A nuclear accident protection decision method, system and computer readable storage medium

Abstract

The present application relates to the technical field of nuclear accident emergency, and discloses a nuclear accident protection decision method, a system and a computer readable storage medium, the nuclear accident protection decision method comprises the following steps: obtaining radioactive release information and local forecast meteorological field data; calculating OIL1 and OIL2 based on the radioactive release information and the local forecast meteorological field data; generating protection decision suggestions according to OIL1 and OIL2. The nuclear accident protection decision system comprises a data acquisition unit, a calculation unit and an auxiliary decision unit. The computer readable storage medium stores a control program, and the control program is executed by the processor to realize the above-mentioned nuclear accident protection decision method. The above-mentioned nuclear accident protection decision method, system and computer readable storage medium combine the local forecast meteorological field data, finely simulate the diffusion and transport of the radioactive plume, can improve the rationality and accuracy of the calculation results of OIL1 and OIL2, and improve the intervention effect.

Description

Technical Field

[0001] This invention relates to the field of nuclear accident emergency technology, and in particular to a nuclear accident protection decision-making method, system, and computer-readable storage medium. Background Technology

[0002] In the event of a nuclear accident at a nuclear power plant, the primary basis for recommending public protection actions and making corresponding decisions is the intervention principle and level of emergency exposure. Due to current capabilities and technologies for predicting, evaluating, and monitoring the evolution of nuclear accidents, the common practice when recommending and deciding on public protection actions according to the above principles is to divide the nuclear accident emergency into two phases: before radioactive release and after radioactive release has begun, making recommendations and decisions separately for each phase. In the pre-release phase, recommendations and decisions on public protection actions should be based on the nuclear accident conditions or the estimated expected dose for those conditions. In the phase after radioactive release, recommendations and decisions should be based on whether the dose that can be avoided when taking a specific protective action exceeds the prescribed general intervention level. However, in the phase after radioactive release, because the general intervention level is expressed in terms of preventable doses, it is difficult to measure rapidly in the field, making it quite challenging to recommend public protection actions and make decisions using the general intervention level in practice.

[0003] To improve the operability of universal intervention levels, the IAEA (International Atomic Energy Agency) introduced the concept of Operational Intervention Level (OIL) in IAEA-TECDOC-953. OIL refers to an easily measurable amount of radiation corresponding to a specific universal intervention level for public protection actions. IAEA-TECDOC-955 provides the default values ​​and assumptions for OIL. The default values ​​for OILs at the operational intervention level can be divided into two categories. One category is used when radioactive release has occurred but the patient is still exposed to radioactive plumes, such as OIL1 (plume environmental dose rate, mainly used for recommending and deciding on evacuation) and OIL2 (plume environmental dose rate, mainly used for recommending and deciding on the administration of iodine tablets). The other category is used when radioactive release has ended and the plume has completely passed through, and the patient is mainly exposed to radioactive sources from ground deposits, such as OIL3 (ground deposit environmental dose rate, used for recommending and deciding on mid-term evacuation), OIL4 (ground deposit environmental dose rate, used for recommending and deciding on temporary accommodation), and OIL5 to OIL9 (used for recommending and deciding on restricting food and water consumption, where: OIL5 is the ground deposit environmental dose rate; OIL6 is the I-131 activity concentration in ground deposits; OIL7 is the Cs-137 activity concentration in ground deposits; OIL8 is the I-131 activity concentration in food, water, or milk samples; and OIL9 is the Cs-137 activity concentration in food, water, or milk samples).

[0004] In the early stages of a nuclear accident, the primary concern is radiation exposure from the radioactive plume, and OIL1 and OIL2 are mainly used to provide recommendations for protective actions. OIL1 and OIL2 primarily use IAEA default values ​​or site-recommended values, or are calculated based on accident source terms and meteorological conditions. Currently, the meteorological conditions used in OIL1 and OIL2 calculations are mainly real-time observed meteorological data, typically a set of real-time observed meteorological elements at a single location (including wind speed, wind direction, atmospheric stability, and rainfall). However, this real-time observed meteorological data cannot reflect the spatiotemporal changes in meteorological conditions, and the simulation of radioactive plume diffusion and transport differs significantly from reality. This results in insufficient rationality and accuracy of the OIL1 and OIL2 calculation results, consequently leading to insufficient intervention effectiveness. Summary of the Invention

[0005] Therefore, it is necessary to address the above-mentioned shortcomings by providing a nuclear accident protection decision-making method, system, and computer-readable storage medium. This method, combined with local forecast meteorological field data, can refine the simulation of the diffusion and transport of radioactive plumes, improve the rationality and accuracy of OIL1 and OIL2 calculation results, and enhance the intervention effect.

