A highly sensitive, synergistic nuclear reactor safety analysis digital system and method

Abstract

The application belongs to the technical field of nuclear engineering and digital modeling, and provides a kind of precise and sensitive collaborative nuclear reactor safety analysis digital system and method, which can enhance the quality and timeliness of system modeling, improve the integrated analysis accuracy, break through the bottleneck of cross-computing collaboration efficiency, solve the problem of implicit computing process, and improve the functional integration and whole-process digital level.The system includes a front-end graphical modeling module, a cross-platform professional computing program engine module, a visual computing process construction module, a graphical post-processing module, and a system overall scheduling and management module.The method realizes precise and sensitive collaborative nuclear reactor safety analysis through the system.The application can enhance the quality and timeliness of system modeling, improve the integrated analysis accuracy, break through the bottleneck of cross-computing collaboration efficiency, and improve the functional integration and whole-process digital level.

Description

Technical Field

[0001] This application belongs to the field of nuclear engineering and digital modeling technology, and in particular relates to a precise and sensitive collaborative digital system and method for nuclear reactor safety analysis. Background Technology

[0002] Pressurized water reactors are complex mega-systems, and their safety analysis involves complex phenomena at multiple scales, including reactor fission heat generation, core flow heat transfer, primary and secondary side flow heat transfer, and containment flow heat transfer. Conducting safety analysis requires core subchannel analysis programs, system analysis programs, and containment analysis programs. In traditional system analysis, these software programs independently perform calculations within their respective ranges and transmit calculations via interfaces, resulting in low analytical accuracy and computational efficiency.

[0003] With technological advancements, platform-based analytics have been gradually applied and promoted across various industries. In the nuclear reactor field, some leading nuclear powers have already implemented platform-based analytics models, such as the Moose platform or Snap. However, as... Figure 1 As shown, the safety analysis of traditional pressurized water nuclear reactors mainly has the following shortcomings or problems to be solved: 1. The single-discipline program modeling process suffers from significant efficiency bottlenecks: The existing system modeling relies on manual card-filling, requiring manual data extraction from paper interfaces, followed by manual cleaning, conversion, and card filling, involving tens of thousands of parameter operations. This process is highly dependent on manual labor, inefficient, and prone to errors, with a single modeling cycle lasting more than three months. There is an urgent need to improve standardization and processing efficiency through automation.

[0004] 2. Significant bottlenecks in the efficiency of software collaboration within the discipline: Existing technologies rely on technicians to manually handle program interfaces between disciplines, lacking standardized data interfaces. This results in manual conversion required for data exchange between cross-disciplinary modules such as thermal hydraulics, containment, and neutron dynamics, leading to low efficiency in collaborative analysis.

[0005] 3. Insufficient functional integration and lack of digital technology support: Existing technologies focus on single software calculations and have not achieved full-process integration of automatic task scheduling and multi-dimensional result processing; they lack real-time visualization monitoring and fault tolerance mechanisms, and manual restart is required once a calculation interruption occurs, affecting the timeliness of analysis. Summary of the Invention

[0006] The purpose of this application is to overcome the shortcomings of the prior art and provide a precise and collaborative digital system and method for nuclear reactor safety analysis, which can enhance the quality and timeliness of system model building, improve the accuracy of integrated analysis, break through the bottleneck of cross-computational collaboration efficiency, solve the problem of implicit computing processes, and improve the functional integration and the level of full-process digitalization.

[0007] To achieve the above objectives, this application provides the following technical solution: In a first aspect, this application provides a precise and sensitive collaborative digital system for nuclear reactor safety analysis, comprising: The front-end graphical modeling module is used to perform graphical and standardized modeling of system analysis programs based on the thermal safety analysis requirements of nuclear pressurized water reactors. A cross-platform professional computing engine module is used to integrate core thermal-hydraulic analysis programs, system transient analysis programs, and containment response analysis programs, and to achieve transparent program invocation and resource scheduling in different system environments; The visualization computing process construction module is used to connect the various computing steps in a graphical way, making the computing process explicit and adjustable. The graphical post-processing module is used for multi-dimensional visualization analysis and result comparison of calculation results; The overall system scheduling and management module is used to implement computing resource scheduling, resource management, and hierarchical access control. Among them, the front-end graphical modeling module, the cross-platform professional computing program engine module, the visual computing process construction module, and the graphical post-processing module collaborate through a standardized data interface using a unified data format description language.

[0008] As an feasible approach, the front-end graphical modeling module includes: The component configuration unit is used to represent pipes, valves, thermal structures, pumps, regulators, control systems, point pile neutron dynamics, variables, and table components in a graphical building block manner, and maps upstream structural, physical, control, and system parameters to component configuration parameters to achieve rule-driven dynamic modeling. The modeling method integration unit is used to standardize the user's modeling process and integrates core modeling methods, drop-down annular cavity modeling methods, pressurizer modeling methods, and steam generator modeling methods.

