Method and system for numerical protection of radiation emergency site disposal personnel, medium and equipment

Abstract

The application discloses a radioactive emergency scene disposal personnel numerical protection method and system, medium and equipment, and the method comprises the steps of: fine-tuning a prefabricated terrain model of an explosion position by using a scene terrain parameter to obtain an explosion scene terrain model, taking the explosion position as a diffusion center, combining a radioactive material space diffusion law and a pollution duration and a preset shift duration to determine a shift shift of the emergency scene disposal personnel; performing plume pollution calculation, deposition pollution calculation, deposition dose calculation, immersion dose calculation, inhalation dose calculation, ingestion dose calculation and dose weight calculation respectively; and determining and displaying numerical protection guidelines according to the shift shift determined by various types of emergency scene disposal personnel and the required calculation results, so that unified calculation can be carried out based on the same data source, and the required data and the shift shift of different types of emergency scene disposal personnel can be displayed in a targeted manner, and real-time sharing of numerical protection is achieved.

Description

Technical Field

[0001] This application relates to the fields of radiation protection technology and radiation emergency technology, and in particular to a numerical protection method, system, medium, and equipment for radiation emergency response personnel. Background Technology

[0002] An RDD (Radiological Dispersal Device) is a device designed and manufactured to spread radioactive materials with the intent to cause panic and economic impact, and to render a contaminated area unusable.

[0003] Radioactive distillations (RDDs) can detonate anywhere without warning, spreading radioactive contaminants across various surfaces and terrains. Once an RDD is detonated, emergency response personnel must arrive at the scene as quickly as possible to conduct emergency response operations. Especially in the initial stages of detonation, emergency personnel may have to immediately perform essential emergency response tasks such as incident investigation, radiation surveys, access control, public evacuation, and search and rescue operations without sufficient information, particularly before the radioactive materials used in the manufacture of the RDD have been identified. To avoid or minimize unnecessary radiation exposure and radioactive contamination to personnel conducting emergency response work at the RDD detonation site, appropriate safety arrangements must be made in advance or as soon as possible. Summary of the Invention

[0004] In view of this, this application provides a numerical protection method, system, medium, and equipment for radiation emergency response personnel. Compared with existing numerical protection methods, which only involve different types of personnel performing data calculations individually, and where the information and data obtained by each individual cannot be unified, leading to difficulties in the actual dispatching process due to the "misalignment" of information among various personnel, this application can perform unified calculations based on the same data source and display the required data and shift schedules in a targeted manner for different types of emergency response personnel, achieving real-time shared numerical protection and improving the efficiency of on-site protection dispatching.

[0005] According to one aspect of this application, a numerical protection method for radiation emergency response personnel is provided, the method comprising: Obtain the on-site topographic parameters of the detonation location of the radioactive dispersal device; The prefabricated terrain model corresponding to the detonation location is retrieved from the prefabricated terrain library. The prefabricated terrain model of the detonation location is fine-tuned using the on-site terrain parameters to obtain the detonation site terrain model. The prefabricated terrain library includes prefabricated terrain models that are prefabricated for multiple geographical locations. Determine the spatial diffusion patterns and duration of contamination of radioactive materials released after the detonation of a radioactive dispersal device; In the terrain model of the detonation site, the detonation location is taken as the diffusion center. Combining the spatial diffusion law of radioactive materials and the duration of pollution, as well as the preset shift time of emergency response personnel, the shift schedule of emergency response personnel at the detonation site is determined. The emergency response personnel include data collection personnel and safety protection personnel. Calculations were performed on plume pollution, sediment pollution, sediment dose, immersion dose, inhalation dose, ingestion dose, and dose weight for the detonation site, and the results of each calculation were obtained. For any type of emergency response personnel, based on the shift schedule determined by the emergency response personnel and the required calculation results, the numerical protection guidelines required by the emergency response personnel are determined and displayed on the preset terminal interface corresponding to the emergency response personnel, so that the emergency response personnel can carry out emergency response work with the numerical protection guidelines displayed on the preset terminal interface.

[0006] According to another aspect of this application, a numerical protection system for radiation emergency response personnel is provided, the system comprising: The on-site terrain parameter acquisition module is used to acquire the on-site terrain parameters of the detonation location of the radioactive dispersal device; The detonation site terrain model construction module is used to retrieve the prefabricated terrain model corresponding to the detonation location from the prefabricated terrain library, and to fine-tune the prefabricated terrain model of the detonation location using the site terrain parameters to obtain the detonation site terrain model. The prefabricated terrain library includes prefabricated terrain models that are prefabricated for multiple geographical locations. The radioactive material identification module is used to determine the spatial diffusion pattern and duration of contamination of radioactive materials released after the detonation of a radioactive dispersal device. The emergency personnel shift determination module is used to determine the shifts of emergency personnel at the detonation site in the terrain model of the detonation site, taking the detonation location as the diffusion center, and combining the spatial diffusion law of radioactive materials and the duration of pollution, as well as the preset shift duration of emergency personnel. The emergency personnel include data collection personnel and safety protection personnel. The radioactive contamination dose effect calculation module is used to perform calculations for plume contamination, sediment contamination, sediment dose, immersion dose, inhalation dose, ingestion dose, and dose weight for the detonation site, and obtain the calculation results for each type of calculation. The numerical protection guide generation and display module is used to determine the required numerical protection guide for any type of emergency response personnel based on their shift schedule and the required calculation results, and display it on the preset terminal interface corresponding to the emergency response personnel, so that the emergency response personnel can carry out emergency response work with the numerical protection guide displayed on the preset terminal interface.

[0007] According to another aspect of this application, a medium is provided having a computer program stored thereon, which, when executed by a processor, implements the above-described numerical protection method for personnel handling radiation emergency situations.

[0008] According to another aspect of this application, an apparatus is provided, including a medium, a processor, and a computer program stored on the medium and executable on the processor, wherein the processor, when executing the program, implements the above-described numerical protection method for personnel handling radiation emergency situations.

[0009] By means of the above technical solution, the numerical protection method, system, medium and equipment for radiation emergency response personnel provided in this application can perform unified calculations based on the same data source, and display the required data and shift schedules in a targeted manner for different types of emergency response personnel, so as to achieve real-time shared numerical protection.

[0010] The above description is only an overview of the technical solution of this application. In order to better understand the technical means of this application and to implement it in accordance with the contents of the specification, and to make the above and other objects, features and advantages of this application more obvious and understandable, the following are specific embodiments of this application. Attached Figure Description

[0011] The accompanying drawings, which are included to provide a further understanding of this application and form part of this application, illustrate exemplary embodiments and are used to explain this application, but do not constitute an undue limitation of this application. In the drawings: Figure 1 A flowchart illustrating a numerical protection method for radiation emergency response personnel provided in an embodiment of this application is shown. Figure 2 This illustration shows a schematic diagram of the main interface of the "Detonation Site Survey" function of an RDD (Radiation Emergency Numerical Protection Guide) system provided in an embodiment of this application. Figure 3 This illustration shows a schematic diagram of the main interface of the "Work Shift Plan" of an RDD radiation emergency numerical protection guide system provided in an embodiment of this application; Figure 4 This illustration shows a schematic diagram of the main interface of the "Work Shift Parameters" of an RDD Radiation Emergency Numerical Protection Guide system provided in an embodiment of this application; Figure 5 This paper shows a schematic diagram of the main interface of an RDD radiation emergency numerical protection guide system for "plume contamination calculation" provided in an embodiment of this application. Figure 6 This paper shows a schematic diagram of the main interface of the "Environmental Media Parameters" of an RDD radiation emergency numerical protection guide system provided in an embodiment of this application; Figure 7 This paper shows a schematic diagram of the main interface of the "Deposition Contamination Calculation" function of an RDD radiation emergency numerical protection guide system provided in an embodiment of this application. Figure 8 This illustration shows a schematic diagram of the main interface of the "weathering factor calculation" function of an RDD radiation emergency numerical protection guide system provided in an embodiment of this application. Figure 9 This paper shows a schematic diagram of the main interface of the "Deposition Dose Calculation" function of an RDD radiation emergency numerical protection guide system provided in an embodiment of this application. Figure 10 This paper shows a schematic diagram of the main interface of the "dose weight calculation" of an RDD radiation emergency numerical protection guide system provided in an embodiment of this application; Figure 11 This application provides an embodiment of an RDD radiation emergency response mission sequence diagram. Figure 12 This illustration shows a schematic diagram of a conceptual model of RDD radioactive contamination provided in an embodiment of this application; Figure 13 This illustration shows a schematic diagram of an RDD correction factor calculation model provided in an embodiment of this application; Figure 14 This illustration shows a process diagram for generating an RDD numerical protection guide according to an embodiment of this application; Figure 15 This illustration shows a schematic diagram of a "unit conversion parameter" main interface provided in an embodiment of this application; Figure 16 A schematic diagram of the structure of a numerical protection system for radiation emergency response personnel provided in an embodiment of this application is shown. Detailed Implementation

[0012] The present application will be described in detail below with reference to the accompanying drawings and embodiments. It should be noted that, unless otherwise specified, the embodiments and features described in the embodiments of the present application can be combined with each other.

[0013] This embodiment provides a numerical protection method for personnel handling radiation emergency situations, such as... Figure 1 As shown, the method includes: Step 101: Obtain the on-site terrain parameters of the detonation location of the radioactive dispersing device; Step 102: Retrieve the prefabricated terrain model corresponding to the detonation location from the prefabricated terrain library, and fine-tune the prefabricated terrain model of the detonation location using the on-site terrain parameters to obtain the detonation site terrain model. The prefabricated terrain library includes prefabricated terrain models that are prefabricated for multiple geographical locations. Step 103: Determine the spatial diffusion pattern and duration of contamination of the radioactive material released after the detonation of the radioactive dispersing device. Step 104: In the terrain model of the detonation site, taking the detonation location as the diffusion center, and combining the spatial diffusion law of radioactive materials and the duration of pollution, as well as the preset shift duration of emergency response personnel, determine the shift schedule of emergency response personnel when carrying out emergency response at the detonation site. Among them, emergency response personnel include data collection personnel and safety protection personnel. Step 105: Perform calculations for plume pollution, sediment pollution, sediment dose, immersion dose, inhalation dose, ingestion dose, and dose weight for the detonation site, and obtain the calculation results for each type of calculation. Step 106: For any type of emergency response personnel, based on the shift schedule determined by the emergency response personnel and the required calculation results, determine the numerical protection guidelines required by the emergency response personnel and display them on the preset terminal interface corresponding to the emergency response personnel, so that the emergency response personnel can carry out emergency response work with the numerical protection guidelines displayed on the preset terminal interface.