[0006] A nuclear accident protection decision-making method includes the following steps: To obtain information on radioactive releases and local forecast meteorological field data; OIL1 and OIL2 are calculated based on the radioactive release information and local forecast meteorological field data. Protection decision recommendations are generated based on OIL1 and OIL2.

[0007] In one embodiment, the radioactive release information includes the unit where the accident occurred and its corresponding accident release source term data, or the sequence of units where the accident occurred and its corresponding accident release source term data sequence.

[0008] In one embodiment, obtaining the local forecast meteorological field data includes: A coordinate system is constructed within a preset range, centered on the unit where the accident occurred; when multiple units experience accidents, a coordinate system is constructed with the unit where the accident first as the reference unit and center. Obtain the corresponding local forecast meteorological field data based on the center and coordinate system.

[0009] In one embodiment, calculating OIL1 and OIL2 based on the radioactive release information and local forecast meteorological field data includes: Several discrete points within the coordinate system are selected as evaluation points. The concentration field and dose field of radioactive materials in the coordinate system are calculated using an atmospheric diffusion and transport model and a dose calculation model that support local meteorological field data. Based on the radioactive material concentration field and dose field, calculate OIL1 and OIL2 corresponding to each evaluation point.

[0010] In one embodiment, the concentration field is calculated according to the following formula: in, For the concentration field, For the two dimensions of the coordinate system, For a period of time, It is a nuclide. The concentration type includes air concentration and ground sediment concentration; This is an atmospheric diffusion transport model. Release source data for the accident. For local forecast meteorological field data, Auxiliary data for concentration field calculations; The dose field is calculated according to the following formula: in, For dose field, For the two dimensions of a planar coordinate system, For a period of time, It is a nuclide. The dose type includes external plume radiation dose, internal plume inhalation radiation dose, and external ground deposition radiation dose. For dose calculation mode, For the concentration field, Auxiliary data for dose field calculation.

[0011] In one embodiment, OIL1 is calculated according to the following formula: The OIL2 is calculated according to the following formula: in, To withdraw from the general intervention level, R1 is the ratio of total effective dose rate to environmental dose rate. For a general intervention level of stable iodine intake, R2 is the ratio of thyroid dose rate to environmental dose rate, and T... e This refers to the duration of smoke plume irradiation.

[0012] In one embodiment, R1 is calculated according to the following formula: R2 is calculated according to the following formula: The Calculate according to the following formula: in, The sum of the total effective doses of all radionuclides over all time periods at the preset evaluation points; The sum of the external plume radiation doses of all nuclides at all time periods at the preset evaluation points; The sum of the ground-deposited external radiation dose of all nuclides at the preset evaluation point over all time periods; The sum of thyroid doses of all radionuclides at all time periods at the preset evaluation points; The effective dose to the whole body = external radiation dose from the plume + internal radiation dose from inhaled plume + external radiation dose from ground deposition; The for The time, This is the threshold for the external radiation dose of the smoke plume.

[0013] In one embodiment, generating protection decision recommendations based on OIL1 and OIL2 includes: Obtain the environmental dose rate of the plume at each monitoring point, and generate the environmental dose rate of the plume at all evaluation points by interpolation based on the coordinate system. Compare the environmental dose rate of the smoke plume with OIL1 and OIL2 at each evaluation point; When the ambient dose rate of the plume is greater than OIL1, a first protective action recommendation is generated; when the ambient dose rate of the plume is greater than OIL2, a second protective action recommendation is generated; otherwise, no protection is required for the cell where the evaluation point is located.

[0014] This invention also discloses a nuclear accident protection decision-making system for implementing the above-mentioned nuclear accident protection decision-making method, comprising: The data acquisition unit is used to acquire information on radioactive releases and local forecast meteorological field data. The calculation unit is used to calculate OIL1 and OIL2 based on the radioactive release information and local forecast meteorological field data; An auxiliary decision-making unit is used to generate protection decision recommendations based on OIL1 and OIL2.