[0009] As an implementable approach, the cross-platform professional computing engine module includes: The nuclear safety analysis program unit integrates the independently developed CORTH core subchannel system analysis program, ARSAC advanced reactor system analysis program, and CONAC or CONTHAP containment response analysis program. When the ARSAC system analysis function unit is connected to the CORTH core thermal-hydraulic analysis function unit, the data stream transmits the core outlet pressure, inlet temperature, and inlet flow rate. When the ARSAC system analysis function unit is connected to the CONAC or CONTHAP containment response function unit, the data stream transmits the breach flow rate and enthalpy value, and automatically performs data density processing as needed. When the ARSAC system analysis function unit is connected to another ARSAC system analysis function unit, the data stream transmits the restart file generated by the previous system analysis function unit and the last restart number in the event sequence file. A cross-platform runtime environment support unit is used to integrate the program through a unified architecture and to enable transparent calls to each analysis module through standardized interfaces; The computing resource management unit is used to support users in configuring computing resources and to switch between parallel computing and serial execution scheduling modes for nuclear safety analysis professional program units and supporting functional units. The computing monitoring unit is used to monitor the CPU utilization, memory usage and data transmission status of each computing module in real time. When a computing interruption or abnormality is detected, it automatically records the breakpoint data and triggers an early warning.

[0010] As an implementable approach, the visualization computing workflow building module includes: The graphical process orchestration engine unit is used to implement interactive computational logic design using draggable process blocks and visual data flow connection lines, automatically records the process creation and modification history, and provides modular extension interfaces to encapsulate professional analysis programs. The multi-dimensional result comparison unit is used to provide multi-dimensional and interactive visualization of the analysis results under different calculation schemes and parameters. The calculation process template management unit is used to save, load and modify calculation process templates according to different accident types. The process templates store the purpose of accident analysis, interface requirements and data processing procedures based on the MBSE concept. The status tracking and viewing unit is used to display the running progress, completion status and key node time of each computing stage in real time through a graphical interface; The interface standardization unit is used to support the rapid integration of new nuclear safety analysis professional computing programs using standardized encapsulation protocols.

[0011] As an implementable approach, the graphical process orchestration engine unit in the visual computing process building module supports the following data flow transfer logic: When the system analysis function unit is connected to the core thermal-hydraulic analysis function unit, the data stream connection transmits the core outlet pressure, inlet temperature and inlet flow rate. When the system analysis function unit is connected to the containment response function unit, the data flow connection transmits the breach flow rate and enthalpy value, and automatically performs density processing on the data according to the requirements. When system analysis function units are connected, the data flow connection transmits the restart file and the last restart number in the event sequence file generated by the previous system analysis function unit.

[0012] As one feasible approach, the graphical post-processing module includes: The data output unit supports exporting data in various standardized data formats, and automatically retains metadata such as calculation parameters, analysis conditions, and result accuracy. The data comparison unit is used for interactive and visual comparison of different calculation schemes and parameter variables, enabling synchronous display of multi-dimensional results and dynamic correlation analysis.

[0013] As an feasible approach, the overall system scheduling and management module includes: The permission hierarchical management unit is used to divide user permissions into three levels: administrator, analyst, and viewer. Administrators have full-process operation and permission allocation permissions, analysts have modeling, process construction and calculation execution permissions, and viewers only have the permissions to view results and trace processes. The distributed computing management unit is used to intelligently allocate computing nodes, memory, and computing power resources based on the priority, computational complexity, and real-time load of multi-user concurrent tasks.

[0014] As an implementable approach, the system also includes an auxiliary module for implementing system-level security management and computing resource optimization. The auxiliary module specifically includes: The overall system scheduling and management unit is used to adopt a hierarchical permission management mechanism, which divides user permissions into three levels: administrator, analyst, and viewer. Administrators have full-process operation and permission allocation permissions, analysts have modeling, process construction and calculation execution permissions, and viewers only have result viewing and process traceability permissions to ensure operational compliance. The distributed computing management unit is used to intelligently allocate computing nodes, memory, and computing power resources based on the priority, computational complexity, and real-time load of multi-user concurrent tasks, thereby enabling high-priority tasks to be scheduled first and improving overall operating efficiency.

[0015] Secondly, this application provides a precision-sensitive collaborative nuclear reactor safety analysis method, based on the system described above, the method comprising the following steps: Step 1: Front-end graphical processing and parametric modeling. The front-end graphical modeling module is used to build the model required for thermal safety analysis of pressurized water reactors. Step 2: Visualize the computing process construction, defining the computing logic and data flow through the visual computing process construction module; Step 3: Automated scheduling and parallel computing of the cross-platform professional computing engine module, calling integrated professional programs for collaborative computing; Step 4: Graphical post-processing and multi-dimensional result comparison, visualizing and analyzing the calculation results.

[0016] As an implementable approach, step 1 specifically includes: Users select the items and accident categories to be analyzed, and the system automatically loads the corresponding basic structure templates. Users input the core structure, system parameters and boundary conditions in layers on the basic structure template, and import interface data from upstream professionals; The system's built-in data consistency verification mechanism performs integrity and logical consistency checks on the parameters entered by the user, and prompts the user to correct any missing or conflicting data.

[0017] As an implementable approach, step 2 specifically includes: Users can customize the calculation process by dragging and dropping process blocks and connecting lines, and insert program function units for core thermal-hydraulic analysis, system transient analysis, and containment response analysis as needed. The system automatically records the process of building the system, enabling version management; Users save the completed process as a computation process template for later reuse.

[0018] As an implementable approach, step 3 specifically includes: The system automatically calls the corresponding computing units according to the process scheduling instructions and performs collaborative computing according to the execution order set by the user; Users can select the parallel computing or serial execution mode of the nuclear safety analysis program unit and its supporting functional units based on their computing power. The system ensures seamless data sharing and efficient data transmission among functional units through standardized data interfaces; During the calculation process, the visualization calculation process construction module monitors the running status of each module in real time and automatically triggers prompts when an anomaly is detected.

