Route performance-based simulation analysis method and system for nuclear power plant

Abstract

This invention provides a method and system for performance-based simulation analysis of nuclear power plant routes. The method includes: S1, identifying various elements, constructing a complete nuclear power plant route topology network model, and determining key constraint nodes; S2, calculating the dose rate of each region in conjunction with reactor type source terms, and generating a spatially mapped radiation field data file; S3, defining dual-condition parameters, clarifying the characteristics of daily operation and overhaul operation; S4, conducting collaborative simulation calculations, simultaneously calculating the personnel flow process in the route network, the matching degree of passage capacity, the congestion evolution mechanism, and the duration and cumulative dose of personnel traversing radiation areas, and extracting the required performance indicators; S5, conducting a comprehensive evaluation based on the performance indicators and outputting a performance-based demonstration report. This invention breaks through traditional technical barriers, constructing a multi-physics collaborative model of radiation environment, passage performance, and personnel flow behavior, and achieving differentiated and accurate modeling of dual-condition operation during daily operation and intensive overhaul.

Description

Technical Field

[0001] This invention relates to the field of route planning for nuclear power plants, and in particular to a method and system for performance simulation analysis of routes in nuclear power plants. Background Technology

[0002] Currently, the field of construction engineering mainly relies on two types of technical means for personnel emergency evacuation demonstration and route planning. However, when faced with the special application scenario of nuclear power plants, both of these methods have exposed significant limitations and are difficult to meet the high standards of nuclear safety demonstration requirements.

[0003] First, traditional deterministic analysis methods rely on fixed parameters and empirical formulas for compliance checks. This leads to discrepancies between the calculated results and actual evacuation efficiency. Given the complex environmental characteristics and stringent nuclear safety requirements of nuclear power plants, this formula-based analysis lacks flexibility and cannot accurately reflect evacuation risks in specific scenarios, often resulting in analysis results that are either overly conservative or distorted.

[0004] Secondly, general-purpose building evacuation simulation software such as Pathfinder and FDS+Evac is used to construct fire scenarios and personnel behavior models. While these tools can construct fire scenarios and simulate personnel movement in smoke environments, they have a key limitation in nuclear power plant applications: Lack of radiation risk quantification: Existing software does not establish a coupling model between radiation dose field and personnel behavior. In nuclear accident scenarios, radiation exposure is a critical factor determining life and death, and general-purpose software cannot quantify this unique risk, resulting in a lack of radiation protection considerations in evacuation route planning.

[0005] Insufficient adaptability to operating conditions: There are significant differences between the "routine operation" and "overhaul" of a nuclear power plant in terms of personnel numbers, movement patterns, and dwell time. General-purpose software struggles to model these two extreme conditions differently and cannot accurately reflect the evacuation bottlenecks under high-density, complex movement patterns during overhauls.

[0006] Therefore, existing methods generally suffer from the problem of disconnect between environmental, structural, and human behavior modules. They are mostly passive judgments of compliance with normative provisions, lacking dynamic iteration and comprehensive performance optimization capabilities. This results in analysis results that are often conservative or distorted, making it difficult to provide sufficient and quantitative design safety demonstration basis for nuclear facilities.

[0007] In view of this, the inventors of this application have designed a route performance simulation analysis method and system for nuclear power plants in order to overcome the above-mentioned technical problems. Summary of the Invention

[0008] The technical problem to be solved by the present invention is to overcome the shortcomings of the existing technology in the field of construction engineering in terms of personnel emergency evacuation demonstration and route planning, which lacks dynamic iteration and comprehensive performance optimization capabilities, and to provide a route performance simulation analysis method and system for nuclear power plants.

[0009] The present invention solves the above-mentioned technical problems through the following technical solution: A method for route performance simulation analysis of a nuclear power plant, characterized in that the method includes the following steps: S1. Organize all elements, construct a complete nuclear power plant route topology network model, and identify key constraint nodes; S2. Combine the source terms of the stack type to calculate the dose rate of each region and generate a spatially mapped radiation field data file; S3. Define dual operating condition parameters to clarify the low-density, clear traffic flow characteristics of daily operation conditions, as well as the high-density, multi-route parallel, and high-congestion characteristics of overhaul conditions. S4. Conduct collaborative simulation calculations to simultaneously calculate the flow process of personnel in the route network, the matching degree of channel capacity, the congestion evolution mechanism, and the duration and cumulative dose of personnel crossing the radiation area, and extract the required performance indicators. S5. Based on the aforementioned performance indicators, conduct a comprehensive evaluation and output a performance-based demonstration report proving that the existing route design meets the requirements for nuclear safety, radiation protection, and operational efficiency.