[0014] In the embodiments described above, numerical protection guidelines can be generated using a "conceptual model" and "big data preprocessing technology." Specifically, firstly, the on-site terrain parameters of the detonation location of the radioactive dispersal device are obtained. Various methods can be used to acquire these parameters, such as using satellite remote sensing imagery to provide a broad overview of the terrain. By analyzing and processing the imagery, information such as terrain undulation, slope, and aspect can be extracted. Alternatively, drones can be used for low-altitude aerial mapping to acquire high-resolution terrain data, construct a three-dimensional terrain model, and accurately measure parameters such as terrain height and distance. Ground-based surveying equipment, such as total stations and GPS receivers, can also be used to conduct on-site measurements and obtain detailed terrain coordinates, elevation, and other data. Next, a pre-fabricated terrain model corresponding to the detonation location is retrieved from a pre-fabricated terrain library and fine-tuned. This library is a collection of pre-fabricated terrain models created in advance for multiple geographical locations. Specifically, based on the geographical information of the detonation location, such as latitude, longitude, and place name, the corresponding pre-fabricated terrain model is found in the library. Then, using the previously acquired on-site terrain parameters, the pre-fabricated terrain model is fine-tuned. For example, if the on-site terrain parameters show a difference between the slope of a certain area and the pre-fabricated terrain model, the slope of that area in the model is adjusted to better match the actual detonation site terrain, ultimately resulting in the detonation site terrain model. Next, the spatial diffusion patterns and duration of contamination of radioactive materials are determined. This can be achieved through theoretical model calculations, combined with factors such as the physicochemical properties of radioactive materials, release methods, and meteorological conditions, to establish a diffusion model to simulate the spatial diffusion patterns of radioactive materials. For example, the Gaussian plume model can be used to simulate the diffusion of radioactive materials in the atmosphere. Simultaneously, by referring to actual monitoring data from previous similar radioactive material leaks or explosions, their diffusion patterns and contamination durations are analyzed to provide a reference for this event. Monitoring equipment can also be set up on-site to monitor changes in radioactive material concentration in real time, and the spatial diffusion patterns and duration of contamination are determined based on the monitoring data. Finally, the shift schedules for emergency response personnel are determined. In the obtained detonation site terrain model, the detonation location is used as the diffusion center. The shift schedules are determined by combining the previously determined spatial diffusion patterns and duration of contamination of radioactive materials with the pre-set shift schedules for emergency response personnel. For example, based on spatial diffusion patterns, it is known that radioactive materials will spread to a certain area within a certain timeframe. Within this area, considering the duration of contamination and pre-set shift schedules, to ensure the safety of emergency response personnel and prevent them from prolonged exposure to high radiation environments, shift schedules are rationally arranged to ensure that personnel on each shift work within a relatively safe dose range. Emergency response personnel include data collection personnel and safety protection personnel, and their shift schedules are determined based on their respective job nature and needs.Next, various dose calculations are performed, including: Plume contamination calculation: Considering the diffusion of radioactive materials in the atmosphere, and taking into account meteorological conditions, topography, and other factors, the concentration distribution of radioactive materials in the plume is calculated. Deposition contamination calculation: Analyzing the deposition of radioactive materials on surfaces such as the ground, the amount and distribution of deposited radioactive materials are calculated. Deposition dose calculation: Based on the amount and distribution of deposited radioactive materials, the external radiation dose received by personnel is calculated. Immersion dose calculation: Obtaining the radiation dose rate at the detonation site and multiplying it by the preset shift duration of emergency response personnel yields the immersion dose; if the radiation dose rate is not obtained, the dose rate is calculated using the time-integrated air activity calculated from plume contamination combined with the gamma-ray constant of the nuclide. When multiple nuclides are involved, the immersion doses of all nuclides are summed to obtain the total immersion dose. Inhalation dose calculation: Obtaining the inhalation activity at the detonation site and multiplying it by the nuclide inhalation dose conversion factor yields the internal radiation dose; if the inhalation activity is not obtained, the inhalation activity is calculated using the time-integrated air activity calculated from plume contamination and the respiratory parameters of emergency response personnel. Ingestion Dose Calculation: The ingestion activity at the detonation site is obtained and multiplied by the nucleoside ingestion dose conversion factor to obtain the ingested internal radiation dose. If the ingestion activity is not obtained, the ingestion activity is calculated using the time-integrated air activity calculated from the plume contamination, combined with the adhesion coefficient and the ingested amount. Dose Weighting Calculation: The total external radiation dose is obtained based on the deposited external radiation dose and the immersion external radiation dose. The total dose is also obtained based on the inhaled internal radiation and the ingested internal radiation. The weighting factor for the total external radiation dose is obtained by calculating the ratio between the two. Next, numerical protection guidelines are determined and displayed. Based on the shift schedules determined by various emergency response personnel (data acquisition personnel and safety protection personnel) and the results of the previous dose calculations, the numerical protection guidelines are determined by comprehensively considering personnel safety and work requirements. For example, the level of protective measures that personnel should take when working in different areas and the maximum allowable stay time are determined based on the dose calculation results. These numerical protection guidelines are then displayed on a preset terminal interface, allowing emergency response personnel to take corresponding protective measures according to the guidelines to ensure their own safety and efficiently complete their work tasks.

[0015] Furthermore, the above embodiments of this application can be applied to the "Numerical Protection System for Radiation Emergency Response Personnel." By clicking operation buttons of different colors on the interface, a "Numerical Protection Guide" can be generated. For example, gray represents inoperable; cyan represents customizable; pink represents input, selection of radiation / radioactive nuclides, calculation, survey, correction, export, and import operations; green represents selecting default parameters from the main data module; and orange represents selecting units. In addition, after obtaining the on-site terrain parameters of the detonation location of the radioactive dispersing device, the contaminated area and buildings can be defined in the detonation site survey interface of the main input module of the "Numerical Protection System for Radiation Emergency Response Personnel," and RDD emergency investigation and detonation site contamination survey information can be entered, such as... Figure 2 As shown, this is used for subsequent calculations.

[0016] Additionally, you can also input the work shift plan interface of the main module ( Figure 3 In the data master module, enter the work shift information (preset shift duration) of emergency response personnel performing specific emergency response tasks at specific times and locations of the RDD detonation site; in the work shift parameter interface ( Figure 4 Select the default parameters (dose limit, shift time, respiratory rate, respirator protection factor, and ingestion rate) for subsequent calculations.

[0017] Optionally, in step 105, a plume pollution calculation is performed for the detonation site to obtain the plume pollution calculation results, including: Step 1051: Determine the plume deposition rate at the detonation site according to Stokes' law; Step 1052: Obtain the plume size at the detonation site; Step 1053: Determine the sediment contamination partition factor based on the distribution ratio of radioactive materials in the air and sediments; Step 1054: Measure and integrate the radioactivity in the air at the detonation site to obtain the time-integrated air activity. If the radioactivity in the air cannot be measured, the time-integrated air activity is back-calculated using the plume deposition rate. Step 1055: Based on the plume deposition rate, plume size, time-integrated air activity, and depositional contamination distribution factor, simulate the diffusion process of the radioactive plume released after the detonation of the radioactive dispersing device in the air, and obtain the distribution of radioactive material concentration at different times and spatial locations after detonation as the plume contamination calculation result.

[0018] In the above embodiments of this application, if it is necessary to consider plume pollution, it can be done in the plume pollution calculation interface of the main calculation module ( Figure 5In the particle size-weighted average plume deposition rate calculation sub-interface, plume pollution calculation is performed; in the work shift parameter interface of the main data module ( Figure 6 Select the default parameters (plume deposition rate, plume size and its deposition rate, and depositional contamination partition factor) in the configuration. The time-integrated air activity in the plume contamination calculation interface is derived from the RDD detonation site survey and can be input by the user. If the time-integrated air activity is not obtained from the site survey, the time-integrated depositional activity can be derived from the depositional activity using the plume deposition rate or the size-weighted average plume deposition rate. If plume contamination is not required, perform the depositional contamination calculation directly.

[0019] Specifically, regarding plume pollution calculations, the core objective is to simulate the diffusion process of radioactive plumes in the air, calculate the distribution of radioactive material concentrations at different times and spatial locations, provide emergency personnel with real-time pollution range and high-risk area identification, and support evacuation, isolation, and protection decisions. Specifically, the following key parameters need to be determined during the calculation process: plume deposition rate v d , which is the velocity of radioactive particles falling from the plume to the ground (unit: m / s), is affected by factors such as particle size, wind speed, and topography, and can be calculated using a modified formula based on Stokes' law: , in, Particle density (kg / m³) Let be the air density (kg / m³), r be the particle radius (m), and g be the acceleration due to gravity. This is a physical quantity in physics that describes the acceleration of an object in a gravitational field caused by gravity. ρ is the aerodynamic viscosity (Pa·s), and Re is the Reynolds number, which is dimensionless and reflects the degree of airflow turbulence.

[0020] plume size distribution The median particle size (in μm) of radioactive particles determines their diffusion capacity and deposition characteristics. It can be preset through on-site sampling or historical data, such as the typical particle size range corresponding to the type of explosive device.

[0021] Depositional pollution partition factor , which represents the distribution ratio of radioactive materials in the air and sediments, reflects the efficiency of pollution migration, and is calculated as follows: , in, Surface sedimentary activity (Bq / m²) Air concentration (Bq / m³) Exposure time (s).

[0022] Time-integrated air activity can be obtained by measuring the radioactivity in the air (Bq / m³) in real time using a portable radiation monitor and integrating the results. .

[0023] When time-integrated air activity cannot be obtained through on-site exploration, it can be indirectly derived by first measuring the activity of ground sediments. According to the plume deposition rate Or particle size weighted average deposition rate Inversely calculate the time integral of air activity: , in, Weighted calculation can be performed based on particle size: , The weight of the i-th particle size segment (based on the particle size distribution function).

[0024] For plume concentration distribution models, a Gaussian plume model can be used, which is suitable for continuous point source releases, or a Lagrange particle model can be used, which is suitable for instantaneous releases. The diffusion coefficient can be corrected by combining a terrain model. , Where Q is the release rate (Bq / s); u is the wind speed (m / s). and These are the lateral and vertical diffusion parameters (affected by atmospheric stability and topography); H is the effective release height (m).

[0025] For terrain correction, the diffusion parameters are adjusted by detonating the on-site terrain model (such as buildings and mountains), for example: Mountainous areas, , Reduce (airflow obstruction); city, Increase (turbulence intensifies).

[0026] Optionally, in step 105, a sedimentary contamination calculation is performed for the detonation site to obtain the sedimentary contamination calculation results, including: Step 1056: Obtain the original sedimentary activity of various environmental media at the detonation site; Step 1057: For any environmental medium, the weathering constant and resuspension factor are used to correct the change of the original sedimentary activity of the environmental medium over time, so as to obtain the final sedimentary activity of the environmental medium. Step 1058: Based on the final deposition activity of each environmental medium, generate the deposition activity distribution of radioactive materials in the environmental medium at different times and spatial locations at the detonation site, as the result of deposition pollution calculation.

[0027] In the above embodiments of this application, the deposition contamination calculation interface of the main calculation module ( Figure 7 ) and weathering factor calculation sub-interface ( Figure 8 In the data master module, perform sediment contamination calculations; in the shift parameter interface ( Figure 6 Select the default parameters (depositional pollution partition factor, weathering factor, resuspension factor, weathering constant) in the configuration. The depositional activity in the depositional pollution calculation interface comes from the RDD detonation site survey (user input). If the site survey does not obtain the depositional activity of all environmental media (ground, roof, exterior wall, floor, interior wall, one or more of these), the depositional activity of all environmental media can be obtained by correcting with the depositional pollution partition factor. If no depositional activity of any environmental media is obtained without a site survey, return to the plume pollution calculation steps and derive the depositional activity from the time-integrated air activity using the plume deposition rate or the particle size-weighted average plume deposition rate.