[0015] The present invention also discloses a computer-readable storage medium having a control program stored thereon, which, when executed by a processor, implements the above-described nuclear accident protection decision-making method.

[0016] The nuclear accident protection decision-making method, system, and computer-readable storage medium of this invention calculate OIL1 and OIL2 using radioactive release information and local forecast meteorological field data. This reflects the impact of spatiotemporal changes in meteorological conditions on the diffusion and transport of radioactive plumes, enabling more precise simulation and prediction of the diffusion and transport of radioactive plumes. This makes the simulation of radioactive plume diffusion and transport closer to the actual situation, thereby improving the rationality and accuracy of the OIL1 and OIL2 calculation results, providing scientific and effective support for emergency decision-making, and enhancing the intervention effect. Attached Figure Description

[0017] To more clearly illustrate the technical solution of the present invention, the present invention will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only show some embodiments of the present invention and should not be considered as a limitation of the scope. For those skilled in the art, other related drawings can be obtained from these drawings without creative effort. In the drawings: Figure 1 This is a flowchart of a nuclear accident protection decision-making method in one embodiment of the present invention; Figure 2 This is a schematic diagram of the structure of a nuclear accident protection decision system in one embodiment of the present invention. Detailed Implementation

[0018] To provide a clearer understanding of the technical features, objectives, and effects of this invention, specific embodiments are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the orientations or positional relationships indicated by terms such as "front," "rear," "upper," "lower," "left," "right," "longitudinal," "horizontal," "vertical," "horizontal," "top," "bottom," "inner," "outer," "head," and "tail" are based on the orientations or positional relationships shown in the accompanying drawings, and are constructed and operated in a specific orientation. They are only for the convenience of describing this technical solution and do not indicate that the device or element referred to must have a specific orientation; therefore, they should not be construed as limitations on this invention.

[0019] It should also be noted that, unless otherwise explicitly specified and limited, terms such as "installation," "connection," "linking," "fixing," and "setting" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components. When an component is referred to as being "on" or "below" another component, the component can be located "directly" or "indirectly" on the other component, or there may be one or more intermediary components. The terms "first," "second," "third," etc., are only for the convenience of describing this technical solution and should not be construed as indicating or implying relative importance or implicitly specifying the number of indicated technical features. Therefore, features defined with "first," "second," "third," etc., may explicitly or implicitly include one or more of that feature. For those skilled in the art, the specific meaning of the above terms in this invention can be understood according to the specific circumstances.

[0020] In the following description, specific details such as particular system architectures and techniques are set forth for illustrative purposes and not for limitation, in order to provide a thorough understanding of the embodiments of the invention. However, those skilled in the art will understand that the invention can be implemented in other embodiments without these specific details. In other instances, detailed descriptions of well-known systems, apparatuses, circuits, and methods are omitted so as not to obscure the description of the invention with unnecessary detail.

[0021] Example 1 Please see Figure 1 This invention discloses a nuclear accident protection decision-making method, which includes the following steps: S1. Obtain information on radioactive releases and local forecast meteorological field data.

[0022] In this embodiment, radioactive release information and local forecast meteorological field data are key parameters for calculating OIL1 and OIL2, directly determining the reliability and rationality of OIL1 and OIL2. Radioactive release information includes the unit where the accident occurred and its corresponding accident release source term data, or the sequence of units where the accident occurred and its corresponding accident release source term data sequence. The information of the unit or sequence of units where the accident occurred includes at least the ID information and location coordinate information of the unit or sequence of units where the accident occurred. Accident release source term data (or accident release source term data sequence) represents the actual or potential release of radioactive material from a given radioactive release source (or radioactive release source sequence). Accident release source term data (or accident release source term data sequence) includes the nuclide composition, quantity, release rate, and release mode of the released material. The nuclide composition may include... 85 Kr、 133Xe, 135 Xe, 131 I, 129 I, 134 Cs、 89 Sr、 132 Te、 140 Ba、 140 La、 103 Ru、 106 Ru、 95 Zr、 95 Nb, 144 Ce et al. Local forecast meteorological field data refers to the predicted data of meteorological elements at various discrete points within a certain area at different points in the future. Compared with real-time meteorological observation data, local forecast meteorological field data reflects the spatial and temporal changes of meteorological elements, is more refined and accurate, and can achieve the effect of predicting trends.