[0019] As an implementable approach, step 4 specifically includes: After the calculation task is completed, the system will synchronize the results to the graphical post-processing module, and the user can confirm the types of data synchronized. Users can use multi-dimensional interactive visualization analysis tools to compare analysis results under different calculation schemes and parameters, and view the core analysis results through charts, animations or 3D models; The system generates a calculation report based on the template selected by the user, and generates corresponding interface forms based on the downstream interface requirements.

[0020] As an implementable approach, its applicable scope covers the operational transients and accident analysis related to pressurized water reactors, mainly including: power operation, power increase / decrease, load step changes, load shedding, feedwater temperature drop caused by feedwater system failure, feedwater flow increase caused by feedwater system failure, excessive increase in secondary steam flow, main steam system accident depressurization, steam system pipeline rupture, external load loss and / or turbine accident shutdown, loss of non-emergency AC power supply to power plant auxiliary facilities, loss of normal feedwater flow, feedwater system pipeline rupture, partial or complete loss of reactor coolant forced flow, reactor coolant pump shaft jamming, uncontrolled extraction of rod bundle control assembly during subcritical or low-power startup, uncontrolled extraction of a set of RCCAs during power operation, extraction of a single control rod assembly during full-power operation, malfunction of the emergency boron injection system during power operation, steam generator heat transfer tube rupture, coolant loss accidents, and containment response caused by primary / secondary loop breaches.

[0021] Compared with existing technologies, the precision-sensitive collaborative digital system and method for nuclear reactor safety analysis provided in this application have the following advantages: This application can enhance the quality and timeliness of system model building, realize the standardization and automation of the establishment of pressurized water reactor thermal safety analysis model from external professional interfaces, and realize the dynamic updating of the model with input parameters.

[0022] This application can improve the accuracy of integrated analysis, construct a full-chain analysis model of core thermal-hydraulic system-containment, optimize key models, and achieve high-precision integrated analysis.

[0023] This application can overcome the bottleneck of cross-computational collaboration efficiency. By adopting a modular architecture and standardized data interface design, it reduces the uncertainty caused by parameter transfer between programs such as thermal hydraulics, containment, and neutron dynamics, and realizes automatic data interaction between modules without manual conversion, thereby improving the efficiency of cross-disciplinary collaborative analysis.

[0024] This application can solve the problem of implicit computational processes, realize the explicit construction and visual configuration of computational processes, make the analysis process reusable and flexibly modifiable, improve fault tracing capabilities, and avoid secondary development costs in complex accident scenarios.

[0025] This application can improve the integration of functions and the level of digitalization of the entire process, integrate parametric modeling, automatic task scheduling and multi-dimensional result comparison functions to achieve integrated support for the entire nuclear safety analysis process; and add real-time visualization monitoring and intelligent fault-tolerant processing mechanisms to avoid manual restart after computation interruption and ensure the timeliness of analysis.

[0026] This application achieves multi-dimensional breakthroughs in "precision improvement, efficiency optimization, enhanced adaptability, simplified operation, and safety assurance," enabling integrated, intelligent, and high-precision end-to-end nuclear reactor safety analysis. Compared with existing technologies, taking loss-of-coolant accident analysis as an example, the overall analysis efficiency is improved by more than 60%, the accuracy of core parameter calculations is improved by 15% to 20%, the operational complexity is reduced by 70%, and the technology adaptability range is expanded by more than three times. Simultaneously, it significantly reduces the cost of manual intervention and the risk of safety assessment. It not only provides nuclear power plants with a more efficient and accurate safety analysis tool but also supports scenarios such as nuclear reactor design optimization and accident contingency plan development, possessing significant engineering application value and economic and social benefits. It can be widely applied to the safety analysis of various pressurized water reactor types. Attached Figure Description

[0027] To more clearly illustrate the technical solution of this application, the accompanying drawings used in the technical description will be briefly introduced below.

[0028] Figure 1 A schematic diagram illustrating the shortcomings of traditional thermal safety analysis techniques; Figure 2 A schematic diagram of the precision-sensitive collaborative digital system for nuclear reactor safety analysis provided in this application; Figure 3 A schematic diagram of the functional composition of the precision-sensitive collaborative digital system for nuclear reactor safety analysis provided in this application; Figure 4 A flowchart of the precision-sensitive collaborative nuclear reactor safety analysis method provided in this application; Figure 5 A diagram illustrating the specific implementation steps of the precision-sensitive collaborative nuclear reactor safety analysis method provided in this application. Detailed Implementation

[0029] The following detailed description provides further details on specific implementation methods.