[0028] Specifically, for sediment contamination calculations, sediment contamination partition factor, weathering factor, resuspension factor, and weathering constant can be used together: First, sediment activity is obtained. If the sediment activity of some or all environmental media (such as ground, roof, exterior walls, floors, interior walls, etc.) has been obtained from the RDD (Radioactive Dispersion Device) detonation site survey, the survey data input by the user can be used directly. If only the sediment activity of some environmental media is obtained, the sediment contamination partition factor can be used for correction to estimate the sediment activity of the unsurveyed media, thereby obtaining the total sediment activity of all environmental media.

[0029] Specifically, if the depositional activity of any environmental medium is not obtained, the calculation returns to the plume contamination step, using the plume deposition rate to deduce the depositional activity from the time-integrated air activity. The weathering constant and resuspension factor are then used to correct for changes in depositional activity over time, such as reductions in radioactive material due to rainwater erosion or wind resuspension. The final depositional activity of each environmental medium is calculated by integrating survey data, partition factor corrections, and weathering corrections. The calculation results show the distribution of radioactive material depositional activity in the environmental medium at different times and spatial locations after detonation, including, for example: 1. Classification of environmental media: The amount of radioactive material deposited on various surfaces such as ground, roof, exterior walls, floor, and interior walls, in units of Bq / m² or other activity units.

[0030] 2. Spatiotemporal distribution: Changes in sedimentary activity at different time points, such as 1 hour, 24 hours, and 7 days after detonation. Differences in sedimentary activity at different spatial locations, such as different distances and orientations around the detonation point.

[0031] 3. Corrected Data: If the original data is missing, the results include estimates derived from the partition factor or plume deposition rate. Dynamic corrections are made considering weathering and resuspension effects. Depositional contamination calculation results can be directly used for: 1. Numerical protection guidelines generation: Based on the results of plume pollution and dosage calculations, determine the shift schedule and protective measures for emergency response personnel, such as the time for wearing protective clothing and evacuation route planning.

[0032] 2. Terminal interface display: The sediment activity distribution map is dynamically displayed on the preset terminal interface, such as a tablet computer, to help personnel avoid highly polluted areas.

[0033] 3. Long-term pollution assessment: Provides basic data for subsequent environmental remediation and public health risk assessment.

[0034] Therefore, based on field survey data, missing data are supplemented using partition factors and plume models, and corrected for weathering effects to achieve spatiotemporal dynamic calculation of sedimentary activity. By fusing multi-source data from surveys, model extrapolation, and dynamic correction (i.e., weathering effects), the accuracy and practicality of the calculation results are improved, especially suitable for situations where data is incomplete in emergency scenarios.

[0035] Optionally, in step 105, a deposition dose calculation is performed for the detonation site to obtain the deposition dose calculation results, including: Step 1059: Calculate the dose rate corresponding to each environmental medium; Step 10510: For any environmental medium, based on the dose rate of the environmental medium, quantify the radiation exposure of emergency response personnel at the detonation site to the environmental medium, and obtain the deposition dose of the environmental medium. Step 10511: Based on the quantified deposition doses of various environmental media at the detonation site, the total deposition dose is obtained as the deposition pollution calculation result.

[0036] In the above embodiments of this application, the calculation of the deposition dose at the detonation site can be achieved through a core logic of "deposition activity distribution - dose rate conversion - time - personnel adaptation - total dose output," combined with the characteristics of radionuclides, environmental media features, and the working scenario of emergency personnel. This transforms the "deposition contamination calculation results," i.e., the deposition activity at different times / spaces, into the "deposition dose actually received by personnel." The specific calculation steps and principles are as follows: Deposition dose refers to the dose received by personnel after radioactive materials are deposited in environmental media, such as ground, soil, vegetation, and building surfaces, and are then exposed to gamma rays. The radiation dose produced by the human body. Its calculation essentially involves: depositional activity, i.e., the radioactivity intensity in the environmental medium, converted into the dose rate at the location of the person – combined with the person's residence time – to obtain the total depositional dose. Specifically: Obtain the basic data for depositional pollution calculation, and extract the following key parameters from the depositional pollution calculation results: Environmental medium type: such as ground (asphalt / cement), soil, vegetation, building surfaces, etc.; Spatiotemporal depositional activity distribution, the depositional activity of the medium at different times (t) and different spatial locations (x, y) (area source: As, unit Bq / m2; volume source: Av, unit Bq / m2). q / kg). Next, determine the radiation characteristic parameters of the radionuclide, and look up the basic parameters of the radioactive material, such as the gamma-ray constant (Γ): reflecting the dose rate produced per unit activity nuclide per unit distance, with units of mSv·m2 (millisieverts·square meters / (hours·megabecquerels)). Decay constant (λ): calculated from the nuclide half-life (λ=ln2 / T1 / 2), used to correct for the time decay of deposition activity (negligible if the duration of contamination is less than 1 / 10 of the half-life in emergency response). The core of deposition dose is to convert the deposition activity in the medium into the dose induced by personnel. The dose rate at a location (unit: mSv / h) can be calculated using a formula tailored to the medium type, such as area source or volume source, and incorporating a geometric correction factor and a medium attenuation factor. The geometric correction factor is based on factors such as the distance between the person and the medium, while the medium attenuation factor characterizes the absorption of gamma rays by the medium. For area source media, such as the ground or building surfaces: an area source refers to radioactive material uniformly deposited on a two-dimensional plane (such as the ground or walls). Emergency scenes often involve large-area uniform deposition, such as ground contamination after a plume spread. The dose rate calculation formula is as follows, for a scenario where a person is standing approximately 1 meter from the medium surface: , : Dose rate of the area source medium (mSv / h); As: Surface source sedimentary activity (Bq / m³) 2 ); Γ: gamma-ray constant (mSv•m) 2 / (h•MBq); F g: Geometric correction factor (typically 0.46 for an infinitely large planar source, reflecting the dose contribution of ground scattering from all directions to personnel). F a : Medium attenuation factor (e.g., soil absorption of γ-rays, typically taken as 0.95 for simplified emergency calculations); Divide by 1000: Change the unit of As from Bq / m 2 Convert to MBq / m2 (1MBq=1000Bq).

[0037] For volumetric sources: Volumetric sources refer to radioactive materials uniformly distributed in a three-dimensional volume (such as soil layers or vegetation leaves). The influence of medium density on the dose rate must be considered. Dose rate calculation formula: , : Dose rate of the body-derived medium (mSv / h); Volumetric sedimentary activity (Bq / kg); ρ: Density of medium (kg / m3, e.g., soil density ≈ 1500 kg / m3) 3 Vegetation density ≈ 500 kg / m² 3 ); Other parameters are the same as those in the surface source formula.

[0038] Next, the total deposition dose is calculated by combining the personnel shift duration. The ultimate goal of deposition dose is to quantify the total radiation exposure of emergency personnel working in a certain area. This can be combined with the preset shift duration (T), such as 4-hour shifts for data collection personnel and 6-hour shifts for safety protection personnel. The formula for calculating the total deposition dose is as follows: , Total deposition dose (mSv) for emergency personnel; : Dose rate of the i-th environmental medium (mSv / h); n: The type of environmental media involved (e.g., ground + vegetation); T: The time emergency personnel spend in the area (shift duration) (h).

[0039] Output the deposition dose calculation results. In particular, for different types of emergency personnel, such as data collection personnel and safety protection personnel, the following results are output: the medium dose rate distribution in the corresponding work area, the total deposition dose of personnel, and the temporal-spatial variation law of the dose rate, such as the highest dose rate 2 hours after pollution, which drops to 0.5 mSv / h after 4 hours due to plume diffusion. Depositional dose calculation results are one of the core bases of numerical protection guidelines, and can be used for: 1. Shift length adjustment: If the total depositional dose exceeds the emergency personnel dose limit (e.g., the ICRP-recommended emergency exposure dose limit of 50 mSv, but in practice it is more stringent, such as 10 mSv), shift length needs to be shortened; 2. Protective equipment upgrade: If the dose rate is too high (e.g., >1 mSv / h), personnel need to be equipped with gamma-ray protective equipment (e.g., lead aprons, to attenuate gamma rays); 3. Work area division: Based on the dose rate distribution, the site is divided into high / medium / low contamination zones (e.g., dose rate >1 mSv / h is high contamination zone, 0.1-1 mSv / h is medium contamination zone, <0.1 mSv / h is low contamination zone), and the frequency of personnel entering high contamination zones is limited. Therefore, the essence of depositional dose calculation is the transformation of "depositional activity - dose rate - total dose". The key is to combine the characteristics of the environmental medium and the personnel's working scenario, such as distance or time, to transform the abstract depositional activity into a "radiation exposure" that emergency personnel can understand. The results directly supported the development of subsequent "numerical protection guidelines," such as limiting stay time and upgrading protective equipment to ensure the radiation safety of emergency response personnel.

[0040] Optionally, in step 105, immersion dose calculation, inhalation dose calculation, ingestion dose calculation, and dose weight calculation are performed for the detonation site to obtain various calculation results, including: Step 10512: For the immersion dose calculation, obtain the radiation dose rate at the detonation site, multiply the radiation dose rate by the preset shift duration of the emergency response personnel, and obtain the immersion dose for the emergency response personnel as the immersion dose calculation result. If the radiation dose rate is not obtained, the radiation dose rate is calculated by using the time integral air activity calculated from the plume pollution and combining it with the gamma-ray constant of the radioactive material. When the radioactive material includes multiple nuclides, the total immersion dose is obtained by summing the immersion doses of each nuclide as the immersion dose calculation result. Step 10513: For inhalation dose calculation, obtain the inhalation activity at the detonation site, multiply the inhalation activity by the radionuclide inhalation dose conversion coefficient, and obtain the inhaled internal radiation dose for emergency response personnel as the inhalation dose calculation result. If the inhalation activity is not obtained, the inhalation activity is calculated using the time integral air activity calculated from the plume pollution and the respiratory parameters of the emergency response personnel. The respiratory parameters include at least one of the following: respiratory rate, preset shift duration, and inhalation fraction. The inhalation fraction represents the proportion of the inhalation into the deep respiratory tract. Step 10514: For the ingestion dose calculation, obtain the ingestion activity at the detonation site, multiply the ingestion activity by the nucleoside ingestion dose conversion coefficient, and obtain the ingested internal radiation dose as the ingestion dose calculation result. If the ingestion activity is not obtained, the ingestion activity is calculated by using the time integral air activity calculated from the plume pollution, combined with the adhesion coefficient and the ingestion amount. Step 10515: For dose weight calculation, the total external irradiation dose is obtained based on the deposited external irradiation dose and the immersion external irradiation dose. The total dose is obtained based on the inhaled internal irradiation and the ingested internal irradiation. By calculating the ratio between the total external irradiation dose and the total dose, the total external irradiation dose weight factor used to characterize the contribution ratio of external irradiation to the total risk is obtained as the dose weight calculation result.