[0023] In step S1, obtaining local forecast meteorological field data includes: S11. Construct a coordinate system within a preset range, with the unit where the accident occurred as the center; when multiple units experience accidents, construct a coordinate system with the unit where the accident first occurred as the reference unit and center.

[0024] In this embodiment, a Cartesian coordinate system is constructed within a square area with sides of 10km or 20km, centered on the unit experiencing the accident. Discrete points uniformly distributed within this coordinate system (e.g., selecting a point with a step size of 500m) serve as evaluation points. These uniformly distributed discrete points divide the constructed Cartesian coordinate system into several computational grids. When multiple units experience accidents, a Cartesian coordinate system is constructed centered on the unit that first experienced the accident. The side length of the Cartesian coordinate system and the step size between adjacent discrete points are increased (i.e., the computational grid is increased) to comprehensively assess the radioactivity around the unit experiencing the accident, as well as the impact of multiple accident units overlapping at a distance from the baseline unit.

[0025] S12. Obtain the corresponding local forecast meteorological field data based on the center and coordinate system.

[0026] In other words, all local forecast meteorological field data within a coordinate system established at this center are acquired to comprehensively assess the diffusion of radioactivity at each point within the coordinate system as it follows changes in meteorological time and space. In this embodiment, the local forecast meteorological field data originates from global, national, or local meteorological forecasting organizations. For example, the local forecast meteorological field data may come from the GRAPES_MESO forecast data released by the China Meteorological Administration, which outputs a three-dimensional grid meteorological field and can provide hourly 72-hour forecast data to predict the propagation of radioactivity in future time periods.

[0027] S2. Calculate OIL1 and OIL2 based on radioactive release information and local forecast meteorological field data.

[0028] In step S2, calculating OIL1 and OIL2 based on radioactive release information and local forecast meteorological field data includes: S21. Select several discrete points within the coordinate system as evaluation points. As mentioned earlier, within the coordinate system established with the accident unit as the center, select a point at a predetermined distance from the center as an evaluation point. In this way, only a portion of the coordinate system needs to be tested to understand the changes in radioactivity within the coordinate system.

[0029] S22. Use atmospheric diffusion and transport models and dose calculation models that support local forecast meteorological field data to calculate the concentration field and dose field of radioactive materials in the coordinate system.

[0030] It should be noted that professional accident consequence assessment software in the industry generally includes atmospheric diffusion and transport models and dose calculation models, and the calculation of the dose field depends on the calculation results of the concentration field. The following describes the process of calculating the concentration field and dose field under the atmospheric diffusion and transport model and the dose calculation model.

[0031] In this embodiment, the concentration field refers to the time-dependent spatial grid distribution of the air concentration and ground deposition concentration of radionuclides; the dose field refers to the time-dependent spatial grid distribution of various doses caused by radionuclides, including whole-body effective dose, external plume irradiation dose, internal plume inhalation irradiation dose, external ground deposition irradiation dose, thyroid dose, etc.

[0032] The concentration field is calculated using the following formula: in, For the concentration field, For the two dimensions of the coordinate system, The location of the evaluation point in the coordinate system (i.e., its spatial location) was determined. For a period of time, Nuclide, that is, the types of nuclides. The concentration type includes air concentration and ground sediment concentration. This is an atmospheric diffusion transport model. Release source data for the accident. For local forecast meteorological field data, This is auxiliary data for concentration field calculation, which can be topographic parameters or other parameters.

[0033] In this embodiment, It is a function of the general atmospheric diffusion and transport model, and its corresponding concentration field formula differs under different models. For example, when establishing a three-dimensional coordinate system centered on the accident unit, under the unsteady Gaussian plume model (i.e., the Lagrange plume model), Calculated as follows: in, The concentration at point (x, y, z) of the i-th smoke plume is expressed in Bq / m³. 3 x, y, and z are the coordinates of the i-th smoke cloud along the wind direction, horizontal direction, and vertical direction, respectively. Let be the intensity of the i-th smoke plume, in Bq. , , These are the diffusion parameters along the wind direction, horizontal direction, and vertical direction, respectively, in meters (m). , , () represents the center position of the i-th smoke cloud, in meters.

[0034] The dose field is calculated according to the following formula: in, For dose field, For the two dimensions of a planar coordinate system, For a period of time, It is a nuclide. Dosage type, including external plume radiation dose, internal plume inhalation radiation dose, and external ground deposition radiation dose; For dose calculation mode, For the concentration field, Auxiliary data for dose field calculation, for example, the auxiliary data for dose field calculation can be a dose conversion factor.