[0030] like Figure 2 and Figure 3 As shown, this application provides a precise and collaborative digital system for nuclear reactor safety analysis, including a front-end graphical modeling module, a cross-platform professional computing engine module, a visual computing workflow construction module, and a graphical post-processing module, supplemented by an overall system scheduling and management module integrating auxiliary functions such as computing resource scheduling, resource management, and hierarchical access control. Details are as follows: The front-end graphical modeling module is used to efficiently, graphically, and in a standardized manner to complete the most complex system analysis procedures in the process of thermal safety analysis of nuclear pressurized water reactors, based on the requirements of thermal safety analysis. The cross-platform professional computing engine module is used to integrate sub-channel level core thermal-hydraulic, system transient and containment response analysis programs, and to realize transparent calling and resource scheduling of the above programs in different systems / environments, so as to achieve high-fidelity safety analysis capabilities; The visual computing process construction module is used to connect the various computing steps in a graphical way, making the computing process explicit, transparent and efficient to adjust. It adopts a visual interface of process blocks and data flow, supports users to customize the computing process through drag and drop, connection and other operations, modularly plug and unplug different computing steps, and realize process version management and automatic process recording. The graphical post-processing module is used for multi-dimensional visualization analysis of calculation results, result comparison and real-time monitoring, and supports intelligent fault-tolerant processing and cross-platform data interaction; The modules mentioned above collaborate through a standardized data interface using a unified JSON-like data format description language, enabling seamless integration of upstream professional interface data with downstream interface data generation, thereby improving the accuracy and efficiency of thermal safety analysis for pressurized water reactors.

[0031] Specifically, the front-end graphical modeling module includes: The system analysis program's component configuration unit helps users quickly complete modeling in a graphical, building-block manner. This unit is presented graphically in the interface. Component configurations mainly include pipes, valves, thermal structures, pumps, pressurizers, control systems, point reactor neutron dynamics, variables, and tables. Based on this, through hard-coding, the nuclear reactor modeling method maps upstream structural, physical, control, and system parameters to the component configuration parameters, thus enabling rule-driven dynamic modeling capabilities.

[0032] The modeling methodology integration unit is used to standardize the user's modeling process. Nuclear reactor modeling methods mainly include core modeling methods, descending annular cavity modeling methods, pressurizer modeling methods, and steam generator modeling methods. This method includes the control volume length / number of nodes for each component, model selection, and the type of component used for modeling.

[0033] The front-end graphical modeling module is used for multi-level parametric modeling, supporting hierarchical and modular modeling based on the thermal safety analysis of nuclear reactor pressurized water reactors. The parameter system is directly linked to upstream professional interfaces.

[0034] The front-end graphical modeling module is used for rule-driven dynamic modeling. It supports the establishment of complete analysis models according to security analysis requirements and automatically verifies the completeness and accuracy of input information to avoid data errors.

[0035] The front-end graphical modeling module is used for visual interactive modeling. It uses a graphical interface to realize intuitive modeling of complex systems and integrates a dedicated component library for pressurized water reactor thermal safety analysis, which supports the improvement of modeling efficiency.

[0036] Specifically, the cross-platform professional computing engine module includes: The nuclear safety analysis program unit is used to calculate the behavioral characteristics of the reactor. The core thermal-hydraulic analysis program mainly includes the independently developed core sub-channel system analysis program CORTH, advanced reactor system analysis program ARSAC, and containment response analysis program CONAC or CONTHAP. All of these programs possess the functions required for pressurized water reactor safety analysis, including high-precision models for pressurized water reactor transient and accident analysis, and have been experimentally verified to ensure calculation accuracy.

[0037] The cross-platform operating environment support unit is used to support the scheduling and task allocation of computing resources for the core thermal-hydraulic analysis program (LINUX), the system transient analysis program (Windows), and the containment response analysis program (UNIX). This unit integrates the three high-precision calculation modules of the core thermal-hydraulic analysis program, the system transient analysis program, and the containment response analysis program through a unified architecture, and realizes transparent calling of each analysis module through standardized interfaces, while maintaining the original high-precision calculation characteristics of each professional program.

[0038] The computing resource management unit allows users to configure computing resources. Users can use this unit to switch between parallel computing and serial execution scheduling modes for the nuclear safety analysis program unit and its supporting functional units. Based on the time requirements, computational complexity, and hardware resource availability of the analysis task, users can customize the execution order and coordination logic of each computing module.

[0039] The computing monitoring unit has intelligent fault tolerance and breakpoint resume capability. It can monitor the CPU utilization, memory usage and data transmission status of each computing module in real time. When a computing interruption or abnormality is detected, it automatically records the breakpoint data, marks the abnormal node and triggers an alert, allowing users to resume the computing process from any interrupted functional unit.

[0040] The cross-platform professional computing engine module is used for high-fidelity safety analysis. It integrates sub-channel-level core thermal-hydraulic, system transient, and containment response analysis programs. Based on rigorously verified models and algorithms, it ensures high-precision and high-resolution simulation and evaluation capabilities for critical safety scenarios.

[0041] The cross-platform professional computing engine module is used for seamless integration in heterogeneous environments, providing a unified client entry point, natively adapting to operating systems such as Linux / Windows and different hardware architectures, and enabling transparent invocation and resource scheduling of professional analysis programs such as reactor core, system, and containment.

[0042] Specifically, the visualization computing process construction module includes: The graphical workflow orchestration engine unit supports users in building computational workflows graphically. It employs draggable workflow blocks and visual data flow connections to achieve interactive computational logic design, making the analysis process explicit. It integrates a full lifecycle version control mechanism, automatically recording workflow creation and modification history, supporting arbitrary version rollback and reproduction, ensuring computational traceability. It provides modular extension interfaces to support the encapsulation of specialized analysis programs such as core thermal analysis and containment response. Through a pluggable architecture, it enables rapid workflow reconstruction for accident scenarios. During this process, the data flow connections between specialized programs exhibit the following characteristics: 1) When the system analysis function unit (Advanced Reactor System Analysis Program ARSAC) is connected to the core thermal-hydraulic analysis function unit (Core Subchannel System Analysis Program CORTH), the data stream connection transmits the core inlet pressure, temperature and flow rate calculated by the system analysis function unit; 2) When the system analysis function unit is connected to the containment response function unit, the data flow connection transmits the breach flow rate and enthalpy value calculated by the system analysis function unit, and automatically performs data density processing according to requirements. 3) When system analysis functional units are connected, the data flow connection transmits the restart file (restart.th) generated by the previous system analysis functional unit and the last restart number in the event sequence file (trip.th).