[0041] In the above embodiments of this application, the deposition dose calculation interface of the main calculation module can be used sequentially. Figure 9 ), Immersion dose calculation interface, Inhalation dose calculation interface, Ingestion dose calculation interface, Dose weight calculation interface ( Figure 10 In the data master module, calculations are performed for sediment contamination, immersion dose, inhalation dose, ingestion dose, and dose weighting. Figure 6 Select the default parameters (roughness factor, resuspension multiplier, building protection factor) in the settings. For immersion dose calculation, inhalation dose calculation, oral dose calculation, and dose weighting, for example: I. Immersion Dosage Calculation: Immersion external radiation dose is the gamma / X-ray external radiation dose received by emergency personnel when they are in a radioactive plume. The calculation process is directly related to the plume contamination results and on-site measurement data, such as corresponding... Figure 10 The "Immersion External Irradiation Dose" item under "Nucleoside Dose" and "Mixture Dose" is as follows: If the dose rate is obtained from the field monitoring instrument, such as 0.1 mSv / h, then... Figure 10 The "dose rate" in the "detection indicators" is directly "transferred" into the system and multiplied by the stay time of emergency personnel. For example, if the preset shift length is 2 hours, the immersion dose is obtained, that is, immersion external irradiation dose = dose rate × stay time. If no on-site data is available, the air concentration calculated using plume pollution, such as the air concentration of Co-60 being 100 Bq / m³, can be combined with the gamma-ray constant of the nuclide, such as the gamma-ray constant of Co-60 being approximately... First, calculate the exposure rate, which is the radiation exposure per unit time, and then multiply it by the dwell time. That is, exposure rate = air concentration × gamma ray constant; immersion external radiation dose = exposure rate × dwell time.

[0042] For a single nuclide, such as Po-210 alone, it is possible to... Figure 10In the “Nucleoside Dosage” module, select the corresponding nuclide, and the system can automatically calculate the gamma-ray constant of that nuclide.

[0043] For mixtures, such as plumes containing Co-60+Sr-90, you can select all nuclides in the "Mixed Dosage" module, and the system will automatically add up the immersion dose of each nuclide to obtain the total dose.

[0044] II. Inhalation Dosage Calculation: Inhaled internal radiation dose is the internal radiation dose caused by the deposition of radioactive material in the body's organs after an emergency responder inhales radioactive aerosols. Figure 10 The "Inhaled Internal Radiation Dose" item under "Nuclear Nucleus Dose" and "Mixed Dose" is as follows: If inhalation activity data is available from an air sampler, such as a Po-210 activity of 50 Bq on a filter membrane, it is directly "transferred" into the system and multiplied by the radionuclide inhalation dose conversion factor. For example, the inhalation DC of Po-210 is approximately 2.5 × 10⁻⁶. -4 Sv / Bq gives the inhaled dose, which is the inhaled internal radiation dose = inhaled activity × inhaled dose conversion factor.

[0045] If no sampling data is available, the air concentration of plume pollution is used, combined with the respiratory parameters of emergency personnel, such as a respiratory rate of 1.2 m³ / h, a preset shift duration of 2 hours, and an inhalation fraction of 0.8. The inhalation fraction represents the proportion of the inhaled substance entering the deep respiratory tract. First, the inhalation activity is calculated, and then multiplied by the dose conversion factor. That is, inhalation activity = air concentration × respiratory rate × time × inhalation fraction. Inhaled internal radiation dose = inhalation activity × inhalation dose conversion factor.

[0046] In particular, the inhaled dose conversion factor (DC) integrates radiation weighting factors and tissue weighting factors, directly reflecting the effective dose of internal irradiation (unit: Sv).

[0047] III. Calculation of Ingested Dosage: Ingested internal radiation dose refers to the internal radiation dose caused by emergency personnel accidentally ingesting contaminated food / water or touching their mouths with contaminated hands. Figure 10 The "Ingested Internal Radiation Dose" item under "Nuclear Nucleotide Dose" and "Mixture Dose" is as follows: If there is laboratory analysis of food / water activity, such as a contaminated water concentration of 100 Bq / L and accidental ingestion of 0.5L, first calculate the ingested activity: 100 × 0.5 = 50 Bq. Then multiply by the nucleoside intake dose conversion factor, such as the ingested DC of Sr-90 being approximately 2.8 × 10⁻⁶. -7 Sv / Bq), the internal radiation dose ingested is equal to the ingested activity multiplied by the ingested dose conversion factor.

[0048] If no detection data is available, the environmental deposition activity of the deposited contaminant, such as a ground deposition activity of 1000 Bq / m², combined with the adhesion coefficient, such as a vegetable surface adhesion coefficient of 0.1 m² / kg, and the ingestion amount, such as consuming 0.2 kg of vegetables, can be used to calculate the ingestion activity: Food contaminant activity = Deposition activity × Adhesion coefficient Ingestion activity = Food contaminant activity × Ingestion amount Ingested internal radiation dose = Ingestion activity × Ingestion dose conversion factor.

[0049] IV. Dose weighting calculation, corresponding to the total external irradiation dose weighting factor: Dose-weighted calculations are used to assess the proportion of external radiation exposure (immersion + deposition) in the total radiation risk, providing a prioritization basis for protection strategies. Figure 10 The "Weighting Factor for Total External Irradiation Dose" item: Based on the previous calculations, the following data will be automatically extracted: Total external radiation dose: deposited external radiation dose + immersion external radiation dose (both are external radiation, from γ / β rays); Total dose: Total external irradiation dose + Total internal irradiation dose (inhaled internal irradiation + ingested internal irradiation).

[0050] The weighting factor is obtained through proportional calculation: External irradiation total dose weighting factor = external irradiation total dose ÷ total dose.

[0051] Therefore, the weighting factor can reflect the proportion of external radiation's contribution to the total risk. For example, 0.7 means that 70% of the risk comes from external radiation. If the weight is high, emergency personnel should prioritize strengthening external radiation protection, such as wearing lead aprons and shortening the time spent in the environment. If the weight is low, they should prioritize strengthening internal radiation protection, such as wearing gas masks and avoiding accidental ingestion.

[0052] In particular, Figure 10 The core difference between the "Nuclear Nucleus Dosage" and "Mixture Dosage" modules lies in the type of contamination: Nuclide dose: For a single nuclide, such as Po-210 only, calculate the various doses of that nuclide (immersion, inhalation, ingestion), and then summarize the external irradiation and total dose.

[0053] Mixture dose: For multiple nuclides, such as Co-60+Sr-90 released by RDD, first calculate the dose of each nuclide, and then sum them to obtain the total dose. For example, the immersion dose of the mixture = Co-60 immersion dose + Sr-90 immersion dose.

[0054] In particular, the calculation results for the four dosages can be directly used for: 1. Shift schedule determination: If the external radiation dose exceeds the limit, such as 2 mSv / shift, the preset shift duration for that area will be shortened; 2. Protection Guideline Generation: If the internal radiation weight is high, the terminal interface will prompt "KN95 mask + goggles are required"; if the external radiation weight is high, it will prompt "lead apron + lead neck brace are required". 3. Risk visualization: The terminal interface will display "high immersion dose area" and "high inhalation risk area" with heat map to guide emergency personnel to avoid danger zones.

[0055] To this end, from basic data, including plume concentration, deposition activity, and field measurements, to dose calculations including immersion, inhalation, and ingestion, to weight assessments including the proportion of external exposure, and then to protection decisions, the system transforms complex radiation dosimetry into an operable "numerical protection guide" through an automated process, directly serving the safe handling of emergency situations.

[0056] Optionally, in step 106, for any type of emergency response personnel, based on the shift schedule determined by the emergency response personnel and the required calculation results, the required numerical protection guidelines for the emergency response personnel are determined and displayed on the preset terminal interface corresponding to the emergency response personnel, including: Step 1061: For data collection personnel, based on the calculation results of plume pollution, sediment pollution, sediment dose, immersion dose, inhalation dose, dose weight, and the shift schedule determined by the data collection personnel, determine the numerical protection guidelines for the data collection personnel and display them on the preset terminal interface. Step 1062: For safety protection personnel, based on the calculation results of plume pollution, sediment pollution, sediment dose, immersion dose, ingestion dose, dose weight, and the shift schedule determined by the safety protection personnel, determine the numerical protection guidelines for the safety protection personnel and display them on the preset terminal interface.

[0057] In the above embodiments of this application, the required calculation results and their uses for data collection personnel are as follows: Data collectors work by venturing deep into contaminated areas to collect data, prioritizing the prevention of exposure to high concentrations of contaminants, excessive dose exposure, and internal radiation intake. Therefore, their required calculations can focus on the contamination distribution at the collection point, individual exposure doses, and the suitability of protective measures. For example: 1. Plume Pollution Calculation Results: This result presents the distribution of radioactive material concentrations at different times and spaces. For data collectors, its uses are mainly reflected in two aspects: first, determining safe collection points by understanding the plume pollution situation and avoiding high-concentration areas in the plume, such as avoiding staying in the high-concentration areas in the center of the plume or downwind; second, planning collection time to avoid the peak period of plume diffusion, thereby reducing the risk of inhalation.

[0058] 2. Deposition Contamination Calculation Results: This result shows the distribution of deposition activity in environmental media such as soil, vegetation, and equipment at different times and spaces. Data collection personnel can use this information to select collection media, prioritizing media with low deposition activity. If collecting media with high deposition activity, protective equipment such as gloves and protective clothing must be worn. At the same time, when collecting soil samples, areas with excessive deposition activity should be avoided to prevent contact with contaminants.

[0059] 3. Depositional Dose Calculation Results: These results present the distribution of external radiation dose caused by the deposition of radioactive materials in the environmental medium at different times and spaces. Data collectors can use this to assess the external radiation risk from contact with deposits when collecting data in specific areas. For example, in areas with high depositional doses, the dwell time should be shortened or protective measures should be increased. It can also be used to verify the effectiveness of protective equipment. If the depositional dose still exceeds the standard after wearing protective clothing, the protective equipment needs to be upgraded.

[0060] 4. Immersion dose calculation results: This result is the immersion dose within the individual's preset shift time, i.e., the total external radiation dose. Data collection personnel can use this to control their stay time. If the dose rate at the collection point is high, such as if it is located in the center of the plume, the shift time needs to be shortened. It can also verify the effectiveness of protection. If the dose still exceeds the standard after wearing a lead apron, the protective measures need to be upgraded.

[0061] 5. Inhalation dose calculation results: This result is the individual inhaled internal radiation dose, calculated based on respiratory parameters such as respiratory rate and inhalation fraction. Data collection personnel can select respiratory protective equipment based on this result. If the inhalation dose exceeds the standard, the gas mask needs to be upgraded from N95 to a full-face mask or other equipment with higher filtration efficiency. The collection method can also be adjusted, such as using remote sampling equipment to reduce direct breathing of polluted air.

[0062] 6. Dose Weighting Calculation Results: This result is the weighting factor for the total external radiation dose, i.e., the proportion of external radiation to the total dose. Data collection personnel can use this to optimize protective resources. If external radiation contributes significantly, such as accounting for 80%, lead aprons should be prioritized; if internal radiation contributes significantly, such as accounting for 60%, respiratory protection should be strengthened, such as wearing powered air-purifying masks.

[0063] II. Calculation Results and Applications Required by Safety and Security Personnel The job of safety personnel is to ensure overall on-site safety, which requires prioritizing the identification of contaminated area boundaries, the deployment logic of protective measures, and safety thresholds for personnel activities. Therefore, their required calculations focus on the extent of regional contamination, the deployment logic of protective measures, and the constraints on personnel behavior, as detailed below: 1. Calculation results of plume pollution: The distribution of radioactive material concentrations at different times and spaces has multiple uses for safety personnel. On the one hand, it can be used to delineate safety boundaries, establishing "no-entry zones," "restricted zones," and "safe zones" based on plume diffusion patterns, such as designating a 1-kilometer downwind zone as a high-concentration area. On the other hand, it can be used to deploy protective barriers, such as building shielding walls along the plume diffusion path downwind to reduce the plume's diffusion range.