[0010] According to an embodiment of the present invention, step S1 includes: S 11 Based on the overall design scheme of the nuclear power plant, clarify the boundary range of the model construction and define the spatial boundary of the core area; clarify the design constraints that the model construction needs to follow to ensure that the model is consistent with the actual design standards of the nuclear power plant; S 12 Based on the nuclear power plant design, establish the reference parameter system required for the three-dimensional model, and clarify the value standards and definition methods for various parameters; S 13 Construct a route topology network model for nuclear power plants.

[0011] According to an embodiment of the present invention, step S 12 Includes: S 121 Define the width, length, and clearance height of each passageway, the dimensions and specifications of doors and elevators, the number of staircases, width, and corner dimensions, as well as the traffic capacity parameters of the intersection nodes of each passageway; S 122Define the functional type of each channel, clarify the priority order of each channel, define the scope and restrictions on the channel occupation during equipment transportation, and determine the specific location and functional attributes of access control and access control nodes.

[0012] According to an embodiment of the present invention, step S 13 Includes: S 131 Based on the design drawings of the nuclear power plant, three-dimensional modeling technology is used to construct three-dimensional geometric models of the main plant, auxiliary plant and various passages and entrances, accurately restore the spatial dimensions, layout and relative positions, and ensure the geometric accuracy of the model; S 132 The three-dimensional geometric space is abstracted into a route topology network with a "node-edge" structure. Core nodes are defined, and their coordinates and attributes are specified. The edge structure of the corresponding channel segments is constructed to form a complete topology network. S 133 Clearly define the constraint nodes.

[0013] According to an embodiment of the present invention, step S 133 The constrained nodes include: radiation zone boundary nodes, traffic bottleneck nodes, emergency exit / safe assembly point nodes, and maintenance operation nodes.

[0014] According to an embodiment of the present invention, step S2 includes: S 21 Set the core parameters of the radiation source items for the nuclear power plant reactor type and clarify the key parameters of the radiation source; set the corresponding process constraints for the radiation source items in combination with the operation and maintenance process requirements of the nuclear power plant. S 22 Calculation and mapping of three-dimensional radiation dose field.

[0015] According to an embodiment of the present invention, step S 22 include: S 221 Set the three-dimensional radiation dose field calculation and related parameters; S 222 Output radiation measurement field cloud map; S 223 Perform spatial coordinate mapping.

[0016] According to an embodiment of the present invention, step S 221 include: S 2211 Define the spatial-energy distribution, transforming the activity of key radiation sources into a spatial distribution function and energy spectrum distribution; establish a dynamic operating condition parameter library covering full-power operation and reactor shutdown overhaul conditions, and control the start-up and shutdown of source terms and intensity changes through state variables; S 2212 Input the density, elemental composition, and cross-section library version of the shielding material, and combine the BIM model to set the shielding thickness, labyrinth structure, and equipment gaps to ensure that the geometric model is consistent with the actual process. S 2213 Particle transport calculations were performed using the Monte Carlo procedure. S 2214 Generate a voxelized dose field and output three-dimensional meshed dose distribution data to ensure that the origin, units, and axes of the radiation field model are consistent with those of the three-dimensional building model.

[0017] According to an embodiment of the present invention, step S 222 This includes: outputting the radiation dose rate calculation results as a three-dimensional radiation dose field cloud map, so that each voxel or grid node in the nuclear power plant space corresponds to a unique radiation dose rate value.

[0018] According to an embodiment of the present invention, step S 223 This includes: accurately aligning the spatial coordinates of the three-dimensional radiation dose field cloud map with the three-dimensional geometric model of the nuclear power plant, and establishing a one-to-one correspondence between "building space and radiation dose".

[0019] According to an embodiment of the present invention, step S4 includes: S 41 Select a co-simulation engine suitable for nuclear facility scenarios, configure the time step, import and verify standardized data from preceding modules, and set simulation boundary conditions; establish a "personnel flow-passage-radiation dose" co-simulation model, initialize and calibrate relevant parameters based on dual-condition parameters; S 42 Generate a personnel model and assign routes based on dual-condition parameters, calculate personnel flow behavior, calculate channel capacity matching degree and classify it; S 43 Simulate the entire congestion evolution process based on thresholds and record key parameters; correlate personnel coordinates with radiation dose fields, and use formulas... Calculate cumulative dose and issue early warnings; S 44 1. Set rules for indicator extraction, extract core indicators, and quantify and organize them; S 45 After extraction, the indicators are verified and abnormal data is removed. Standardized exportable reports are generated according to dual working conditions. S 46 Establish synergistic relationships among various indicators to form a linkage between indicators of "personnel-traffic-radiation"; S 47 Repeat the simulation multiple times under the same working condition to ensure that the coefficient of variation of key indicators is ≤5%, and control the simulation error to ≤10% by comparing with historical data.