[0043] The multi-dimensional results comparison unit can provide multi-dimensional, interactive visualization of analysis results under different calculation schemes and parameters, enabling full-process traceability and visual management of nuclear safety analysis results. The specific functions of the multi-dimensional results comparison unit are as follows: 1) Supports extracting the timestamps of important events from the result files of system analyzers and containment analyzers, and outputting them in the form of a list to the prepared report; 2) Supports extracting data from the result files of core thermal-hydraulic, system analysis, and containment response analysis programs based on user-specified reusable templates, and generating graphs; 3) Supports matching by name and automatically pasting the generated curves into the specified report template.

[0044] The calculation workflow template management unit supports users in saving, loading, and modifying calculation templates. Based on different incident types, the unit generates calculation workflows covering the entire process from parameter modeling, calculation, and result processing, which can be saved in the workflow template library. Changes to workflows in this library require approval within the system. Workflows in this library can be loaded and reused; by modifying parameter configurations, such as upstream interface library sources and necessary calculation file paths, automated analysis of the same type of incident can be achieved. Furthermore, this workflow template adopts the MBSE (Mystery, Execution, and Evaluation) concept, storing the purpose of the incident analysis, interface requirements, data processing procedures, and principles within the template. Users can access relevant professional knowledge at any time through help documentation, systematically mastering the forward analysis capabilities for this incident.

[0045] The status tracking and viewing unit allows users to view the current location of the calculation and the completion status (success or failure) of completed functional units in real time through a graphical workflow. It can display the running progress, completion status (success / failure), and time consumption of key nodes of each calculation stage in the form of progress bars, node status indicators, and dynamic data flow animations, allowing users to keep abreast of the dynamics of the analysis process and trace abnormal nodes. In addition, the status tracking and viewing unit allows users to start the process from any selected functional unit for failed or terminated processes.

[0046] The standardized interface unit adopts a standardized encapsulation protocol, which supports the rapid integration of new nuclear safety analysis professional computing programs. It does not require modification of the core system architecture. It can realize process reconstruction and analysis support for new accident scenarios by simply configuring program interface parameters and data interaction formats.

[0047] The visual computing workflow construction module features a graphical workflow orchestration engine, employing a visual design of workflow blocks and data flows. It supports interactive workflow construction through drag-and-drop connections, enabling explicit display of computing logic and transparent management of processes.

[0048] The visual computing workflow building module is used for full lifecycle version control. It integrates automatic tracking and recording functions for workflow creation and modification, supports version rollback and historical workflow reproduction, and ensures computing traceability.

[0049] The visualization computing process building module has a modular and scalable architecture, supports the encapsulation and plugging of professional computing programs such as core thermal analysis and containment analysis, and adapts to the need for rapid process reconstruction in complex accident scenarios.

[0050] Specifically, the graphical post-processing module includes: The data output unit supports exporting data in various standardized formats, including CSV, Excel, WORD, PNG, and text formats. Exported data automatically retains key metadata such as calculation parameters, analysis conditions, and result accuracy, adapting to the format requirements of downstream report preparation, data archiving, and multi-professional review processes.

[0051] The data comparison unit supports interactive and visual comparisons of different calculation schemes and parameter variables, enabling simultaneous display of multi-dimensional results and dynamic correlation analysis.

[0052] The graphical post-processing module is used for multi-dimensional dynamic comparative analysis, supporting interactive visualization comparison of calculation schemes and parameter variables, and realizing synchronous display of multi-dimensional results and dynamic correlation analysis.

[0053] The graphical post-processing module is used for scenario-based template data output, providing a standardized result export interface to adapt to customized output needs in different application scenarios such as report generation and data reuse.

[0054] Preferably, the system also includes a system overall scheduling and management module for unified scheduling in heterogeneous environments, compatible with multiple operating systems and hardware platforms, realizing cross-module coupling integration and dynamic allocation of distributed resources, and supporting concurrent access and task scheduling by multiple users.

[0055] The system's overall scheduling and management module has a full-link security control mechanism. It ensures operational compliance through encrypted data interfaces and hierarchical permission management, and achieves full-process responsibility traceability and data security protection by combining operation log tracking.

[0056] The system's overall scheduling and management module has a standardized collaborative computing framework, integrates heterogeneous computing resources based on a unified client, and intelligently schedules modules according to security analysis requirements to ensure traceability of the computing process and optimal resource utilization.

[0057] Preferably, the system also includes an auxiliary module for implementing system-level security management and computing resource optimization.

[0058] The auxiliary modules specifically include: The overall system scheduling and management unit adopts a hierarchical permission management mechanism, dividing user permissions into three levels: administrator, analyst, and viewer. Administrators have full-process operation and permission allocation permissions, analysts have modeling, process construction and calculation execution permissions, and viewers only have result viewing and process traceability permissions, ensuring operational compliance.

