description. Thus, all variations falling within the meaning and scope of equivalents of the claims are intended to be embraced within the invention. No appended diagram markings in the claims should be construed as limiting the scope of the claims.

[0132] Furthermore, it is clear that the word "comprising" does not exclude other units or steps, and the singular does not exclude the plural. Multiple units or systems stated in a system claim may also be implemented by a single unit or system through software or hardware.

[0133] However, those skilled in the art should understand that various modifications can be made to the neutron dose assessment method and system based on mobile phone neutron activation product analysis proposed in this invention without departing from the scope of the invention. Therefore, the scope of protection of this invention should be determined by the appended claims.

Claims

1. A neutron dose assessment method based on the analysis of neutron activation products in mobile phones, applied to electronic devices, characterized in that, include: Obtain a mobile phone sample carried by the person being irradiated, and confirm the model and type of the mobile phone sample; The activation measurement of the mobile phone sample was performed using a gamma spectrometer to determine the type of neutron activation products used for neutron despectroscopy in the mobile phone sample, thereby obtaining the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation and the measured activation reaction rate of each activation product. Using a particle transport simulation program, the calculated activation reaction rates of each element are calculated under a hypothetical neutron source irradiation condition using an equivalent medium model corresponding to the mobile phone model type of the mobile phone sample. The method for obtaining the equivalent medium model corresponding to the mobile phone model type includes acquiring mobile phone samples of various models and obtaining the background radiation data of each mobile phone sample using a gamma spectrometer. Based on the background radiation data of the mobile phone samples and the peak areas of the gamma-ray characteristic peaks of each neutron activation product of the pre-acquired mobile phone samples, the net peak area of ​​the gamma-ray characteristic peaks of each neutron activation product of the mobile phone samples after neutron irradiation is obtained. The method for obtaining the peak area of ​​the gamma-ray characteristic peaks of the neutron activation products of the mobile phone samples includes... The process includes: measuring the gamma spectrum of a pre-irradiated mobile phone sample using a gamma spectrometer; determining the types of neutron activation products for each model of mobile phone sample based on the characteristic gamma ray energies; recording the peak areas of the characteristic peaks of the neutron activation products; irradiating the pre-irradiated mobile phone sample using a neutron source with known energy distribution and intensity; measuring the geometric parameters of the mobile phone sample and establishing a geometric three-dimensional model of the mobile phone sample; determining the elemental types of the mobile phone sample based on the types of neutron activation products; assigning initial content to each element of the mobile phone sample; and using a particle transport simulation program, establishing an equivalent medium model of the mobile phone sample based on the geometric three-dimensional model of the mobile phone sample, the elements of the mobile phone sample, and the corresponding initial content of the elements. The calculated activation reaction rate of each element is compared with the measured activation reaction rate to obtain the ratio of the measured activation reaction rate to the calculated activation reaction rate. Based on the ratio of the measured activation reaction rate to the calculated activation reaction rate, the preset neutron energy spectrum corresponding to the preset neutron source irradiation conditions is corrected to obtain the corrected neutron energy spectrum. The final neutron energy spectrum is obtained based on the corrected neutron energy spectrum. Based on the final neutron energy spectrum, the neutron dose of the person irradiated corresponding to the mobile phone sample is obtained; The initial total activity of all types of neutron activation products of the mobile phone sample at the end of neutron irradiation was obtained by the following formula: in, The initial total activity of all types of neutron activation products in the mobile phone sample at the moment the neutron irradiation ends; The mobile phone sample carried by the person being irradiated; Indicates the phone model type; The moment when the person being irradiated by neutrons ends; t 1 ＇ The moment when the measurement of the mobile phone sample begins; t 2 ＇ This refers to the moment when the measurement of the mobile phone sample ends; For record t 2 ＇— t 1 ＇ The mobile phone samples obtained during the time period were measured. Phone(i)' Counting of gamma-ray characteristic peaks of neutron-activated products; λ j For the first j The decay constant of each activated product; R j For the first j The branching ratio of the gamma rays of the activated product to be tested; k j For the gamma spectrometer to the first j The detection efficiency of the gamma rays to be tested for each activated product; The end time of irradiation Then, at the measurement time t 2 ＇— t 1 ＇ The proportion of activated products that decreases due to the decay of activated products over a period of time.

2. The neutron dose assessment method based on mobile phone neutron activation product analysis according to claim 1, characterized in that, The equivalent medium model is used as the initial equivalent medium model; Using a particle transport simulation program, the initial equivalent medium model of the mobile phone sample was simulated to be irradiated by a neutron source with the same energy spectrum distribution and intensity as the pre-irradiated mobile phone sample. Using a particle transport simulation program, the initial equivalent medium model after simulated irradiation was measured using a gamma spectrometer; and the peak areas of the gamma-ray characteristic peaks of each neutron activation product of the initial equivalent medium model were obtained. Based on the ratio of the peak area of ​​the gamma-ray characteristic peak of each neutron-activated product in the initial equivalent medium model to the net peak area of ​​the gamma-ray characteristic peak of each neutron-activated product in the mobile phone sample after neutron irradiation, the initial equivalent medium model is corrected to obtain the corrected initial equivalent medium model. The final equivalent medium model of the mobile phone sample is obtained based on the modified initial equivalent medium model.

3. The neutron dose assessment method based on mobile phone neutron activation product analysis according to claim 2, characterized in that, Based on a multi-parameter global optimization algorithm, the content of each element in the modified initial equivalent medium model is corrected using a particle transport simulation program to obtain the final equivalent medium model of the mobile phone sample.