[0020] This invention also provides a route performance simulation analysis system for nuclear power plants, characterized in that the system employs the route performance simulation analysis method for nuclear power plants as described above, and the system includes: The operating condition and basic data input module is used to comprehensively import the three-dimensional layout of nuclear power plant buildings, route topology network, channel geometry and traffic capacity thresholds, radiation source item distribution and zoning information, and to finely define the number of personnel, personnel distribution, work flow and process constraint boundaries during daily operation and major overhaul. The radiation environment field simulation module is used to establish a high-precision three-dimensional radiation dose field model based on the reactor design, and to calculate and output dose rate distribution data of each route node under normal operation and accident conditions as a function of spatial location and time. Dual-condition personnel behavior modeling module, used for differentiated modeling; The route performance coupling simulation module is used to synchronously iteratively calculate radiation field data, channel structure capacity and personnel flow model, and solve the travel time, congestion point identification, dynamic distribution of personnel density, cumulative radiation dose accumulation and route bottleneck analysis in real time during the personnel flow process. The performance verification and output module is used to automatically compare the key indicators output by the simulation with safety criteria, radiation protection limits and traffic efficiency requirements, and generate quantitative evaluation conclusions and analysis reports.

[0021] The present invention also provides an electronic device, characterized in that the electronic device includes: a processor and a memory, the memory storing a program or instructions executable on the processor, the program or instructions being executed by the processor to implement the route performance simulation analysis method for nuclear power plants as described above.

[0022] The present invention also provides a readable storage medium, characterized in that a program or instructions are stored on the readable storage medium, and when the program or instructions are executed by a processor, the route performance simulation analysis method for nuclear power plants described above is implemented.

[0023] The positive and progressive effects of this invention are as follows: The present invention provides a method and system for route performance simulation analysis of nuclear power plants, aiming to break through traditional technical barriers and construct a multi-physics collaborative model of radiation environment, channel performance and personnel flow behavior, so as to achieve differentiated and accurate modeling of dual working conditions of daily operation and intensive overhaul.

[0024] The route performance simulation analysis method for nuclear power plants is no longer limited to static standard verification, but can dynamically simulate and quantify the exposure dose and passage efficiency of personnel in complex radiation fields, thereby comprehensively demonstrating the performance of route design in terms of safety, rationality and optimization.

[0025] The proposed route performance simulation analysis method for nuclear power plants fills a gap in the industry and can effectively meet the high-standard demonstration requirements for personnel evacuation and radiation protection in complex scenarios during the safety review of exported nuclear power units. Attached Figure Description

[0026] The above and other features, properties and advantages of the present invention will become more apparent from the following description taken in conjunction with the accompanying drawings and embodiments, in which the same reference numerals always denote the same features, wherein: Figure 1 This is a flowchart of the route performance simulation analysis method for nuclear power plants according to the present invention. Detailed Implementation

[0027] The present invention will be further described below with reference to specific embodiments and accompanying drawings. More details are set forth in the following description in order to provide a full understanding of the present invention. However, the present invention can obviously be implemented in many other ways different from those described herein. Those skilled in the art can make similar extensions and derivations based on actual application situations without departing from the spirit of the present invention. Therefore, the scope of protection of the present invention should not be limited by the content of this specific embodiment.

[0028] Embodiments of the invention will now be described in detail with reference to the accompanying drawings. It should be noted that these and subsequent drawings are merely illustrative and should not be construed as limiting the scope of the invention. Wherever possible, the same reference numerals will be used in all drawings to denote the same or similar parts.

[0029] Furthermore, although the terminology used in this invention is selected from commonly known and used terms, some terms mentioned in this specification may have been selected by the applicant in his or her judgment, and their detailed meanings are explained in the relevant sections of the description herein.

[0030] Furthermore, the invention should be understood not only through the actual terminology used, but also through the meaning implied by each term.

[0031] like Figure 1 As shown, this invention discloses a route performance simulation analysis method for nuclear power plants, comprising the following steps: Step S1: Organize all elements, construct a complete nuclear power plant route topology network model, and identify key constraint nodes. For example, organize elements such as plant buildings, passageways, lobbies, staircases, and emergency exits.

[0032] Preferably, step S1 includes: Step S 11 1. Defining Design Boundaries and Constraints: Based on the overall design scheme of the nuclear power plant, clarify the boundary range of the model construction and define the spatial boundaries of the core areas. For example, define the spatial boundaries of core areas such as the main plant building, auxiliary plant buildings, emergency passages, stairwells, and entrances / exits.

[0033] At the same time, the design constraints that need to be followed in model construction are clearly defined, including process equipment layout specifications, equipment maintenance path planning requirements, radiation zone boundary range, emergency evacuation direction criteria and fire zone boundary regulations, to ensure that the model is consistent with the actual design standards of nuclear power plants.

[0034] Step S 12 Establishment of a benchmark parameter system: Based on the nuclear power plant design, establish the benchmark parameter system required for the three-dimensional model, and clarify the value standards and definition methods for various parameters.