[0059] The distributed computing management unit can intelligently allocate computing nodes, memory, and computing power resources based on the priority, computational complexity, and real-time load of hardware resources for concurrent tasks from multiple users, thereby enabling priority scheduling of high-priority tasks and improving overall operating efficiency.

[0060] The system adopts a modular architecture, integrating a front-end graphical modeling module, a cross-platform professional computing engine module, a visual computing process construction module, and a graphical post-processing module. It is supplemented by an overall system scheduling and management module that integrates auxiliary functions such as computing resource scheduling, resource management, and hierarchical access control, so as to achieve the accuracy, collaboration, and visualization of the entire process of thermal safety analysis of nuclear pressurized water reactors.

[0061] In addition, such as Figure 4 and Figure 5 As shown, this application also provides a precise and sensitive collaborative nuclear reactor safety analysis method, which can be applied to the analysis of transient operation and accidents of pressurized water reactors. The main aspects include: power operation, power increase / decrease, load step change, load shedding, feedwater temperature drop caused by feedwater system failure, feedwater flow increase caused by feedwater system failure, excessive increase in secondary steam flow, main steam system accident depressurization, steam system pipeline rupture, external load loss and / or turbine accident shutdown, loss of non-emergency AC power supply to power plant auxiliary facilities, loss of normal feedwater flow, feedwater system pipeline rupture, partial or complete loss of reactor coolant forced flow, reactor coolant pump shaft jamming, uncontrolled extraction of rod bundle control assembly during subcritical or low-power startup, uncontrolled extraction of a group of RCCAs during power operation, extraction of a single control rod assembly during full-power operation, malfunction of the emergency boron injection system during power operation, steam generator heat transfer tube rupture, coolant loss accidents, and containment responses caused by primary / secondary loop breaches.

[0062] This method includes the following steps: Step 1: Front-end graphical processing and parametric modeling; Step 2: Visualize the computation process construction; Step 3: Automated scheduling and parallel computing of cross-platform professional computing engine modules; Step 4: Graphical post-processing and comparison of multi-dimensional results.

[0063] Specifically, step 1 includes: Step 1.1: Users enter the system's main interface through the front-end graphical modeling module and select the items and accident categories to be analyzed on the main interface; Step 1.2: The system automatically loads the basic structure templates corresponding to the selected project and accident category; Step 1.3: Based on actual analysis requirements, users input the core structure, system parameters, and boundary conditions in layers on the loaded basic structure template; users define key sub-modules layer by layer through multi-level parametric modeling, including but not limited to: core components, coolant loop, safety injection system, and containment and its heat dissipation system; Step 1.4: Users import interface data from upstream disciplines (such as equipment, control, fuel, etc.) into the front-end module; during the modeling process, the system regularizes the data processing methods from upstream parameters to the program input model according to the modeling method and program input requirements, and implements them in this module; users can compile and modify the regulations according to their needs; Step 1.5: The system's built-in data consistency verification mechanism performs integrity checks and logical consistency checks on every parameter input by the user. When the user defines the core coolant loop parameters, the system automatically verifies the connection relationships of each node, the dimensional matching of physical quantities, and the rationality of boundary conditions. Once input is missing or logical conflicts are detected, the system promptly prompts the user to make corrections through the graphical interface, ensuring the accuracy and data quality of the modeling stage.

[0064] Specifically, step 2 includes: Step 2.1: After the modeling is completed and the data consistency verification is passed, the user enters the visual computing process construction module (this module provides a visual interface based on process blocks and data flow). Step 2.2: Users can customize the calculation process required for nuclear safety analysis by dragging and dropping process blocks and connecting lines. This includes inserting program function units as needed (such as core thermal-hydraulic analysis, system transient analysis, containment response analysis, etc.) as well as auxiliary processing units when transferring data between programs, and adjusting the order of process blocks and the direction of data flow. Step 2.3: The process construction interface displays process nodes with clear graphic icons and shows the parameter transfer relationship between nodes through visual connections (these connections carry the data transfer function and clearly reflect the parameter transfer information of each calculation module). Step 2.4: Users can manage the version of the constructed computing process. The system automatically records the construction process, which facilitates analysis, traceability, and reproduction. Step 2.5: After the process is built, the user saves the process template for reuse as a reference in subsequent analysis.

[0065] Specifically, step 3 includes: Step 3.1: Once the visualization calculation process is determined, the user schedules the cross-platform professional calculation program engine module, which integrates core thermal-hydraulic program, containment analysis program and system transient behavior analysis program functional units; Step 3.2: The system automatically calls the corresponding computing units to perform calculations according to the process scheduling instructions. Users can set the execution order according to their needs, for example, performing system transient analysis first, and then automatically transferring the analysis results to the core thermal-hydraulic analysis function unit and the containment response analysis interface unit. At the same time, users can select the parallel computing or serial execution of the nuclear safety analysis professional program unit according to the computing power. Step 3.3: The system ensures seamless data sharing and efficient data transmission among functional units through standardized data interfaces, allowing users to focus only on the execution order and logic during this process; Step 3.4: During the calculation process, the visualization calculation process construction module monitors the running status of each module in real time; when the monitoring detects an anomaly, the system automatically triggers a prompt, and the user analyzes and modifies according to the error message.