[0064] 2. Deposition Contamination Calculation Results: The distribution of deposition activity in environmental media at different times and spaces helps safety personnel manage protective equipment and plan contamination cleanup. In terms of protective equipment management, it helps avoid placing protective equipment, such as lead aprons and masks, in areas with high deposition activity, such as equipment surfaces with excessive deposition activity. In terms of contamination cleanup planning, it helps identify areas requiring focused cleanup, such as areas with high vegetation deposition activity.

[0065] 3. Deposition Dose Calculation Results: These results present the distribution of external radiation dose caused by the deposition of radioactive materials in the environmental medium at different times and spaces. Safety personnel can use this to assess the external radiation risk level caused by deposits in different areas, providing a basis for delineating safe zones. For example, areas with higher deposition doses can be designated as high-risk zones, restricting personnel access. It can also be used to guide the deployment of protective measures, such as adding shielding facilities or strengthening personnel protection in areas with higher deposition doses.

[0066] 4. Immersion dose calculation results: The calculation results of the radiation dose rate and total immersion dose in different areas can allow safety personnel to monitor personnel activities and remind data collection personnel of the dose rate in a certain area. For example, if the dose rate in a certain area reaches 10 μSv / h, they can be informed that the maximum stay time is 30 minutes. The protection level can also be adjusted. If the dose rate in a certain area exceeds the standard, the shielding measures in that area can be upgraded, such as increasing the thickness of the lead plate.

[0067] 5. Ingestion Dosage Calculation Results: The results of the ingested internal radiation dose provide guidance for safety personnel in managing on-site food and handling contaminated materials. Regarding on-site food management, it is prohibited to eat or drink food in areas with excessive ingestibility, such as areas with high vegetation deposition activity. Regarding handling contaminated materials, personnel are reminded to wash their hands after contact with contaminated soil to avoid accidental ingestion.

[0068] 6. Dose Weighting Calculation Results: The result of the total external radiation dose weighting factor can help safety personnel optimize protection strategies. If external radiation contributes significantly, such as accounting for 70%, then the "shielded area" should be expanded first; if internal radiation contributes significantly, such as accounting for 50%, then all personnel should be equipped with protective equipment such as gas masks first.

[0069] Optionally, in step 104, in the terrain model of the detonation site, taking the detonation location as the diffusion center, and combining the spatial diffusion pattern of radioactive materials and the duration of pollution, as well as the preset shift duration of emergency response personnel, the shift schedule for emergency response personnel at the detonation site is determined, including: Step 1041: In the terrain model of the detonation site, with the detonation location as the diffusion center, different contaminated areas are divided according to the distribution of radioactive material concentration at different times and spatial locations. The contaminated areas include high-contamination areas, medium-contamination areas, and low-contamination areas with decreasing radioactive material concentrations. The radioactive material concentration in the high-contamination area exceeds a preset multiple of the preset safety threshold, the radioactive material concentration in the medium-contamination area is between a preset multiple of the preset safety threshold and the preset safety threshold, and the radioactive material concentration in the low-contamination area is below the preset safety threshold. Step 1042: For different contaminated areas, use the immersion dose calculation method to assess the immersion dose for emergency response personnel in each contaminated area. Step 1043: Based on the preset maximum radiation dose limit that emergency response personnel can accept in a single shift, and the immersion dose assessment results of each contaminated area, determine the allowable stay time for emergency response personnel in each contaminated area. Step 1044: Determine the shift schedule for emergency response personnel at the detonation site based on the allowable stay time and preset shift duration for each contaminated area.

[0070] In the above embodiments of this application, in the terrain model of the detonation site, the detonation location is taken as the diffusion center. Combining the spatial diffusion pattern of radioactive materials, the duration of contamination, and the preset shift duration for emergency response personnel, the shift schedule for emergency response personnel at the detonation site is determined. For example, this can be done according to the following steps: 1. Clarify the diffusion characteristics and key parameters of radioactive materials: Spatial diffusion patterns: The diffusion direction and range of radioactive materials can be determined based on their diffusion characteristics in the air, such as the influence of wind direction, wind speed, and atmospheric stability. For example, under stable atmospheric conditions, a radioactive plume may diffuse in a fan shape; under unstable atmospheric conditions, the diffusion range may be wider and more irregular. Furthermore, clarifying the changes in the concentration distribution of radioactive materials in the air at different time points can be achieved through prior plume pollution calculations, revealing the concentration distribution of radioactive materials at different times and spatial locations.

[0071] Duration of contamination: This determines the duration of contamination caused by radioactive materials at the detonation site. This duration is influenced by various factors, such as the half-life of the radionuclide and meteorological conditions, such as rainfall, which can accelerate the settling and removal of contaminants. For example, some short-half-lived radionuclides may experience a significant reduction in contamination levels within hours to days, while long-half-lived radionuclides may continue to cause contamination for weeks or even longer.

[0072] Preset shift duration: The shift duration of data collection personnel and safety protection personnel can be preset according to the nature and requirements of emergency response work, such as a shift cycle of 4 hours or 6 hours.

[0073] 2. Classification of pollution areas by level: Based on concentration distribution: In the terrain model of the detonation site, with the detonation location as the center, different contamination levels are divided according to the concentration distribution of radioactive materials at different times and spaces. For example, it can be divided into high-contamination areas (radioactive material concentration exceeds the preset safety threshold by several times), medium-contamination areas (concentration between the preset safety threshold and the high-contamination area concentration), and low-contamination areas (concentration below the preset safety threshold).

[0074] Considering diffusion trends: Combining the spatial diffusion patterns of radioactive materials, predict the changing trends of contaminated areas at different points in time, such as whether the contaminated areas will expand, shrink, or move in a specific direction, so as to dynamically adjust the classification of contaminated areas.

[0075] 3. Assess the radiation dose to personnel in each contaminated area: Immersion dose assessment: For different contaminated areas, the immersion dose for emergency response personnel in each area is obtained using immersion dose calculation methods. Based on the aforementioned immersion dose calculation method, if the exposure dose rate can be obtained, it is multiplied by the preset shift duration to obtain the immersion dose; if the exposure dose rate cannot be obtained, the exposure dose rate is calculated using the time-integrated air activity calculated from the plume pollution, combined with the gamma-ray constant of the radioactive nuclides. When the radioactive material includes multiple nuclides, the total immersion dose is obtained by summing the immersion doses of each nuclide.

[0076] In particular, other dose assessments can be used as supplementary references. Although the determination of shifts is mainly based on immersion dose, the results of other dose calculations such as inhalation dose and ingestion dose can also be comprehensively considered to fully assess the radiation risk to personnel in each contaminated area. For example, in highly contaminated areas, the inhalation dose may also be higher, requiring further emphasis on respiratory protection measures.

[0077] 4. Determine the permissible stay time in each contaminated area: Based on safe dose limits: The maximum permissible radiation dose limit for emergency response personnel during a single shift, as stipulated by relevant national and industry standards, can be used to determine the permissible stay time for emergency response personnel in different contaminated areas, in conjunction with the immersion dose assessment results for each contaminated area. For example, if the calculated immersion dose in a highly contaminated area exceeds the safe dose limit within the preset shift duration, the stay time in that area must be shortened to ensure that the radiation dose received by personnel remains within safe limits.

[0078] In particular, individual differences and protective measures should also be considered. That is, when determining the permissible stay time, the individual differences of emergency response personnel, such as age and health status, as well as the effectiveness of protective measures taken, such as wearing protective clothing and gas masks, in reducing radiation dose, should also be taken into account. For example, wearing high-efficiency protective equipment can appropriately extend the stay time in the contaminated area.

[0079] 5. Arrange shift schedules: Data collection personnel shift arrangements: Data collection personnel need to go deep into contaminated areas to collect data. Based on the allowed stay time in each contaminated area and the preset shift length, the shift schedule for data collection personnel should be reasonably arranged. For example, in highly contaminated areas, due to the shorter allowed stay time, multiple short shifts may need to be arranged to ensure the continuous data collection work while protecting personnel safety; in low-contaminated areas, the shift time can be appropriately extended to improve work efficiency.

[0080] Safety personnel shift arrangements: Safety personnel are responsible for ensuring overall on-site safety. Their shift arrangements must comprehensively consider the monitoring of each contaminated area, the deployment and adjustment of protective measures, and other related tasks. Based on the risk level of different contaminated areas and the focus of safety protection work, the shift schedule for safety personnel should be rationally arranged to ensure that there is always sufficient safety protection force on-site for control throughout the duration of pollution. For example, around highly polluted areas and at key protection nodes, dedicated personnel should be assigned to conduct real-time monitoring and protective operations, and the shift interval can be appropriately shortened according to the actual situation.

[0081] In particular, shift schedules can be dynamically adjusted, for example: Real-time monitoring and feedback: During emergency response, the spread of radioactive materials, changes in contaminated area concentrations, and radiation doses received by on-site personnel can be continuously monitored in real time. Relevant information is acquired promptly through on-site monitoring equipment and data transmission systems, and the monitoring results are fed back to the command center.

[0082] Adjusting shifts based on changes: Based on real-time monitoring feedback, if the contaminated area expands, concentration increases, or radiation doses received by personnel approach safety limits, the shift schedules of emergency response personnel should be dynamically adjusted in a timely manner. For example, the number of personnel on duty in highly contaminated areas may be increased or shift times may be shortened to ensure personnel safety; if the contamination situation eases, shift arrangements can be appropriately optimized to improve work efficiency.

[0083] Furthermore, for example, it can be done Figure 10 In the protection guide generation interface of the main output module, from the work shift plan interface ( Figure 3 The dose limits, shift times, stay times, and respirator protection factors are transferred from the dose weighting calculation interface. Figure 9 The total dose is transferred in. If the total dose is less than or equal to the dose limit, click the return limit calculation button to generate the return limit (dose rate, exposure rate, alpha activity, beta activity, and radionuclide activity). If the total dose is greater than the dose limit, click the shift time, stay time, and respirator protection factor adjustment buttons until the total dose is less than or equal to the dose limit, and then click the return limit calculation button again to generate the return limit. The shift time, stay time, respirator protection factor, and any one or any combination of return limits for dose rate, exposure rate, alpha activity, beta activity, and radionuclide activity that meet the dose limit constitute the numerical protection guideline.

[0084] Optionally, the on-site terrain parameters include the area type of the detonation location as determined by on-site survey, the surrounding vegetation type, and at least one of the following: ground material, building type, building geometry, and building material of the building at the detonation location. The area type includes urban, suburban, and rural areas; the surrounding vegetation type includes vines, herbs, shrubs, and trees; the ground material includes asphalt, cement, sand, gravel, plastic, and soil; the building type includes residential, commercial, industrial, agricultural, transportation, energy, educational, and medical buildings; the building geometry includes area, height, thickness, and number of floors; and the building materials include structural materials, decorative materials, and special materials. Structural materials include concrete, steel, stone, and wood; decorative materials include paint, varnish, tiles, and glass; and special materials include fireproof, moisture-proof, thermal insulation, and sound insulation materials.