[0035] Specifically, step S 12 Preferably, it includes: Step S 121 Define the width, length, and clearance height of each passageway, the dimensions and specifications of doors and elevators, the number of staircases, width, and corner dimensions, as well as the traffic capacity parameters of the intersection nodes of each passageway, to ensure that the parameters are consistent with the actual engineering design parameters of the nuclear power plant and to guarantee the geometric accuracy of the model.

[0036] Step S 122 Define the functional type of each passage, including daily passage, maintenance passage, and emergency evacuation passage.

[0037] Clearly define the access priority of each channel, define the scope and restrictions on channel occupancy during equipment transportation, and determine the specific location and functional attributes of access control and permission control nodes. This will provide functional support for subsequent topology network construction and personnel behavior simulation.

[0038] Step S 13 Construct a route topology network model for nuclear power plants.

[0039] Step S 13 Includes: Step S 131 Geometric model construction: Based on the design drawings of the nuclear power plant (such as CAD / BIM design drawings), three-dimensional modeling technology is used to construct three-dimensional geometric models of the main plant, auxiliary plant and various passages and entrances, accurately restore the spatial dimensions, layout and relative positions, and ensure the geometric accuracy of the model.

[0040] Step S 1321. Topology Network Construction: Abstract the three-dimensional geometric space into a route topology network with a "node-edge" structure, define core nodes (e.g., defining core nodes such as channel intersections and radial zone boundaries), and clarify the coordinates and attributes of the core nodes. Construct the edge structure of the corresponding channel segments, assigning them core attributes such as length and passage capacity, to form a complete topology network.

[0041] Step S 133 1. Define key constraint nodes: Clearly define the constraint nodes.

[0042] Preferably, step S 133 The constraint nodes include: radiation zone boundary nodes (controlling dose area crossing), traffic bottleneck nodes (restricting traffic flow), emergency exit / safe assembly point nodes (supporting evacuation simulation), and maintenance operation nodes (precisely locating high-dose exposure areas), providing constraint support for subsequent simulations.

[0043] Step S2: Calculate the dose rate of each region by combining the reactor type source term, and generate a spatially mapped radiation field data file.

[0044] Preferably, step S2 includes: Step S 21 1. Radiation source term parameter setting: Set the core parameters of the radiation source terms of the nuclear power plant reactor type, and clarify the key parameters of the radiation sources, such as the key parameters of the main radiation sources such as the reactor core, primary loop equipment, spent fuel pool, and radioactive waste system, including the activity, energy distribution and geometric location of each radiation source, to ensure that the source term parameters match the actual design and operating conditions of the nuclear power plant, and to provide accurate input for radiation dose rate calculation.

[0045] Process constraint setting: Based on the operation and maintenance process requirements of nuclear power plants, process constraints corresponding to radiation source items are set. Preferably, the process constraints include: state parameters of radiation source items under different operating conditions, defining the variation law of radiation source items caused by various operations under overhaul conditions. The material type and thickness parameters of various shielding bodies are clearly defined, including specific parameters of shielding bodies such as concrete, lead, and water, providing constraint support for accurate calculation of radiation dose rate.

[0046] Step S 22 Calculation and mapping of three-dimensional radiation dose field.

[0047] Preferably, step S 22 include: Step S 221 Set the three-dimensional radiation dose field calculation and related parameters.

[0048] Preferably, step S 221 include: Step S 2211Refined modeling of source term data: Define spatial-energy distribution, transforming the activity of key radiation sources into spatial distribution functions (e.g., volume sources, surface sources) and energy spectrum distributions (e.g., fission spectrum, decay gamma spectrum). Establish a dynamic operating condition parameter library covering full-power operation and reactor shutdown overhaul conditions, controlling source term start-up, shutdown, and intensity changes through state variables.

[0049] Step S 2212 Integration of process constraints and shielding parameters: Input the density, elemental composition and section library version of the shielding material (such as concrete, lead, etc.), and combine it with the BIM model to set the shielding thickness, maze structure and equipment gaps to ensure that the geometric model is consistent with the actual process.

[0050] Step S 2213 Three-dimensional radiation dose field calculation: Particle transport calculations were performed using the Monte Carlo program.

[0051] Step S 2214 Spatial coordinate mapping and output: Generates a voxelized dose field and outputs three-dimensional meshed dose distribution data (supports VTK / HDF5 format), ensuring that the origin, units and axes of the radiation field model are consistent with those of the three-dimensional building model (BIM), thereby providing an accurate dose input interface for subsequent personnel path planning.

[0052] Step S 222 Output radiation measurement field cloud map.

[0053] Preferably, step S 222 This includes: outputting the radiation dose rate calculation results as a three-dimensional radiation dose field cloud map, so that each voxel or grid node in the nuclear power plant space corresponds to a unique radiation dose rate value, thereby realizing the visualization of the radiation dose field.

[0054] Step S 223 Perform spatial coordinate mapping.