[0066] Specifically, step 4 includes: Step 4.1: After the calculation task is completed, the system will synchronize the results to the graphical post-processing module. The user needs to confirm the types of data to be synchronized and whether the synchronization is in accordance with the preset conditions. Step 4.2: This module provides multi-dimensional interactive visualization analysis tools, allowing users to compare analysis results under different calculation schemes and parameters; it supports intuitive viewing of core analysis results (such as core temperature distribution, containment pressure changes, and key system parameter curves) through charts, animations, and 3D models. Step 4.3: The system supports the export and archiving of results for key physical quantities, the standardization of interfaces for downstream professionals, and the seamless flow of analysis data in the design, operation, and review stages. Users can select the appropriate template to generate calculation reports according to report publication requirements, and generate corresponding interface sheets according to downstream interface needs.

[0067] In summary, this application, through modular architecture and visualization process technology, breaks down data barriers between multiple disciplines and physical fields, including nuclear reactor thermal-hydraulic system analysis and containment analysis. It achieves efficient parametric modeling, automated task scheduling, multi-dimensional visualization post-processing, and intelligent recommendation feedback. The system possesses high flexibility, scalability, and security. It supports data traceability, process reproduction, and result tracking throughout the entire process, providing scientific and efficient technical support for the diverse safety analysis needs of next-generation nuclear power plants.

[0068] This application, based on the interdisciplinary technologies of nuclear engineering and computer science, integrates the entire process of front-end modeling, professional calculation, workflow construction, and result post-processing through the core logic of "modular decomposition, standardized collaboration, visual management and control, digital support, and cross-platform adaptation." It employs a dual-engine architecture of a precision layer (high-precision analysis program) and an agile layer (digital agile coordination process) and a multi-disciplinary program coordination calculation method to achieve high-precision and efficient collaborative analysis across the entire chain of reactor core thermal-hydraulic systems and containment. Its core principles are: eliminating functional barriers with a modular architecture; establishing cross-disciplinary data links with standardized data interfaces; achieving traceability of the analysis process with explicit workflows; balancing accuracy and efficiency with model accuracy enhancement and digital efficiency mechanisms; and adapting to heterogeneous computing environments through cross-platform deployment. This approach specifically addresses the shortcomings of existing technologies in terms of collaborative efficiency, workflow control, functional integration, adaptability, and analytical accuracy.

[0069] This application has the following functions: (1) Modeling and Parameter Input: Through the front-end graphical modeling module, multi-level parametric modeling of subsystems and components is carried out according to the thermal safety analysis requirements of pressurized water reactors. This includes core channel models, main piping models, pressure vessel models, steam generator models, pressurizer models, main pump models, dedicated safety system models, control models, and core physics models. The parameters for the above modeling are all derived from upstream professional interfaces. By embedding rules in the graphical modeling model, the connection between interface parameters and safety analysis models is established, and the dynamic updating capability of the model is achieved by using interface data as the driving force.

[0070] (2) Professional calculation programs: Based on the requirements of nuclear reactor safety analysis, the program includes CORTH, a sub-channel analysis program that meets the requirements of core thermal-hydraulic analysis; ARSAC, a system analysis program that meets the requirements of system transient behavior analysis; and CONAC & CONTHAP, a containment analysis program that meets the requirements of containment response analysis. Among them, CORTH has the ability to perform fine-grained analysis of the entire core steady-state and transient grid elements; ARSAC has the ability to accurately predict the system behavior of typical equipment, systems and components of pressurized water reactors; CONAC has the ability to perform efficient and fast containment pressure and temperature analysis; and CONTHAP has the ability to perform fine-grained and large-scale coarse-grid CFD analysis of the containment.

[0071] (3) Calculation process construction: Using the visual calculation process construction module, the graphical process blocks of the model, calculation, analysis and other links are connected in series / parallel through drag and drop, connection and other operations. The calculation process is customized, the system automatically records the process version and retains the operation trajectory, and supports flexible modification of the process and version backtracking.

[0072] (4) Calculation scheduling and execution: The visualization process module issues scheduling instructions, the cross-platform professional calculation program engine module starts the coordination architecture, schedules the core thermal-hydraulic subroutine, containment analysis subroutine and system analysis calculation program, and realizes collaborative calculation according to the defined process; during the process, automatic fault detection is used to deal with the problem of calculation interruption; and the current status of the process can be given in real time.

[0073] (5) Results processing and monitoring: The graphical post-processing module performs multi-dimensional interactive visualization analysis of the calculation results, compares the results of different schemes / time nodes, conducts trend analysis and anomaly detection of key physical quantities, monitors the calculation status in real time and issues warnings, and supports result export and full-process traceability.

[0074] (6) Data security and compliance management: Each module interacts with encrypted data through standardized data interfaces, allocates operation permissions based on the user permission hierarchical management mechanism, and achieves full-process operation traceability and responsibility allocation through operation log recording and behavior tracking, so as to ensure data security and operation compliance.

[0075] (7) Cross-platform adaptation: Based on the actual operating environment of each professional software and the requirements of security analysis, the module can be launched on a unified client under different hardware platforms and operating system environments, and supports concurrent access by multiple users and distributed computing resource scheduling.

[0076] The above description is only a specific embodiment of this application, but the protection scope of this application is not limited thereto. Any changes or substitutions that can be easily conceived by those skilled in the art within the scope of the technology disclosed in this application should be included within the protection scope of this application.