[0035] When dc is the external plume radiation dose, the external plume radiation dose field for: in, Air radioactivity concentration (corresponding to) (c takes the air concentration type). The external radiation dose conversion factor (parameter) for nuclide n is the smoke cloud radiation dose conversion factor. Unit: Sv m³ / (Bq s)); The time step is set to a single time period, thus the cumulative external radiation dose of the plume is obtained by integrating the grid over time periods.

[0036] When dc is the internal radiation dose from plume inhalation, the internal radiation dose field from plume inhalation... for: Air radioactivity concentration (corresponding to) (c takes the air concentration type). The human respiratory rate (a fixed constant, included in auxiliary data p′) p′ is the radionuclide inhalation dose conversion factor (in units of Sv / Bq, representing the effective dose to be accumulated for every 1 Bq of radionuclide inhaled). The time step is set to a single time period, thus the cumulative internal radiation dose from the plume inhalation is obtained by integrating the grid over time periods.

[0037] When dc is the external radiation dose of ground deposition, the external radiation dose field of ground deposition... for: in, Air radioactivity concentration (corresponding to) c represents the air concentration type), and vd represents the dry deposition rate (i.e., auxiliary data p′). For a single time step, The external irradiation conversion factor of ground-deposited nuclides (i.e., auxiliary data p′, in units of Sv·m² / Bq).

[0038] When dc is the thyroid dose, the thyroid dose field for: Air radioactivity concentration (corresponding to) (c takes the air concentration type). The human respiratory rate (a fixed constant, included in auxiliary data p′) p′ is the thyroid dose conversion factor (Sv / Bq) for radionuclide n. The time step is a single time period, which is used to obtain the cumulative thyroid dose by integrating the grid over time periods.

[0039] S23. Based on the radioactive material concentration field and dose field, calculate OIL1 and OIL2 corresponding to each evaluation point.

[0040] In this embodiment, OIL1 is calculated according to the following formula: OIL2 is calculated according to the following formula: in, To determine the general intervention level for evacuation, the general intervention level for evacuation given in the national standard (GB18871) is selected as 50 mSv; R1 is the ratio of total effective dose rate to environmental dose rate, where environmental dose rate refers to external radiation dose rate (air immersion external radiation + ground deposition external radiation), which can be calculated by combining the results of concentration and dose calculations based on atmospheric diffusion and transport models. To determine the general intervention level for stable iodine intake, the general intervention level for stable iodine intake given in the national standard (GB18871) was selected as 100 mSv; R² is the ratio of thyroid dose rate to environmental dose rate, and T... e T represents the duration of plume irradiation, expressed in hours. For simplified calculations, T is used. e 4 hours can be taken directly; under precise calculation, the concentration calculation results combined with atmospheric diffusion and transport models, T e The cumulative time during which the air concentration at the evaluation point exceeds a certain threshold is taken.

[0041] Furthermore, R1 is calculated according to the following formula: R2 is calculated according to the following formula: in, The sum of the total effective doses of all radionuclides over all time periods at the preset evaluation points; The sum of the external plume radiation doses of all nuclides at all time periods at the preset evaluation points; The sum of the ground-deposited external radiation dose of all nuclides at the preset evaluation point over all time periods; The total thyroid dose is the sum of the doses of all radionuclides at all time periods at the preset evaluation site; the effective systemic dose = external plume radiation dose + internal plume inhalation radiation dose + external ground deposition radiation dose, in other words... It is the sum of the external radiation dose of all nuclides in the plume, the internal radiation dose of the plume inhalation, and the external radiation dose of the ground deposition at all time periods at the preset evaluation points.

[0042] Calculate according to the following formula: in, for The time of time, that is, Need to meet This is a threshold for the radiation dose outside the plume, which can be set as needed, for example, a threshold of 1.0E-3 mSv. It should be noted that in this embodiment, The cumulative duration of external plume irradiation dose exceeding the minimum dose limit in the dose calculation results (concentration field) of each evaluation point should be taken, which represents the actual duration of plume irradiation.