[0055] Preferably, step S 223 This includes: accurately aligning the spatial coordinates of the three-dimensional radiation dose field cloud map with the three-dimensional geometric model of the nuclear power plant, establishing a one-to-one correspondence between "building space and radiation dose", and providing accurate dose input for the cumulative calculation of radiation dose along the subsequent personnel traversing the path.

[0056] Step S3: Define dual operating condition parameters, clarify the low-density and clear traffic flow characteristics of daily operation conditions, and the high-density, multi-route parallel and high-congestion characteristics of overhaul conditions. The specific parameter configurations are shown in Table 1 and Table 2 below.

[0057] Table 1 shows the parameter configuration for operating condition A: daily operation condition.

[0058] Table 2 shows the parameter configuration for Condition B: Overhaul Condition.

[0059] The formula for calculating personnel density (corresponding to the quantification of personnel characteristics) is: ρ = N / S; ρ represents personnel density (persons / m²); N represents the number of people working simultaneously in the area; S represents the effective passage / operation building area.

[0060] The source term fluctuation coefficient (corresponding to dose characteristic quantization) is: K represents the fluctuation coefficient of the radiation source term; D max / D avg This indicates the maximum regional dose rate and the average background dose rate.

[0061] Channel utilization (corresponding to the quantification of passage parameters) is:

[0062] Here, the input layer function is to uniformly convert the 3D building topology model, 3D radiation dose field cloud map, and dual-condition personnel / access / dose parameters into input data that the simulation engine can recognize, so as to realize the coordinated mapping of the three major elements of building, radiation, and personnel.

[0063] Step S4: Conduct collaborative simulation calculations to simultaneously calculate the flow of people in the route network, the matching degree of channel capacity, the congestion evolution mechanism, and the duration and cumulative dose of people crossing the radiation area, and extract the required performance indicators. For example, extract key performance indicators such as maximum travel time, congestion duration, peak population density, individual and group radiation dose, and route utilization rate.

[0064] Step S4 includes: Step S 41 1. Preliminary preparation and core process calculation: Select a collaborative simulation engine that is compatible with the nuclear facility scenario, configure the time step (e.g., configure a 1-second time step, 24 hours for daily operation simulation and 72 hours for overhaul operation simulation), import and verify the standardized data of the preceding modules, and set the simulation boundary conditions.

[0065] Establish a collaborative model of "personnel flow - passageway access - radiation dose", initialize relevant parameters based on dual-condition parameters and calibrate them (simulation deviation ≤10%).

[0066] Step S 42 The four core processes of synchronous calculation are: generating personnel models and allocating routes based on dual-condition parameters, calculating personnel flow behavior, calculating channel capacity matching degree and classifying and judging.

[0067] Step S 43The entire process of congestion evolution is simulated based on thresholds, and key parameters are recorded. Personnel coordinates are correlated with the radiation dose field, and the result is obtained through formulas. Calculate cumulative dose and issue early warnings.

[0068] Step S 44 Key performance indicator extraction and output: Define indicator extraction rules (e.g., extract real-time indicators every 30 seconds, summarize and statistically analyze at the end of the simulation, perform unified statistics across the entire area and time period, specify indicator units and classify by dual operating conditions, and remove outlier data), extract core indicators, and quantify them. For example, indicator extraction is categorized into four main types: traffic, personnel, radiation dose, and routes. Specifically, extract and quantify core indicators such as maximum traffic time, peak personnel density, cumulative individual / group dose, and route utilization rate.

[0069] Step S 45 After extraction, the indicators are verified and abnormal data is removed. Standardized exportable reports are generated according to dual working conditions, providing direct data support for subsequent path optimization and radiation risk management.

[0070] Step S 46 Establish synergistic relationships among various indicators. For example, personnel density affects the passage capacity and congestion evolution, congestion duration affects the radiation exposure duration of personnel and thus relates to cumulative radiation dose, and route utilization is linked to passage efficiency and dose exposure, forming a "personnel-passage-radiation" indicator linkage relationship to support subsequent multi-dimensional optimization analysis.

[0071] Step S 47 Simulation quality control: Repeat simulations under the same operating conditions multiple times to ensure that the coefficient of variation of key indicators is ≤5%, and control the simulation error to ≤10% by comparing with historical data. Preferably, an anomaly early warning mechanism can also be set to ensure the continuity of simulation.

[0072] Step S5: Based on the performance indicators, a comprehensive evaluation is conducted, and a performance-based demonstration report is output to prove that the existing route design meets the requirements of nuclear safety, radiation protection, and operational efficiency, providing scientific, intuitive, and quantifiable technical support for the safety review of nuclear facilities.

[0073] This invention also provides a route performance simulation analysis system for nuclear power plants, employing the route performance simulation analysis method for nuclear power plants as described above. The route performance simulation analysis system for nuclear power plants includes: The operating condition and basic data input module is used to comprehensively import the three-dimensional layout of nuclear power plant buildings, route topology network, channel geometry and traffic capacity thresholds, radiation source item distribution and zoning information, and to finely define the number of personnel, personnel distribution, work flow and process constraint boundaries during daily operation and major overhaul.