[0085] In the above embodiments of this application, the following content can be stored as default environment media parameters. Figure 6 In the main data module, the data master module is used for parameter maintenance. It includes one sub-module for correction factors and parameters for radioactive materials, field surveys, environmental media, work shifts, inhalation / ingestion, identified radionuclides, and unit conversion parameters (such as...). Figure 15 Seven main interfaces are implemented. The output of the correction factor submodule is stored in the main data module as the default environment medium parameter.

[0086] Specifically, in the correction factor submodule of the main data module, the surface morphology, land cover features, and environmental conditions of sites that may have been or have already been hit by RDDs are modeled, and correction factors (deposition pollution distribution factor, roughness factor, weathering factor, resuspension factor, resuspension multiplier, building protection factor, etc.) are calculated for functions of regional type (urban, suburban, rural, etc.), ground material (asphalt, cement, sand, gravel, plastic, soil, etc.), vegetation type (vines, herbs, shrubs, trees, etc.), building type (residential, commercial, industrial, agricultural, transportation, energy, education, medical, etc.), building geometry (area, height, thickness, number of floors, etc.), building material (concrete, steel, stone, wood, etc. structural materials; paint, varnish, tiles, glass, etc. decorative materials; fireproof, moisture-proof, heat-insulating, etc. special materials), climate index (dry, humid, etc.), meteorological index (temperature, wind, etc.), traffic index (smooth, congested, etc.), and activity index (slight, severe, etc.).

[0087] The technical solution of this embodiment can be applied to a numerical protection system for radiation emergency response personnel. The system consists of four main modules (input, calculation, output, and data) and one sub-module (correction factor). A user-friendly interface guides users through the system's operation, providing various options from data entry and calculation execution to result display and parameter maintenance. The operation is simple and easy to understand. The input module is used for data entry, implemented through two main interfaces: detonation site survey and work shift planning. The calculation module performs calculations, implemented through seven main interfaces: plume contamination calculation, deposition contamination calculation, deposition dose calculation, immersion dose calculation, inhalation dose calculation, ingestion dose calculation, and dose weight calculation, as well as two sub-interfaces: particle size-weighted average plume deposition rate calculation and weathering factor calculation. The output module displays results through one main interface: numerical protection guide.

[0088] In one specific embodiment, a numerical protection guideline can be generated using a "conceptual model" and "big data preprocessing techniques." The conceptual model is used to calculate the numerical protection guideline using simple equations (addition, multiplication, and exponentiation) based on various correction factors. The big data preprocessing techniques are used to provide the necessary correction factors for the calculations related to the conceptual model through detailed calculations based on modeling specific surface morphology, land cover features, and environmental conditions at the RDD detonation site.

[0089] This "conceptual model" divides RDD radiological emergency response into two phases: the initial phase and the later phase, with the time boundary defined as the completion of plume deposition. The completion of plume deposition is relative to the RDD detonation time. At this point, the radioactive material released from the RDD has been completely deposited, sufficient data has been obtained to map radioactive contamination contour lines, and the conditions are met for making detailed arrangements for emergency personnel to carry out specific emergency response tasks at specific times and locations within the RDD detonation site.

[0090] This "conceptual model" is based on different sources of pollution in two stages of radiation emergency response. It classifies radioactive pollution into two categories: plume pollution and sediment pollution. The pollution level is represented by time-integrated air activity and sediment activity, respectively. It considers four types of radiation pathways: external radiation through sedimentation, external radiation through immersion, internal radiation through inhalation, and internal radiation through accidental ingestion.

[0091] This "conceptual model" starts with the depositional contamination at the completion of plume deposition, using various correction factors pre-generated by "big data preprocessing technology" to achieve rapid calculation of numerical protection guidelines. These include: 1) using a partition factor to correct for the distribution of depositional contamination, and simultaneously using the Bateman equation to simulate the radioactive decay and growth of depositional contamination; 2) using a weathering factor to correct for the reduction of depositional contamination due to physical processes, and simultaneously using a roughness factor to correct for the external radiation dose from depositional contamination from different non-infinitely flat planes; 3) assuming contact between plume contamination and depositional contamination, for the initial stage of detonation, using the plume deposition velocity, deriving the time-integrated air activity forward from the depositional activity at the completion of plume deposition, for use in... Calculate the immersion external and inhalation internal radiation doses from plume contamination; for the later stages of detonation, use a resuspension factor to derive resuspension parameters from the depositional activity at the completion of plume deposition, and use these parameters to calculate the immersion external and inhalation internal radiation doses from resuspension of deposited contamination. Simultaneously, use resuspension multipliers to correct for the resuspension factor affected by different meteorological conditions, traffic conditions, and human activities; 4) Use a building protection factor to correct for the dose reduction from outdoor contamination due to being inside a building; 5) Use a respirator protection factor to correct for the dose reduction from inhalation internal radiation due to wearing a respirator; 6) Use an identification nuclide correction factor to correct for the numerical protection guidelines after identifying radioactive materials used in RDD manufacturing.

[0092] The correction factors required for the calculations related to this "conceptual model" are based on the surface morphology of the RDD detonation site, namely socio-economic elements (residential areas, engineering buildings, transportation lines, etc.) and natural geographical elements (topography, soil, vegetation, etc.), especially the feature modeling of densely populated areas, and taking into account the influence of environmental conditions. They are defined as functions of region type (urban, suburban, rural, etc.), ground material (asphalt, cement, sand, plastic, soil, etc.), vegetation type (vines, herbs, shrubs, trees, etc.), building type (residential, commercial, industrial, agricultural, transportation, energy, education, medical, etc.), building geometry (area, height, thickness, number of floors, etc.), building material (concrete, steel, stone, wood, etc. structural materials; paint, varnish, tiles, glass, etc. decorative materials; fireproof, moisture-proof, heat-insulating, etc. special materials), climate index (dry, humid, etc.), meteorological index (temperature, wind, etc.), traffic index (smooth, congested, etc.), and activity index (slight, severe, etc.). They are generated in advance before RDD detonation or quickly after RDD detonation for user use and maintenance.

[0093] By applying the above embodiments of this application, a conceptual model was established that uses big data preprocessing technology to clean the data into simple functions related to correction factors such as depositional contamination distribution factors, roughness factors, weathering factors, resuspension factors, resuspension multipliers, and building protection factors. This model then uses simple equations (addition, multiplication, and exponentiation) to calculate numerical protection guidelines. Based on this conceptual model, an interface system providing users with various options was established. This system is simple to operate, easy to understand, calculates quickly, and produces accurate results. The generated numerical protection guidelines are commensurate with specific contamination scenarios caused by RDD detonation and the necessary emergency response tasks and their execution sequence, making it an effective tool for ensuring the radiation safety of personnel handling RDD radiation emergencies. It can generate a set of numerical protection guidelines commensurate with radioactive materials used in RDD manufacturing, specific contamination scenarios caused by RDD detonation, and the necessary emergency response tasks and their execution sequence. It also features a user-friendly interface providing various options, fast calculation, accurate results, simple operation, and easy understanding, making it an effective tool for ensuring the radiation safety of personnel handling RDD radiation emergencies.

[0094] In another specific embodiment, it can be applied to a numerical protection system for personnel handling radiation emergency situations. This system only requires any one of the measured values ​​of dose rate, exposure rate, alpha activity, beta activity, or nuclide activity at the RDD detonation site. It can process any radionuclide or nuclide from Pu-239, Am-241, Cm-244, Po-210, Pu-238, Cf-252, Ra-226, Sr-90, Co-60, Cs-137, Tm-170, Ir-192, Se-75, or Yb-169. This system provides radiation emergency response for RDDs manufactured in combination that cause radiation contamination of any one or any combination of α, β, γ, and EC. It can use Pu-239, Po-210, Sr-90, and Co-60 as dose rate, exposure rate, α activity, and β activity markers, respectively, in situations where the materials used in the initial manufacturing of the RDD are unknown. It can provide numerical protection guidelines that meet dose limits, including shift times, dwell time, respirator protection, and return limits for any one or any combination of dose rate, exposure rate, α activity, β activity, and radionuclide activity.

[0095] Numerical protection guidelines can be generated using only any one of the measured values ​​for dose rate, exposure rate, alpha activity, beta activity, and nuclide activity. It can handle scenarios where any or any combination of radionuclides, such as Pu-239, Am-241, Cm-244, Po-210, Pu-238, Cf-252, Ra-226, Sr-90, Co-60, Cs-137, Tm-170, Ir-192, Se-75, and Yb-169, are used as materials for RDD manufacturing. It can handle scenarios involving radioactive contamination from RDD detonation, including any or any combination of alpha, beta, gamma, and extracorporeal radiation. It demonstrates methods for handling radiation emergency situations where the materials used in RDD manufacturing are unknown, using Pu-239, Po-210, Sr-90, and Co-60 as dose rate, exposure rate, alpha activity, and beta activity markers, respectively. Rapid calculations are achieved using correction factors, simple equations, and conceptual models. Using big data preprocessing technology, the numerical protection guideline is cleaned of complex functions related to the surface morphology, land cover features, and environmental conditions of the RDD manufacturing radioactive materials and the RDD detonation site. These functions are then simplified into simpler functions related to correction factors such as sedimentary contamination distribution factors, roughness factors, weathering factors, resuspension factors, resuspension multipliers, and building protection factors, thereby achieving accurate calculations.

[0096] It can provide numerical protection guidelines that meet dose limits, including shift times, dwell times, respirator protection, and any combination of dose rate, exposure rate, alpha activity, beta activity, and radionuclide activity return limits. It includes 17 main interfaces for detonation site survey, shift planning, plume contamination calculation, deposition contamination calculation, deposition dose calculation, immersion dose calculation, inhalation dose calculation, ingestion dose calculation, dose weighting calculation, numerical protection guidelines, radioactive material parameters, site survey parameters, environmental medium parameters, shift parameters, inhalation and ingestion parameters, identified radionuclide parameters, and unit conversion parameters, as well as 2 sub-interfaces for particle size-weighted average plume deposition rate calculation and weathering factor calculation. It is compatible with scenarios specific to RDD radiation emergency response, including emergency incident investigation, plume contamination identification, detonation site survey, deposition contamination identification, shift planning, radiation dose prediction, protection guideline development, and necessary response tasks and their execution sequence based on survey requirements.

[0097] Furthermore, such as Figure 11 As shown, the radiation emergency response task can be carried out according to the following steps: An investigation into an RDD incident is the initial step in emergency response. It requires a comprehensive investigation of any RDD incident to collect basic information about the incident and provide foundational data for subsequent response efforts.

[0098] Determining the detonation time and location, and identifying whether plume contamination should be considered, helps determine the extent of contamination and the areas that may be affected. Assessing whether plume contamination needs to be considered—plume contamination refers to the contamination plume formed by the diffusion of radioactive materials in the air—will affect the scope and method of subsequent contamination surveys.

[0099] Contamination survey of the detonation site: After determining the detonation time and location and whether plume contamination should be considered, a contamination survey is conducted at the detonation site to understand the actual contamination situation.

[0100] Identifying the contaminated environmental media and their contamination levels, identifying the type of radiation and / or radionuclides, and determining the contaminated environmental media, such as air, soil, and water, are crucial for selecting appropriate protective measures and disposal methods. Identifying the type of radiation, such as alpha, beta, and gamma radiation, and / or specific radionuclides is also essential for selecting appropriate protective measures and disposal methods.