[0043] When the scenario involves multiple reactor accidents, R1 and R2 for each evaluation point consider the superposition of the dose fields caused by the accident releases from each reactor. For example, when evaluation point A is affected by both reactor M and reactor N, and both reactors M and N simultaneously produce radioactivity at evaluation point A, the R1 value at evaluation point A is the sum of the R1 values ​​of reactor M and reactor N at evaluation point A, thus comprehensively assessing the radioactive impact of multiple accident points on the same location.

[0044] S3. Generate protection decision recommendations based on OIL1 and OIL2.

[0045] In step S3, generating protection decision recommendations based on OIL1 and OIL2 includes: S31. Obtain the plume environmental dose rate at each monitoring point, and generate the plume environmental dose rate at all evaluation points based on coordinate system interpolation.

[0046] Because fixed radiation monitoring stations or mobile monitoring equipment deployed on-site are often not evenly distributed around the faulty unit at unit step lengths, the actual physical test points are only a few discrete locations. When the smoke cloud passes through a test point, the equipment measures the instantaneous gamma external radiation dose rate (unit: μSv / h) in real time, i.e., a single point, single time period. The instantaneous value is obtained, and by reading the measured data of all field radiation monitoring instruments, a set of true dose rate values ​​for discrete and sparse points are obtained.

[0047] Because the coordinate systems in the aforementioned concentration and dose fields are large, densely and uniformly distributed computational grids, most cells lack monitoring instruments and therefore have no measured data. In this case, using the planar coordinates (x, y) of the monitoring points and the measured dose rate as a benchmark, a spatial interpolation algorithm is employed to calculate the dose rate of any intermediate grid (i, j) using known discrete measurement point data. Finally, using data from a few measurement points, a fully covered, continuous two-dimensional grid dose field is constructed, yielding the plume dose rate for each evaluation grid and forming a continuous and complete regional dose distribution field.

[0048] For example, when using the inverse distance weighted interpolation method to calculate the environmental dose rate of the smoke plume at the evaluation point, the environmental dose rate of the smoke plume at the evaluation point... for: in, To represent the measured dose rate, there are a total of k measured monitoring points. For the evaluation points to be sought and the first The planar Euclidean distance between two monitoring points is given by p, where p is the power of the distance (p=2 is commonly used for radiation fields). The formula for the planar Euclidean distance between two points is: .

[0049] S32. Compare the environmental dose rate of the plume at each evaluation point with OIL1 and OIL2 to determine the radioactivity at each evaluation point. The environmental dose rate of the plume at each evaluation point is the measured value or the interpolated value at that evaluation point.

[0050] S33. When the ambient dose rate of the plume is greater than OIL1, generate the first protective action recommendation; when the ambient dose rate of the plume is greater than OIL2, generate the second protective action recommendation; otherwise, no protection is required for the cell where the evaluation point is located.

[0051] Specifically, when the ambient dose rate of the plume is greater than OIL1, the recommended protective action for the cell containing the evaluation point (a square centered on the evaluation point with the aforementioned step size as its side length) is evacuation; that is, the first recommended protective action is evacuation. When the ambient dose rate of the plume is greater than OIL2, the recommended protective action for the cell containing the evaluation point is concealment; that is, the second recommended protective action is concealment. Otherwise, no protective action is required for the cell containing the evaluation point. Based on this, a set of cells recommended for evacuation and a set of cells recommended for concealment are generated, thus forming evacuation and concealment areas.

[0052] Finally, a sequence of points of concern (such as residential areas, special population gathering points, etc.) within the evaluation scope is obtained, and spatial analysis is performed on each one. If a point of concern is located within an element of the evacuation cell set (i.e., within one of the evacuation cells), the recommended protective action is evacuation; if a point of concern is located within an element of the concealment cell set (i.e., within one of the concealment cells), the recommended protective action is concealment; otherwise, no action is recommended. Based on this, the final set of points of concern with recommended protective actions of evacuation and concealment is formed.