4. The neutron dose assessment method based on mobile phone neutron activation product analysis according to claim 2, characterized in that, A method for correcting the initial equivalent medium model based on the ratio of the peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product in the initial equivalent medium model to the net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product in the neutron-irradiated mobile phone sample includes the following: set up ,in, The peak area of ​​the gamma-ray characteristic peaks of each neutron activation product in the initial equivalent medium model; The net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone sample after neutron irradiation. When 0.99≤r≤1.01, the initial equivalent medium model is determined to meet the error requirements of the element content of the equivalent medium model; the initial equivalent medium model is used as the equivalent medium model of the final mobile phone sample. When r>1.01 or r<0.99, it is determined that the initial equivalent medium model does not meet the error requirements of the element content of the equivalent medium model; the initial content of each element in the initial equivalent medium model is corrected by the following formula to obtain the content of each element, and then the corrected initial equivalent medium model is obtained. 。 5. The neutron dose assessment method based on mobile phone neutron activation product analysis according to claim 1, characterized in that, The activation reaction rate is obtained by the following formula. in, To measure the activation reaction rate; The initial total activity of all types of neutron activation products in the mobile phone sample at the moment the neutron irradiation ends; The content of each element in the equivalent medium model; For elements x atomic weight.

6. A neutron dose assessment system based on the analysis of neutron activation products in mobile phones, characterized in that, The system includes: The sample acquisition unit is used to acquire a mobile phone sample carried by the irradiated person and to confirm the mobile phone model and type of the mobile phone sample. The energy spectrum acquisition unit is used to perform activation measurements on the mobile phone sample using a gamma spectrometer, determine the types of neutron activation products used for neutron spectroscopy in the mobile phone sample, and then obtain the initial total activity of all types of neutron activation products in the mobile phone sample at the end of neutron irradiation and the measured activation reaction rate of each activation product; using a particle transport simulation program, it simulates and calculates the calculated activation reaction rate of each element under a hypothetical neutron source irradiation condition using an equivalent medium model corresponding to the mobile phone model type of the mobile phone sample; and compares the calculated activation reaction rate of each element with the measured activation reaction rate. The ratio of the measured activation reaction rate to the calculated activation reaction rate is obtained by comparison. Based on the ratio of the measured activation reaction rate to the calculated activation reaction rate, the preset neutron energy spectrum corresponding to the preset neutron source irradiation conditions is corrected to obtain the corrected neutron energy spectrum. The final neutron energy spectrum is obtained based on the corrected neutron energy spectrum. The equivalent medium model is established based on the geometric three-dimensional model of the mobile phone sample, the elements of the mobile phone sample, and the initial content of the elements. The method for obtaining the equivalent medium model corresponding to the mobile phone model type includes obtaining mobile phone samples of various mobile phone models and using... A gamma-ray spectrometer is used to obtain background radiation data for mobile phone samples of various models. Based on the background radiation data of the mobile phone samples and the peak areas of the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone samples obtained in advance, the net peak area of ​​the gamma-ray characteristic peaks of each neutron-activated product of the mobile phone samples after neutron irradiation is obtained. The method for obtaining the peak area of ​​the gamma-ray characteristic peaks of the neutron-activated products of the mobile phone samples includes measuring the gamma energy spectrum of the pre-irradiated mobile phone samples using a gamma-ray spectrometer, determining the types of neutron-activated products of each model of mobile phone sample through the characteristic gamma-ray energies, and recording... The peak areas of the characteristic peaks of the neutron activation products are recorded; the pre-irradiated mobile phone sample is irradiated with a neutron source with known energy spectrum distribution and intensity; the geometric parameters of the mobile phone sample are measured, and a geometric three-dimensional model of the mobile phone sample is established; the elemental types of the mobile phone sample are determined according to the types of neutron activation products; and an initial content is assigned to each element of the mobile phone sample; using a particle transport simulation program, an equivalent medium model of the mobile phone sample is established based on the geometric three-dimensional model of the mobile phone sample, the elements of the mobile phone sample, and the initial content of the elements. The initial total activity of all types of neutron activation products of the mobile phone sample at the end of neutron irradiation was obtained by the following formula: in, The initial total activity of all types of neutron activation products in the mobile phone sample at the moment the neutron irradiation ends; The mobile phone sample carried by the person being irradiated; Indicates the phone model type; The moment when the person being irradiated by neutrons ends; t 1 ＇ The moment when the measurement of the mobile phone sample begins; t 2 ＇ This refers to the moment when the measurement of the mobile phone sample ends; For record t 2 ＇— t 1 ＇ The mobile phone samples obtained during the time period were measured. Phone(i)' Counting of gamma-ray characteristic peaks of neutron-activated products; λ j For the first j The decay constant of each activated product; R j For the first j The branching ratio of the gamma rays of the activated product to be tested; k j For the gamma spectrometer to the first j The detection efficiency of the gamma rays to be tested for each activated product; The end time of irradiation Then, at the measurement time t 2 ＇— t 1 ＇ The proportion of activated products that decreases due to the decay of activated products over a period of time; The neutron dose acquisition unit is used to obtain the neutron dose of the person being irradiated corresponding to the mobile phone sample based on the final neutron energy spectrum.

7. An electronic device, characterized in that, The electronic device includes a memory, a processor, and a neutron dose assessment program based on mobile phone neutron activation product analysis stored in the memory and executable on the processor. When the neutron dose assessment program based on mobile phone neutron activation product analysis is executed by the processor, it implements the neutron dose assessment method based on mobile phone neutron activation product analysis as described in any one of claims 1 to 5.

8. A computer-readable storage medium storing a computer program, characterized in that, When the computer program is executed by the processor, it implements the neutron dose assessment method based on mobile phone neutron activation product analysis as described in any one of claims 1 to 5.

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