[0101] The document proposes a work shift plan and recommendations for surveying needs. The work shift plan, based on the pollution situation and personnel protection requirements, rationally arranges staff shifts to reduce radiation dose and ensure personnel safety. The surveying needs recommendations, based on the previous survey results, propose further surveying needs and recommendations to ensure a comprehensive understanding of the pollution situation.

[0102] Based on the previous investigation, survey and analysis results, specific protection guidelines and recommendations are proposed, including the selection of personal protective equipment and the implementation of protective measures, in order to reduce the harm of radiation to personnel.

[0103] Perform other emergency response tasks such as access control, public evacuation, and search and rescue. For example, access control involves controlling access to and from the contaminated area to prevent unauthorized personnel from entering and to avoid the spread of radiation hazards. Public evacuation involves promptly organizing the evacuation of the public from threatened areas to safe zones, based on the degree and extent of contamination, to ensure public safety.

[0104] Search and rescue: Searching for and rescuing people who may be suffering from radiation damage or trapped in contaminated areas, ensuring that they receive timely assistance and treatment.

[0105] By implementing the above steps in an orderly manner, radiation emergency response tasks can be carried out systematically and effectively, minimizing radiation hazards and protecting the lives of personnel and the stability of the environment.

[0106] A conceptual model of RDD radioactive contamination is shown below. Figure 12 As shown in the figure, the RDD correction factor calculation model is illustrated in the figure. Figure 13 As shown.

[0107] The process of generating the RDD numerical protection guidelines can also include, for example: Figure 14 As shown, the core logic is "environmental adaptation correction - multi-source parameter integration - precise dose calculation - graded protection output," combined with the synergistic effect of the "correction factor module, data module, input module, calculation module, and output module" shown in the diagram, implemented step by step. Specifically: The core function of the correction factor module is to generate "environmental correction factors" for different terrains, land features, and environmental conditions. This addresses the issue of "differences in the diffusion / deposition patterns of radioactive materials in complex environments," such as how tall buildings in cities can block plume diffusion, and how asphalt surfaces deposit pollutants more easily than soil. The specific operation is as follows: 1. Input environmental characteristic parameters: Collect information on the detonation site's regional type (urban / suburban / rural), ground material (asphalt / cement / soil), vegetation type (herbaceous / shrub / tree), building characteristics (type / height / density), building materials (concrete / steel / wood), meteorological conditions (wind speed / wind direction / humidity), traffic conditions (congested / smooth), and activity scene (residential area / commercial area / industrial area).

[0108] 2. Big Data Generation Correction Factors: By analyzing the impact of different environmental conditions on radioactive diffusion / deposition through big data analysis, for example, if the plume diffusion rate in urban areas is 30% lower than that in rural areas, the correction factor is 0.7. The system outputs topographic correction factors, land cover correction factors, meteorological correction factors, etc., to adjust the accuracy of subsequent pollution calculations.

[0109] Next, the data module, the data hub of the "Numerical Protection Guidelines," needs to integrate multi-dimensional parameters such as radiation source characteristics, on-site monitoring, environmental media, and personnel working patterns to provide a basis for calculations. Specifically, this includes: Radioactive material parameters: type of radionuclide, such as Cs-137, Co-60, activity (i.e., total radioactivity), half-life, and gamma-ray constant are used to calculate external radiation dose; Field monitoring parameters: On-site measured air radioactivity concentration, soil sediment activity, dose rate, etc. If on-site measurement is not possible, it needs to be inferred from the model. Environmental media parameters: type of polluted environmental media (air / soil / water / vegetation) and range of pollution; Work shift parameters: shift duration for emergency personnel (e.g., 4 hours / shift), work area (high / medium / low pollution zone), and stay time; Inhalation / ingestion parameters: respiratory rate of the person (e.g., 1.2 m³ / h), inhalation fraction (the proportion that enters the deep respiratory tract, e.g., 0.75), and ingestion amount (if accidental ingestion is involved, e.g., 0.5 kg / day). Auxiliary parameters: calibration parameters of the labeling device (accuracy correction of the monitoring equipment), unit conversion factors, such as the conversion between Bq and Ci.

[0110] Next, the input module needs to transform the actual pollution situation on site and personnel work arrangements into the "boundary conditions" for calculation, ensuring that the calculation closely matches the real-world emergency response scenario: 1. Detonation site survey: Through on-site monitoring, such as portable gamma spectrometers and aerosol samplers, the contaminated area is divided into high / medium / low contamination areas, the distribution of radioactive concentration in each area, and the type of contaminant. For example, the high contamination area is concentrated within 500 meters northwest of the detonation point, with an air concentration of 1000 Bq / m³ and a soil sediment activity of 5000 Bq / kg. 2. Work shift plan: Clearly define the job type (data collection / safety protection), work area, shift length, and task content of emergency personnel. For example, data collection personnel need to enter the high-pollution area and change shifts every 4 hours; safety protection personnel are on duty in the medium-pollution area and change shifts every 6 hours.

[0111] Next, the calculation module is the core. Based on the previous correction factors, basic data, and on-site input, it needs to complete seven key calculations to quantify the radiation dose to personnel in different scenarios: 1. Plume pollution calculation: Combining correction factors (meteorology / topography), radioactive source activity, and wind speed, simulate the diffusion process of radioactive plume in the air and output the air concentration distribution at different times / spaces. For example, 2 hours after detonation, the plume spreads 1 kilometer to the northwest and the concentration drops to 500 Bq / m³. 2. Calculation of sedimentation pollution: Combine the ground material correction factor and vegetation interception coefficient to calculate the sedimentation activity of radioactive materials in soil / water / vegetation. For example, if the sedimentation activity of asphalt surface is 20% higher than that of soil, then the corrected soil sedimentation activity is 4000 Bq / kg. 3. Calculation of deposition dose: Calculate the external radiation dose to personnel from radioactive materials deposited in the environmental medium, such as the gamma radiation of Cs-137 in soil, with a dose rate of 0.1 mSv / hour to personnel on the ground; 4. Immersion dose calculation: Calculate the external exposure dose of personnel from the gamma radiation of radioactive materials in the air. Formula: Dose rate × shift duration; if the dose rate cannot be measured, use "time integral air activity × gamma ray constant" for calculation. 5. Inhalation dose calculation: Calculate the internal radiation dose of personnel inhaled by radioactive aerosols using the formula: air concentration × breathing rate × shift length × inhalation fraction × radionuclide inhalation dose conversion factor; 6. Calculation of ingested dose: Calculate the internal radiation dose of accidentally ingested contaminated food / water using the formula: Ingested amount × Contaminant activity in the medium × Nucleotide dose conversion factor; 7. Dose weighting calculation: Calculate the contribution ratio of external irradiation (immersion + deposition) and internal irradiation (inhalation + ingestion). For example, if external irradiation accounts for 70%, then the focus of protection should be on "protection against gamma rays".

[0112] Next, the output module needs to combine the calculation results with personnel job requirements to generate targeted and actionable numerical protection guidelines, such as "Personnel staying in highly polluted areas for ≤1 hour must wear Grade A protective clothing." Specifically, this should cover the following: 1. Regional Classified Protection: Based on the calculation results of plume / sediment pollution, high, medium and low pollution zones are divided, and the allowable stay time and required protective equipment for each zone are specified. For example, in high pollution zones, Class A protective clothing and HEPA filter masks are required; in medium pollution zones, Class B protective clothing and gas masks are required; and in low pollution zones, Class C protective clothing and face masks are required. 2. Job-specific protection: Data collection personnel: Based on immersion / inhalation dose calculations, clarify "the maximum stay time in a highly polluted area, such as 4 hours, with personal dose monitoring required every hour, and evacuation required if it exceeds 0.5 mSv"; For safety personnel stationed around the contaminated area: based on sediment / ingestion dose calculations, it should be determined that "the location of the station must be far away from the downwind side of the plume, shifts must be changed every 6 hours, and the pollution level of the environmental media must be tested regularly"; 3. Emergency Operation Guidelines: These include access control, closing entrances to high-pollution areas, public evacuation (requiring evacuation to 2 kilometers upwind of the plume), protective measures for rescue personnel, carrying portable dosimeters, and taking doses every 30 minutes.

[0113] Furthermore, as Figure 1 In terms of specific implementation, this application provides a numerical protection system for radiation emergency response personnel, such as... Figure 16 As shown, the system includes: The on-site terrain parameter acquisition module 201 is used to acquire the on-site terrain parameters of the detonation location of the radioactive dispersing device; The detonation site terrain model construction module 202 is used to retrieve the prefabricated terrain model corresponding to the detonation location from the prefabricated terrain library, and fine-tune the prefabricated terrain model of the detonation location using the site terrain parameters to obtain the detonation site terrain model. The prefabricated terrain library includes prefabricated terrain models that are prefabricated for multiple geographical locations. Radioactive material determination module 203 is used to determine the spatial diffusion pattern and duration of contamination of radioactive materials released after the detonation of the radioactive dispersing device. The emergency personnel shift determination module 204 is used to determine the shifts of emergency personnel at the detonation site in the terrain model of the detonation site, taking the detonation location as the diffusion center, and combining the spatial diffusion law of radioactive materials and the duration of pollution, as well as the preset shift duration of emergency personnel. The emergency personnel include data collection personnel and safety protection personnel. The radioactive contamination dose effect calculation module 205 is used to perform calculations for plume contamination, sediment contamination, sediment dose, immersion dose, inhalation dose, ingestion dose, and dose weight for the detonation site, and obtain the calculation results for each calculation. The numerical protection guide generation and display module 206 is used to determine the required numerical protection guide for any type of emergency response personnel based on the shift schedule and required calculation results determined by the emergency response personnel, and display it on the preset terminal interface corresponding to the emergency response personnel, so that the emergency response personnel can carry out emergency response work with the numerical protection guide displayed on the preset terminal interface.

[0114] It should be noted that other corresponding descriptions of the functional units involved in the numerical protection system for radiation emergency response personnel provided in this application embodiment can be found by referring to... Figure 1 The corresponding descriptions in the method will not be repeated here.

[0115] Based on the above, Figure 1 Accordingly, this application also provides a medium on which a computer program is stored, which, when executed by a processor, implements the above-described method. Figure 1 Numerical protection methods for personnel handling radiation emergencies are shown.

[0116] Based on this understanding, the technical solution of this application can be embodied in the form of a software product, which can be stored in a non-volatile medium (such as CD-ROM, USB flash drive, mobile hard drive, etc.) and includes several instructions to enable a device (such as personal computer, server, or network device, etc.) to execute the methods described in various implementation scenarios of this application.

[0117] Based on the above, Figure 1 The method shown, and Figure 16 To achieve the above objectives, the virtual system embodiment shown in this application also provides a device, which may be a personal computer, server, network device, etc. This device includes a medium and a processor; the medium is used to store a computer program; the processor is used to execute the computer program to achieve the above-described objectives. Figure 1 Numerical protection methods for personnel handling radiation emergencies are shown.

[0118] Optionally, the device may also include a user interface, a network interface, a camera, radio frequency (RF) circuitry, sensors, audio circuitry, a Wi-Fi module, etc. The user interface may include a display screen, input units such as a keyboard, etc., and optional user interfaces may also include USB interfaces, card reader interfaces, etc. The network interface may optionally include standard wired interfaces, wireless interfaces (such as Bluetooth interfaces, Wi-Fi interfaces), etc.