[0053] Example 2 Please combine Figure 1 and Figure 2This invention also discloses a nuclear accident protection decision-making system, which is used to implement the nuclear accident protection decision-making method of Embodiment 1. The nuclear accident protection decision-making system of this embodiment includes a data acquisition unit, a calculation unit, and an auxiliary decision-making unit. The data acquisition unit is used to acquire radioactive release information and local forecast meteorological field data. It can automatically collect local forecast meteorological field data, accident source term data, environmental monitoring data, etc. The local forecast meteorological field data comes from data sources / interfaces of global / national / local meteorological forecasting organizations, the accident source term data comes from other accident source term estimation software tools, and the environmental monitoring data comes from environmental monitoring software systems. The calculation unit is used to calculate OIL1 and OIL2 based on the radioactive release information and local forecast meteorological field data; that is, by automatically performing atmospheric diffusion transport and dose calculation, it calculates and outputs OIL1 and OIL2. The auxiliary decision-making unit is used to generate protection decision recommendations based on OIL1 and OIL2. In this embodiment, the auxiliary decision-making unit, based on the calculated output of OIL1 and OIL2, combined with environmental monitoring data and data of concern, provides a set of cells and areas for generating protection action recommendations of evacuation and concealment, and provides a set of concerns for which protection action recommendations of evacuation and concealment are given.

[0054] In this embodiment, the process by which the data acquisition unit acquires radioactive release information and local forecast meteorological field data is exactly the same as step S1 in Embodiment 1. The process by which the calculation unit calculates OIL1 and OIL2 based on the radioactive release information and local forecast meteorological field data is exactly the same as step S2 in Embodiment 1. The process by which the auxiliary decision-making unit generates protection decision recommendations based on OIL1 and OIL2 is exactly the same as step S3 in Embodiment 1. Specifically, the processes of: the type of radioactive release information; the establishment of the coordinate system; the acquisition of local forecast meteorological field data; the selection of evaluation points; the calculation of the concentration field and dose field of radioactive materials within the coordinate system using the atmospheric diffusion transport model and dose calculation model supporting the local forecast meteorological field data; the calculation of OIL1 and OIL2 corresponding to each evaluation point based on the radioactive material concentration field and dose field; the calculation of the plume environmental dose rate at the evaluation point based on the measured plume environmental dose rate; and the comparison of the plume environmental dose rate with the corresponding OIL1 and OIL2 to generate protection action recommendations are all the same as in Embodiment 1. For details, please refer to the relevant description in Embodiment 1, which will not be repeated here.

[0055] Example 3 The present invention also discloses a computer-readable storage medium storing a control program thereon. When the control program is executed by a processor, it implements the above-described nuclear accident protection decision-making method, that is, it is used to execute the steps of the nuclear accident protection decision-making method in Embodiment 1.

[0056] This embodiment provides a computer program product containing instructions that, when run on a computer, cause the computer to perform the steps in the method provided in the above-described method embodiment.

[0057] Understandable Figure 2 The block diagram of the nuclear accident protection decision system shown is only a partial block diagram of the structure related to this solution and does not constitute a limitation on the electronic equipment applied to it. The specific electronic equipment may include more or fewer components than shown in the figure, or combine certain components, or have different component arrangements.

[0058] In one embodiment, the computer program of this embodiment can run on any possible electronic device, and the memory of the electronic device can store the various program modules that make up the nuclear accident protection decision system described above. The computer program composed of the various program modules causes the processor to execute the steps in the method of Embodiment 1 described in this specification.

[0059] It should be noted that the descriptions of the storage medium and system embodiments above are similar to the descriptions of the method embodiments in Embodiment 1, and have similar beneficial effects. For technical details not disclosed in the storage medium, storage medium, and device embodiments of this embodiment, please refer to the description of the method embodiments in Embodiment 1 for understanding.

[0060] The nuclear accident protection decision-making method, system, and computer-readable storage medium of this invention calculate OIL1 and OIL2 using radioactive release information and local forecast meteorological field data. This reflects the impact of spatiotemporal changes in meteorological conditions on the diffusion and transport of radioactive plumes, enabling more precise simulation and prediction of the diffusion and transport of radioactive plumes. This makes the simulation of radioactive plume diffusion and transport closer to the actual situation, thereby improving the rationality and accuracy of the OIL1 and OIL2 calculation results, providing scientific and effective support for emergency decision-making, and enhancing the intervention effect.

[0061] It is understood that the above embodiments only illustrate preferred embodiments of the present invention, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the present invention. It should be noted that those skilled in the art can freely combine the above technical features without departing from the concept of the present invention, and can also make several modifications and improvements, all of which fall within the protection scope of the present invention. Therefore, all equivalent transformations and modifications made with respect to the scope of the claims of the present invention should fall within the scope of the claims of the present invention.