[0074] The radiation environment field simulation module is used to establish a high-precision three-dimensional radiation dose field model based on the reactor design. It can calculate and output dose rate distribution data of each route node under normal operation and accident conditions as a function of spatial location and time.

[0075] The dual-condition personnel behavior modeling module is used for differentiated modeling. The core of this module lies in differentiated modeling: for daily operation conditions, it sets behavioral parameters for a small number of fixed personnel, fixed routes, low dwell time, and low congestion probability. For major overhaul conditions, it simulates the complex behavioral characteristics of a large number of workers distributed at multiple points, moving in opposite directions, with high dwell time and high congestion probability, and customizes key parameters such as personnel movement speed, flow density, path selection preferences, and work dwell time.

[0076] The route performance coupling simulation module, as the system's computing engine, is used to synchronously iteratively calculate radiation field data, channel structure capacity, and personnel flow model, and to solve in real time the travel time, congestion point identification, dynamic distribution of personnel density, cumulative radiation dose accumulation, and route bottleneck analysis during the personnel flow process.

[0077] The performance verification and output module is used to automatically compare the key indicators output by the simulation with safety criteria, radiation protection limits and traffic efficiency requirements, and generate quantitative evaluation conclusions and analysis reports to directly support design compliance verification.

[0078] The present invention also provides an electronic device, comprising: a processor and a memory, wherein the memory stores a program or instructions executable on the processor, the program or instructions being executed by the processor to implement the route performance simulation analysis method for nuclear power plants as described above.

[0079] The present invention also provides a readable storage medium on which a program or instruction is stored, which, when executed by a processor, implements the route performance simulation analysis method for nuclear power plants as described above.

[0080] Based on the above description, the route performance simulation analysis method and system for nuclear power plants of this invention aims to overcome the limitations of traditional nuclear power plant personnel evacuation analysis, which separates radiation environment from personnel behavior and lacks sufficient differentiation of operating conditions. By constructing a multi-physics field collaborative model of "radiation dose field - channel structure performance - personnel behavior characteristics", it realizes dynamic simulation and quantitative evaluation of route traffic efficiency, radiation exposure risk and congestion risk under two typical operating conditions of nuclear power plant daily operation and major overhaul, thereby providing a solid performance demonstration basis for the correctness, safety and optimization of route design.

[0081] In summary, the route performance simulation analysis method and system for nuclear power plants of the present invention have the following advantages: I. The proposed route performance simulation analysis method for nuclear power plants is highly targeted and adaptable to the unique radiation scenarios of nuclear power plants. It is the first method to deeply integrate radiation dose fields with route travel and personnel behavior, enabling quantitative assessment of radiation exposure risks and meeting nuclear safety and radiation protection requirements.

[0082] Second, the route performance simulation analysis method for nuclear power plants strictly distinguishes between two operating conditions, and the simulation is more realistic. Personnel models for daily operation and overhaul conditions are established separately, which solves the distortion problem caused by the "one-size-fits-all" approach of traditional methods, and the results are more reliable.

[0083] Third, the performance simulation analysis method for nuclear power plant routes enables performance demonstration, supporting the design verification of nuclear facilities. It not only meets the requirements of the specifications, but also "proves the design itself to be reasonable and safe" through dynamic simulation, and can be directly used for external technical demonstration and review support.

[0084] Fourth, the route performance simulation analysis method for nuclear power plants can achieve multi-module collaboration and comprehensively evaluate the three major elements of environment, passage, and personnel. It can identify route bottlenecks, congestion risks, and high-dose exposure points, providing a scientific and technical basis for optimizing radiation protection design and iterating route schemes for nuclear power plants.

[0085] Fifth, the route performance simulation analysis method for nuclear power plants is standardized, highly reusable, with a clear process and well-defined inputs and outputs. It can be applied to route design verification for different nuclear facilities and has engineering promotion value.

[0086] For those skilled in the art, the above disclosure is merely illustrative and does not constitute a limitation of this application. Although not explicitly stated herein, those skilled in the art may make various modifications, improvements, and corrections to this application. Such modifications, improvements, and corrections are suggested in this application and therefore remain within the spirit and scope of the exemplary embodiments of this application.

[0087] It should be noted that the use of terms such as "first" and "second" to define components is merely for the purpose of distinguishing the corresponding components. Unless otherwise stated, the above terms have no special meaning and therefore should not be construed as limiting the scope of protection of this application.

[0088] Furthermore, this application uses specific terms to describe embodiments of the application. For example, "an embodiment," "one embodiment," and / or "some embodiments" refer to a particular feature, structure, or characteristic related to at least one embodiment of the application. Therefore, it should be emphasized and noted that "an embodiment," "one embodiment," or "an alternative embodiment" mentioned twice or more in different locations in this specification do not necessarily refer to the same embodiment. In addition, certain features, structures, or characteristics in one or more embodiments of the application can be appropriately combined.