[0119] Those skilled in the art will understand that the device structure provided in this embodiment does not constitute a limitation on the device, and may include more or fewer components, or combine certain components, or have different component arrangements.

[0120] The medium may also include an operating system and a network communication module. The operating system is a program that manages and stores the device's hardware and software resources, supporting the operation of information processing programs and other software and / or programs. The network communication module is used to enable communication between the various components within the medium, as well as communication with other hardware and software within the physical device.

[0121] Through the above description of the embodiments, those skilled in the art can clearly understand that this application can be implemented by means of software plus necessary general-purpose hardware platforms, or by hardware implementation using on-site terrain parameters to fine-tune the prefabricated terrain model of the detonation location to obtain the detonation site terrain model. Taking the detonation location as the diffusion center, combined with the spatial diffusion law of radioactive materials, the duration of pollution, and the preset shift duration, the shift schedule of emergency response personnel is determined; respectively, plume pollution calculation, deposition pollution calculation, deposition dose calculation, immersion dose calculation, inhalation dose calculation, ingestion dose calculation, and dose weight calculation are performed. Based on the shift schedules determined by each type of emergency response personnel and the required calculation results, numerical protection guidelines are determined and displayed respectively. It can perform unified calculations based on the same data source, and display the required data and shift schedules in a targeted manner for different types of emergency response personnel, so as to achieve real-time shared numerical protection.

[0122] Those skilled in the art will understand that the accompanying drawings are merely schematic diagrams of a preferred embodiment, and the modules or processes shown in the drawings are not necessarily essential for implementing this application. Those skilled in the art will understand that the modules in the system of the embodiment scenario can be distributed throughout the system of the embodiment scenario as described, or they can be modified to reside in one or more systems different from this embodiment scenario. The modules of the above-described embodiment scenario can be combined into one module, or further divided into multiple sub-modules.

[0123] The serial numbers in this application are for descriptive purposes only and do not represent the superiority or inferiority of any particular implementation scenario. The above disclosures are merely a few specific implementation scenarios of this application; however, this application is not limited thereto, and any modifications that can be made by those skilled in the art should fall within the protection scope of this application.

Claims

1. A numerical protection method for personnel handling radiation emergency situations, characterized in that, The method includes: Obtain the on-site topographic parameters of the detonation location of the radioactive dispersal device; The prefabricated terrain model corresponding to the detonation location is retrieved from the prefabricated terrain library. The prefabricated terrain model of the detonation location is fine-tuned using the on-site terrain parameters to obtain the detonation site terrain model. The prefabricated terrain library includes prefabricated terrain models that are prefabricated for multiple geographical locations. Determine the spatial diffusion patterns and duration of contamination of radioactive materials released after the detonation of a radioactive dispersal device; In the terrain model of the detonation site, the detonation location is taken as the diffusion center. Combining the spatial diffusion law of radioactive materials and the duration of pollution, as well as the preset shift time of emergency response personnel, the shift schedule of emergency response personnel at the detonation site is determined. The emergency response personnel include data collection personnel and safety protection personnel. Calculations were performed on plume pollution, sediment pollution, sediment dose, immersion dose, inhalation dose, ingestion dose, and dose weight for the detonation site, and the results of each calculation were obtained. For any type of emergency response personnel, based on the shift schedule determined by the emergency response personnel and the required calculation results, the numerical protection guidelines required by the emergency response personnel are determined and displayed on the preset terminal interface corresponding to the emergency response personnel, so that the emergency response personnel can carry out emergency response work with the numerical protection guidelines displayed on the preset terminal interface.

2. The method according to claim 1, characterized in that, Calculations were performed on the plume contamination at the detonation site, and the results were obtained, including: Determine the plume deposition rate at the detonation site based on Stokes' law; Obtain the plume size at the detonation site; Based on the distribution ratio of radioactive materials in the air and in sediments, the sediment contamination partition factor is determined. The radioactivity in the air at the detonation site is measured and integrated to obtain the time-integrated air activity. If the radioactivity in the air cannot be measured, the time-integrated air activity is inferred from the plume deposition rate. Based on plume deposition rate, plume size, time-integrated air activity, and depositional contamination distribution factor, the diffusion process of radioactive plumes released after the detonation of a radioactive dispersing device in the air is simulated, and the concentration distribution of radioactive materials at different times and spatial locations after detonation is obtained as the plume contamination calculation results.

3. The method according to claim 1, characterized in that, Depositional contamination calculations were performed at the detonation site, and the results were obtained, including: Obtain the original sedimentary activity of various environmental media at the detonation site; For any environmental medium, the weathering constant and resuspension factor are used to correct the change of the original sedimentary activity of the environmental medium over time, so as to obtain the final sedimentary activity of the environmental medium. Based on the final deposition activity of various environmental media, the deposition activity distribution of radioactive materials in the environmental media at different times and spatial locations at the detonation site is generated as the result of deposition pollution calculation.

4. The method according to claim 3, characterized in that, Deposition dose calculations were performed at the detonation site, and the results were obtained, including: Calculate the dose rate corresponding to each environmental medium; For any given environmental medium, based on the dose rate of the environmental medium, the radiation exposure of emergency response personnel at the detonation site during emergency response is quantified to obtain the deposition dose of the environmental medium. Based on the quantified deposition doses of various environmental media at the detonation site, the total deposition dose is obtained as the result of deposition pollution calculation.

5. The method according to claim 2, characterized in that, Submersion dose, inhalation dose, ingestion dose, and dose weighting were calculated for the detonation site, yielding various calculation results, including: For immersion dose calculation, the radiation dose rate at the detonation site is obtained, and the radiation dose rate is multiplied by the preset shift length of the emergency response personnel to obtain the immersion dose for the emergency response personnel as the immersion dose calculation result. If the radiation dose rate is not obtained, the radiation dose rate is calculated by using the time integral air activity calculated from the plume pollution and combining it with the gamma-ray constant of the radioactive material. When the radioactive material includes multiple nuclides, the total immersion dose is obtained by summing the immersion doses of each nuclide as the immersion dose calculation result. For inhalation dose calculation, the inhalation activity at the detonation site is obtained, and the inhalation activity is multiplied by the radionuclide inhalation dose conversion coefficient to obtain the inhaled internal radiation dose for emergency response personnel as the inhalation dose calculation result. If the inhalation activity is not obtained, the inhalation activity is calculated using the time integral air activity calculated from the plume pollution and the respiratory parameters of the emergency response personnel. The respiratory parameters include at least one of the following: respiratory rate, preset shift duration, and inhalation fraction. The inhalation fraction represents the proportion of the inhalation into the deep respiratory tract. For the calculation of ingestion dose, the ingestion activity at the detonation site is obtained, and the ingestion activity is multiplied by the nucleoside ingestion dose conversion coefficient to obtain the internal radiation dose of accidental ingestion as the ingestion dose calculation result. If the ingestion activity is not obtained, the time integral air activity calculated from the plume pollution is used, and the ingestion activity is calculated by combining the adhesion coefficient and the ingestion amount. For dose weighting calculation, the total external radiation dose is obtained based on the deposited external radiation dose and the immersion external radiation dose. The total dose is obtained based on the inhaled internal radiation and the ingested internal radiation. By calculating the ratio between the total external radiation dose and the total dose, the total external radiation dose weighting factor used to characterize the contribution ratio of external radiation to the total risk is obtained as the dose weighting calculation result.

6. The method according to claim 1, characterized in that, For any type of emergency response personnel, based on the shift schedule determined by the emergency response personnel and the required calculation results, the required numerical protection guidelines for the emergency response personnel are determined and displayed on the preset terminal interface corresponding to the emergency response personnel, including: For data collection personnel, based on the calculation results of plume pollution, sediment pollution, sediment dose, immersion dose, inhalation dose, dose weight, and the shift schedule determined by the data collection personnel, numerical protection guidelines for data collection personnel are determined and displayed on the preset terminal interface; For safety personnel, based on the calculation results of plume pollution, sediment pollution, sediment dose, immersion dose, ingestion dose, dose weight, and the shift schedule determined by the safety personnel, numerical protection guidelines for data collection personnel are determined and displayed on the preset terminal interface.

7. The method according to claim 2, characterized in that, In the terrain model of the detonation site, with the detonation location as the diffusion center, and considering the spatial diffusion patterns of radioactive materials, the duration of contamination, and the pre-set shift schedules for emergency response personnel, the shift schedules for emergency response personnel at the detonation site are determined, including: In the terrain model of the detonation site, with the detonation location as the diffusion center, different contaminated areas are divided according to the distribution of radioactive material concentration at different times and spatial locations. The contaminated areas include high-contamination areas, medium-contamination areas, and low-contamination areas with decreasing radioactive material concentrations. The radioactive material concentration in the high-contamination area exceeds the preset safety threshold by a preset multiple, the radioactive material concentration in the medium-contamination area is between the preset safety threshold by a preset multiple and the preset safety threshold, and the radioactive material concentration in the low-contamination area is below the preset safety threshold. For different contaminated areas, the immersion dose calculation method is used to assess the immersion dose for emergency response personnel in each contaminated area. Based on the preset maximum radiation dose limit that emergency response personnel can receive in a single shift, and the immersion dose assessment results of each contaminated area, the allowable stay time for emergency response personnel in each contaminated area is determined. Based on the permitted stay time and preset shift length for each contaminated area, the shift schedule for emergency response personnel at the detonation site is determined.

8. A numerical protection system for personnel handling radiation emergency situations, characterized in that, The system includes: The on-site terrain parameter acquisition module is used to acquire the on-site terrain parameters of the detonation location of the radioactive dispersal device; The detonation site terrain model construction module is used to retrieve the prefabricated terrain model corresponding to the detonation location from the prefabricated terrain library, and to fine-tune the prefabricated terrain model of the detonation location using the site terrain parameters to obtain the detonation site terrain model. The prefabricated terrain library includes prefabricated terrain models that are prefabricated for multiple geographical locations. The radioactive material identification module is used to determine the spatial diffusion pattern and duration of contamination of radioactive materials released after the detonation of a radioactive dispersal device. The emergency personnel shift determination module is used to determine the shifts of emergency personnel at the detonation site in the terrain model of the detonation site, taking the detonation location as the diffusion center, and combining the spatial diffusion law of radioactive materials and the duration of pollution, as well as the preset shift duration of emergency personnel. The emergency personnel include data collection personnel and safety protection personnel. The radioactive contamination dose effect calculation module is used to perform calculations for plume contamination, sediment contamination, sediment dose, immersion dose, inhalation dose, ingestion dose, and dose weight for the detonation site, and obtain the calculation results for each type of calculation. The numerical protection guide generation and display module is used to determine the required numerical protection guide for any type of emergency response personnel based on their shift schedule and the required calculation results, and display it on the preset terminal interface corresponding to the emergency response personnel, so that the emergency response personnel can carry out emergency response work with the numerical protection guide displayed on the preset terminal interface.

9. A medium having a computer program stored thereon, characterized in that, When the computer program is executed by the processor, it implements the method for numerical protection of personnel in radiation emergency response as described in any one of claims 1 to 7.

10. An apparatus comprising a medium, a processor, and a computer program stored on the medium and executable on the processor, characterized in that, When the processor executes the computer program, it implements the method for numerical protection of personnel in radiation emergency response as described in any one of claims 1 to 7.

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