Claims

1. A nuclear accident protection decision-making method, characterized in that, Includes the following steps: To obtain information on radioactive releases and local forecast meteorological field data; OIL1 and OIL2 are calculated based on the radioactive release information and local forecast meteorological field data. Protection decision recommendations are generated based on OIL1 and OIL2.

2. The nuclear accident protection decision-making method according to claim 1, characterized in that, The radioactive release information includes the unit where the accident occurred and its corresponding accident release source data, or the sequence of units where the accident occurred and its corresponding accident release source data sequence.

3. The nuclear accident protection decision-making method according to claim 2, characterized in that, Obtaining the local forecast meteorological field data includes: A coordinate system is constructed within a preset range, centered on the unit where the accident occurred; when multiple units experience accidents, a coordinate system is constructed with the unit where the accident first as the reference unit and center. Obtain the corresponding local forecast meteorological field data based on the center and coordinate system.

4. The nuclear accident protection decision-making method according to claim 3, characterized in that, The calculation of OIL1 and OIL2 based on the radioactive release information and local forecast meteorological field data includes: Several discrete points within the coordinate system are selected as evaluation points. The concentration field and dose field of radioactive materials in the coordinate system are calculated using an atmospheric diffusion and transport model and a dose calculation model that support local meteorological field data. Based on the radioactive material concentration field and dose field, calculate OIL1 and OIL2 corresponding to each evaluation point.

5. The nuclear accident protection decision-making method according to claim 4, characterized in that, The concentration field is calculated according to the following formula: in, For the concentration field, For the two dimensions of the coordinate system, For a period of time, It is a nuclide. The concentration type includes air concentration and ground sediment concentration; This is an atmospheric diffusion transport model. Release source data for the accident. For local forecast meteorological field data, Auxiliary data for concentration field calculations; The dose field is calculated according to the following formula: in, For dose field, For the two dimensions of a planar coordinate system, For a period of time, It is a nuclide. The dose type includes external plume radiation dose, internal plume inhalation radiation dose, and external ground deposition radiation dose. For dose calculation mode, For the concentration field, Auxiliary data for dose field calculation.

6. The nuclear accident protection decision-making method according to claim 5, characterized in that, OIL1 is calculated according to the following formula: The OIL2 is calculated according to the following formula: in, To withdraw from the general intervention level, R1 is the ratio of total effective dose rate to environmental dose rate. For a general intervention level of stable iodine intake, R2 is the ratio of thyroid dose rate to environmental dose rate, and T... e This refers to the duration of smoke plume irradiation.

7. The nuclear accident protection decision-making method according to claim 6, characterized in that, R1 is calculated according to the following formula: R2 is calculated according to the following formula: The Calculate according to the following formula: in, The sum of the total effective doses of all radionuclides over all time periods at the preset evaluation points; The sum of the external plume radiation doses of all nuclides at all time periods at the preset evaluation points; The sum of the ground-deposited external radiation doses of all nuclides at all time periods at the preset evaluation points; The sum of thyroid doses of all radionuclides at all time periods at the preset evaluation points; The effective dose to the whole body = external radiation dose from the plume + internal radiation dose from inhaled plume + external radiation dose from ground deposition; The for The time, This is the threshold for the external radiation dose of the smoke plume.

8. The nuclear accident protection decision-making method according to claim 7, characterized in that, The generation of protection decision recommendations based on OIL1 and OIL2 includes: Obtain the environmental dose rate of the plume at each monitoring point, and generate the environmental dose rate of the plume at all evaluation points by interpolation based on the coordinate system. Compare the environmental dose rate of the smoke plume with OIL1 and OIL2 at each evaluation point; When the ambient dose rate of the plume is greater than OIL1, a first protective action recommendation is generated; when the ambient dose rate of the plume is greater than OIL2, a second protective action recommendation is generated; otherwise, no protection is required for the cell where the evaluation point is located.

9. A nuclear accident protection decision-making system, used to implement the nuclear accident protection decision-making method according to any one of claims 1-8, characterized in that, include: The data acquisition unit is used to acquire information on radioactive releases and local forecast meteorological field data. The calculation unit is used to calculate OIL1 and OIL2 based on the radioactive release information and local forecast meteorological field data; An auxiliary decision-making unit is used to generate protection decision recommendations based on OIL1 and OIL2.

10. A computer-readable storage medium, characterized in that, It stores a control program, which, when executed by a processor, implements the nuclear accident protection decision-making method according to any one of claims 1-8.

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