[0089] Similarly, it should be noted that, in order to simplify the description of the embodiments disclosed in this application and thus aid in the understanding of one or more embodiments of the invention, the foregoing description of the embodiments of this application sometimes combines multiple features into one embodiment, drawing, or description thereof. However, this disclosure method does not mean that the subject matter of this application requires more features than those mentioned in the claims. In fact, the embodiments have fewer features than all the features of the single embodiments disclosed above. Some embodiments use numbers describing the quantity of components and attributes. It should be understood that such numbers used in the description of embodiments are modified in some examples by the terms "approximately," "approximately," or "generally." Unless otherwise stated, "approximately," "approximately," or "generally" indicates that the numbers are allowed to vary by ±20%.

[0090] Accordingly, in some embodiments, the numerical parameters used in the specification and claims are approximate values, which may be changed depending on the characteristics required by individual embodiments. In some embodiments, the numerical parameters should take into account specified significant digits and employ a general method of digit preservation. Although the numerical ranges and parameters used to confirm their breadth of application in some embodiments of this application are approximate values, in specific embodiments, such values ​​are set as precisely as feasible.

[0091] While specific embodiments of the present invention have been described above, those skilled in the art should understand that these are merely illustrative examples, and the scope of protection of the present invention is defined by the appended claims. Those skilled in the art can make various changes or modifications to these embodiments without departing from the principles and essence of the present invention, but all such changes and modifications fall within the scope of protection of the present invention.

Claims

1. A method for performance-based simulation analysis of a nuclear power plant's power line, characterized in that, The route performance simulation analysis method for nuclear power plants includes the following steps: S1. Organize all elements, construct a complete nuclear power plant route topology network model, and identify key constraint nodes; S2. Combine the source terms of the stack type to calculate the dose rate of each region and generate a spatially mapped radiation field data file; S3. Define dual operating condition parameters to clarify the low-density, clear traffic flow characteristics of daily operation conditions, as well as the high-density, multi-route parallel, and high-congestion characteristics of overhaul conditions. S4. Conduct collaborative simulation calculations to simultaneously calculate the flow process of personnel in the route network, the matching degree of channel capacity, the congestion evolution mechanism, and the duration and cumulative dose of personnel crossing the radiation area, and extract the required performance indicators. S5. Based on the aforementioned performance indicators, conduct a comprehensive evaluation and output a performance-based demonstration report proving that the existing route design meets the requirements for nuclear safety, radiation protection, and operational efficiency.

2. The method for route performance simulation analysis of nuclear power plants as described in claim 1, characterized in that, Step S1 includes: S 11 Based on the overall design scheme of the nuclear power plant, clarify the boundary range of the model construction and define the spatial boundary of the core area; clarify the design constraints that the model construction needs to follow to ensure that the model is consistent with the actual design standards of the nuclear power plant; S 12 Based on the nuclear power plant design, establish the reference parameter system required for the three-dimensional model, and clarify the value standards and definition methods for various parameters; S 13 Construct a route topology network model for nuclear power plants.

3. The method for route performance simulation analysis of nuclear power plants as described in claim 2, characterized in that, The step S 12 Includes: S 121 Define the width, length, and clearance height of each passageway, the dimensions and specifications of doors and elevators, the number of staircases, width, and corner dimensions, as well as the traffic capacity parameters of the intersection nodes of each passageway; S 122 Define the functional type of each channel, clarify the priority order of each channel, define the scope and restrictions on the channel occupation during equipment transportation, and determine the specific location and functional attributes of access control and access control nodes.

4. The method for route performance simulation analysis of nuclear power plants as described in claim 2, characterized in that, The step S 13 Includes: S 131 Based on the design drawings of the nuclear power plant, three-dimensional modeling technology is used to construct three-dimensional geometric models of the main plant, auxiliary plant and various passages and entrances, accurately restore the spatial dimensions, layout and relative positions, and ensure the geometric accuracy of the model; S 132 Abstracting the three-dimensional geometric space into a route topology network with a "node-edge" structure, defining the core nodes, and clarifying the coordinates and attributes of the core nodes; constructing the edge structure of the corresponding channel segments to form a complete topology network; S 133 Clearly define the constraint nodes.

5. The route performance simulation analysis method for nuclear power plants as described in claim 4, characterized in that, The step S 133 The constrained nodes include: radiation zone boundary nodes, traffic bottleneck nodes, emergency exit / safe assembly point nodes, and maintenance operation nodes.

6. The method for route performance simulation analysis of nuclear power plants as described in claim 2, characterized in that, Step S2 includes: S 21 Set the core parameters of the radiation source items for the nuclear power plant reactor type and clarify the key parameters of the radiation source; set the corresponding process constraints for the radiation source items in combination with the operation and maintenance process requirements of the nuclear power plant. S 22 Calculation and mapping of three-dimensional radiation dose field.