Claims

1. A precise and collaborative digital system for nuclear reactor safety analysis, characterized in that, include: The front-end graphical modeling module is used to perform graphical and standardized modeling of system analysis programs based on the thermal safety analysis requirements of nuclear pressurized water reactors. A cross-platform professional computing engine module is used to integrate core thermal-hydraulic analysis programs, system transient analysis programs, and containment response analysis programs, and to achieve transparent program invocation and resource scheduling in different system environments; The visualization computing process construction module is used to connect the various computing steps in a graphical manner. The graphical post-processing module is used for multi-dimensional visualization analysis and result comparison of calculation results; The overall system scheduling and management module is used for computing resource scheduling, resource management, and hierarchical access control.

2. The precision-sensitive collaborative digital system for nuclear reactor safety analysis according to claim 1, characterized in that, The front-end graphical modeling module includes: The component configuration unit is used to represent components and map upstream structural, physical, control, and system parameters to the parameters of component configuration, so as to realize rule-driven dynamic modeling. The modeling method integration unit is used to standardize the user's modeling process and integrates core modeling methods, drop-down annular cavity modeling methods, pressurizer modeling methods, and steam generator modeling methods.

3. The precision-sensitive collaborative digital system for nuclear reactor safety analysis according to claim 1, characterized in that, The cross-platform professional computing engine module includes: The Nuclear Safety Analysis Specialized Program Unit is used to integrate the Core Subchannel System Analysis Program, the Advanced Reactor System Analysis Program, and the Containment Response Analysis Program. A cross-platform runtime environment support unit is used to integrate the program through a unified architecture and to enable transparent calls to each analysis module through standardized interfaces; The computing resource management unit is used to support users in configuring computing resources and to enable switching between parallel computing and serial execution scheduling modes for the nuclear safety analysis professional program unit and its supporting functional units. The computing monitoring unit is used to monitor the CPU utilization, memory usage and data transmission status of each computing module in real time. When a computing interruption or abnormality is detected, it automatically records the breakpoint data and triggers an early warning.

4. The precision-sensitive collaborative digital system for nuclear reactor safety analysis according to claim 1, characterized in that, The visualization computation process building module includes: The graphical process orchestration engine unit is used to implement interactive computational logic design using draggable process blocks and visual data flow connection lines, and automatically records the process creation and modification history. The multi-dimensional result comparison unit is used to provide multi-dimensional and interactive visualization of the analysis results under different calculation schemes and parameters. The calculation process template management unit is used to save, load, and modify calculation process templates according to different accident types; The status tracking and viewing unit is used to display the running progress, completion status and key node time of each computing stage in real time through a graphical interface; The interface standardization unit is used to support the rapid integration of new nuclear safety analysis professional computing programs using standardized encapsulation protocols.

5. The precision-sensitive collaborative digital system for nuclear reactor safety analysis according to claim 1, characterized in that, The graphical post-processing module includes: The data output unit supports exporting data in various standardized data formats, and automatically retains metadata such as calculation parameters, analysis conditions, and result accuracy. The data comparison unit is used for interactive and visual comparison of different calculation schemes and parameter variables, enabling synchronous display of multi-dimensional results and dynamic correlation analysis.

6. The precision-sensitive collaborative digital system for nuclear reactor safety analysis according to claim 1, characterized in that, The overall system scheduling and management module includes: The permission hierarchy management unit is used to classify user permissions; The distributed computing management unit is used to intelligently allocate computing nodes, memory, and computing power resources based on the priority, computational complexity, and real-time load of multi-user concurrent tasks.

7. The precision-sensitive collaborative digital system for nuclear reactor safety analysis according to claim 1, characterized in that, It also includes auxiliary modules for implementing system-level security management and computing resource optimization. These auxiliary modules include: The security control unit is used to classify and verify users' operation permissions through a hierarchical permission management mechanism to ensure system operation compliance and data security. The resource optimization unit is used to intelligently schedule computing nodes and computing resources based on the computing needs of multi-user concurrent tasks and the real-time load status of hardware resources.

8. A precise and coordinated digital method for nuclear reactor safety analysis, characterized in that, Based on the system as described in any one of claims 1 to 7, the method comprises: Step 1: Front-end graphical processing and parametric modeling. The front-end graphical modeling module is used to build the model required for thermal safety analysis of pressurized water reactors. Step 2: Visualize the computing process construction, defining the computing logic and data flow through the visual computing process construction module; Step 3: Through the automated scheduling and parallel computing of the cross-platform professional computing engine module, call the integrated program for collaborative computing; Step 4: Graphical post-processing and multi-dimensional result comparison, visualizing and analyzing the calculation results.

9. The precise and sensitive collaborative nuclear reactor safety analysis method according to claim 8, characterized in that, Step 1 includes: Select the project and accident category to be analyzed, and the corresponding basic structure template will be automatically loaded. The core structure, system parameters, and boundary conditions are input in layers on the basic structural template, and interface data from upstream professionals is imported. Perform integrity and logical consistency checks on the input parameters, and prompt for correction of missing or conflicting data.

10. The precise and sensitive collaborative nuclear reactor safety analysis method according to claim 8, characterized in that, Step 3 includes: According to the process scheduling instructions, the corresponding computing units are automatically invoked, and collaborative computing is performed according to the execution order set by the user; Based on the available computing power, select the parallel computing or serial execution mode for the nuclear safety analysis program unit and its supporting functional units.

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