7. The method for route performance simulation analysis of nuclear power plants as described in claim 6, characterized in that, The step S 22 include: S 221 Set the three-dimensional radiation dose field calculation and related parameters; S 222 Output radiation measurement field cloud map; S 223 Perform spatial coordinate mapping.

8. The method for route performance simulation analysis of nuclear power plants as described in claim 7, characterized in that, The step S 221 include: S 2211 Define the spatial-energy distribution, transforming the activity of key radiation sources into a spatial distribution function and energy spectrum distribution; establish a dynamic operating condition parameter library covering full-power operation and reactor shutdown overhaul conditions, and control the start-up and shutdown of source terms and intensity changes through state variables; S 2212 Input the density, elemental composition, and cross-section library version of the shielding material, and combine the BIM model to set the shielding thickness, labyrinth structure, and equipment gaps to ensure that the geometric model is consistent with the actual process. S 2213 Particle transport calculations were performed using the Monte Carlo procedure. S 2214 Generate a voxelized dose field and output three-dimensional meshed dose distribution data to ensure that the origin, units, and axes of the radiation field model are consistent with those of the three-dimensional building model.

9. The method for route performance simulation analysis of nuclear power plants as described in claim 7, characterized in that, The step S 222 This includes: outputting the radiation dose rate calculation results as a three-dimensional radiation dose field cloud map, so that each voxel or grid node in the nuclear power plant space corresponds to a unique radiation dose rate value.

10. The method for route performance simulation analysis of nuclear power plants as described in claim 7, characterized in that, The step S 223 This includes: accurately aligning the spatial coordinates of the three-dimensional radiation dose field cloud map with the three-dimensional geometric model of the nuclear power plant, and establishing a one-to-one correspondence between "building space and radiation dose".

11. The method for route performance simulation analysis of nuclear power plants as described in claim 1, characterized in that, Step S4 includes: S 41 Select a co-simulation engine suitable for nuclear facility scenarios, configure the time step, import and verify standardized data from preceding modules, and set simulation boundary conditions; establish a "personnel flow-passage-radiation dose" co-simulation model, initialize and calibrate relevant parameters based on dual-condition parameters; S 42 Generate a personnel model and assign routes based on dual-condition parameters, calculate personnel flow behavior, calculate channel capacity matching degree and classify it; S 43 Simulate the entire congestion evolution process based on thresholds and record key parameters; correlate personnel coordinates with radiation dose fields, and use formulas... Calculate cumulative dose and issue early warnings; S 44 1. Set rules for indicator extraction, extract core indicators, and quantify and organize them; S 45 After extraction, the indicators are verified and abnormal data is removed. Standardized exportable reports are generated according to dual working conditions. S 46 Establish synergistic relationships among various indicators to form a linkage between indicators of "personnel-traffic-radiation"; S 47 Repeat the simulation multiple times under the same working condition to ensure that the coefficient of variation of key indicators is ≤5%, and control the simulation error to ≤10% by comparing with historical data.

12. A route performance simulation analysis system for a nuclear power plant, characterized in that, The route performance simulation analysis system for the nuclear power plant adopts the route performance simulation analysis method for nuclear power plants as described in any one of claims 1-11, and the route performance simulation analysis system for the nuclear power plant includes: The operating condition and basic data input module is used to comprehensively import the three-dimensional layout of nuclear power plant buildings, route topology network, channel geometry and traffic capacity thresholds, radiation source item distribution and zoning information, and to finely define the number of personnel, personnel distribution, work flow and process constraint boundaries during daily operation and major overhaul. The radiation environment field simulation module is used to establish a high-precision three-dimensional radiation dose field model based on the reactor design, and to calculate and output dose rate distribution data of each route node under normal operation and accident conditions as a function of spatial location and time. Dual-condition personnel behavior modeling module, used for differentiated modeling; The route performance coupling simulation module is used to synchronously iteratively calculate radiation field data, channel structure capacity and personnel flow model, and solve the travel time, congestion point identification, dynamic distribution of personnel density, cumulative radiation dose accumulation and route bottleneck analysis in real time during the personnel flow process. The performance verification and output module is used to automatically compare the key indicators output by the simulation with safety criteria, radiation protection limits and traffic efficiency requirements, and generate quantitative evaluation conclusions and analysis reports.

13. An electronic device, characterized in that, The electronic device includes a processor and a memory, the memory storing programs or instructions that can run on the processor, the programs or instructions being executed by the processor to implement the route performance simulation analysis method for nuclear power plants as described in any one of claims 1-11.

14. A readable storage medium, characterized in that, The readable storage medium stores a program or instructions, which, when executed by a processor, implement the route performance simulation analysis method for nuclear power plants as described in any one of claims 1-11.

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