A method and apparatus for evaluating a nuclear plant

Abstract

The application discloses a nuclear equipment evaluation method and device, and relates to the field of nuclear equipment design. The method comprises the following steps: obtaining a geometric model of a preset nuclear equipment scheme; establishing a finite element analysis model according to the geometric model; solving the finite element analysis model to obtain component information; and generating an evaluation result according to the component information. The method automatically calls a geometric model database and a material performance database, avoids repeated modeling operations of designers and engineers in a traditional process, shortens the finite element model establishment time, eliminates errors that are prone to occur when material data is manually matched, and ensures the accuracy and efficiency of the preprocessing stage. Through the synergistic effect of an evaluation criterion database and a report automatic generation module, the report writing time is shortened, human errors are reduced through a standardized feedback mechanism, the checking efficiency of analysis conclusions is greatly improved, and finally, the whole process optimization from parameter input to report generation is realized.

Description

Technical Field

[0001] This application relates to the field of nuclear equipment design, and in particular to a method and apparatus for evaluating nuclear equipment. Background Technology

[0002] Reactor structural mechanics analysis is a critical process in nuclear engineering to ensure the safe operation of nuclear facilities. In facilities such as nuclear power plants, equipment must withstand extreme conditions such as high temperatures and pressures, thus necessitating structural strength assessments using computer-aided techniques. Specifically, this process involves geometric model creation, material property assignment, finite element analysis (FEM), and stress-based safety evaluation. Designers first provide equipment parameters, which engineers then use to build digital models, simulating the stress conditions under different operating conditions, and ultimately determining whether the structure meets safety standards. This process is crucial for preventing nuclear leaks or equipment failure.

[0003] In existing technologies, reactor structural mechanics analysis primarily relies on two-dimensional CAD drawings to transfer design parameters, resulting in low efficiency and insufficient reliability. Designers and engineers must repeatedly draw geometric models, wasting significant time; engineers must manually match material property data to the finite element model, a process prone to errors and dependent on human experience; report writing and verification require manual extraction of calculation results and documentation, leading to high field redundancy and requiring verifiers to rerun code for verification, consuming additional time; more seriously, the lack of a standardized feedback mechanism for analysis results to structural design fails to ensure timely design optimization, increasing overall design risk. These problems collectively reduce the efficiency and reliability of the analysis process. Summary of the Invention

[0004] In view of this, this application provides a method and apparatus for evaluating nuclear equipment, the main purpose of which is to solve the technical problems of low efficiency and insufficient reliability of existing reactor structural mechanics analysis processes.

[0005] According to one aspect of this application, a method for evaluating nuclear facilities is provided, the method comprising:

[0006] Obtain the geometric model of the preset nuclear equipment scheme; A finite element analysis model is established based on the described geometric model; Solve the finite element analysis model to obtain component information; An evaluation result is generated based on the component information.

[0007] In one feasible implementation, the step of obtaining the geometric model of the preset nuclear device scheme includes: Obtain the structural parameters of the preset nuclear equipment scheme, and call the matching geometric model in the geometric model database according to the structural parameters.

[0008] In one feasible implementation, the structural parameters include: Structural type, structural dimensions, material information, analysis conditions, operating temperature and pressure.

[0009] In one feasible implementation, the step of establishing the finite element analysis model based on the geometric model includes: The geometric model is modified by geometric features, segmented features and meshed to obtain the finite element analysis model. Material property data from the material property database is then used to assign material properties to the finite element analysis model.

[0010] In one feasible implementation, the step of solving the finite element analysis model to obtain component information includes: The finite element analysis model is solved using finite element methods to obtain the solution results; The solution results are post-processed to obtain the component information.

[0011] In one feasible implementation, the step of post-processing the solution result includes: Identify the areas of interest, and obtain the component information of the areas of interest in batches based on the solution results.

[0012] In one feasible implementation, the step of generating evaluation results based on the component information includes: Obtain the operating condition information of the preset nuclear equipment scheme, call the matching evaluation criteria in the evaluation criterion database, analyze and evaluate the component information according to the operating condition information and the evaluation criteria, and generate evaluation results; Check whether the evaluation results meet the requirements. If they do, generate an evaluation report based on the evaluation results.

[0013] In one feasible implementation, the step of checking whether the evaluation result meets the requirements further includes: If the requirements are not met, the finite element solution and subsequent steps are repeated. Once the requirements are met, the evaluation report is generated. If the requirements are still not met, a feedback report will be generated based on the evaluation results.

[0014] In one feasible implementation, the method further includes: A preliminary analysis report is generated based on the evaluation report or the feedback report, project information of the preset nuclear equipment scheme is obtained, and a complete report is generated based on the preliminary analysis report and the project information.

[0015] According to another aspect of this application, a nuclear facility evaluation apparatus is provided, the apparatus comprising: The structural parameter input module 10 is used to obtain the structural parameters of the preset nuclear equipment scheme. The structural parameter input module 10 includes a structural type input module 101, a structural dimension input module 102, and other parameter input modules 103. The model library calling module 20 is used to call the matching geometric model in the geometric model database according to the structural parameters; Finite element modeling module 30 is used to establish a finite element analysis model based on the geometric model; Finite element solution module 40 is used to perform finite element solution on the finite element analysis model to obtain the solution results; The post-processing module 50 is used to determine the parts of interest and obtain the component information of the parts of interest in batches based on the solution results; The calculation result evaluation module 60 is used to obtain the operating condition information of the preset nuclear equipment scheme, call the matching evaluation criteria in the evaluation criteria database, analyze and evaluate the component information according to the operating condition information and the evaluation criteria, generate evaluation results, and check whether the evaluation results meet the requirements. Report generation module 70 is used to generate an evaluation report based on the evaluation results; The geometric model database 80 is used to store the geometric models of the nuclear equipment with preset finite element analysis models. The geometric model database 80 includes a cylinder model database 801, a head model database 802, a nozzle model database 803, a support model database 804, a plate and shell model database 805, and other model databases 806. The material property database 90 is used to store preset material property data and assign material properties to the finite element analysis model. The material property database 90 includes a physical property database 901 and a mechanical property database 902. The load database 100 is used to store preset finite element solution results. The load database 100 includes a temperature and pressure database 1001, a mechanical load database 1002, a preload 1003, and other load databases 1004. The evaluation criteria database 110 is used to store preset evaluation criteria. The evaluation criteria database 110 includes the ASME code evaluation criteria database 1101, the RCC-M code evaluation criteria database 1102, the GBT standard evaluation criteria database 1103, and other code or standard evaluation criteria databases 1104.

[0016] This application provides a method and apparatus for evaluating nuclear equipment. The method includes: obtaining a geometric model of a preset nuclear equipment scheme; establishing a finite element analysis model based on the geometric model; solving the finite element analysis model to obtain component information; and generating evaluation results based on the component information. Compared with traditional reactor structural mechanics analysis methods and processes, this application has the following significant technical advantages: A database of commonly used geometric models and material properties for reactor structures has been established, enabling structural engineers to quickly complete finite element modeling and material assignment for reactor structures, thus improving preprocessing efficiency. A database of nuclear equipment evaluation criteria and an automatic report generation module were established, which can automatically analyze and evaluate the calculation results and generate corresponding preliminary report documents, reducing the probability of human error in the processing of calculation results by structural engineers and improving the efficiency of report writing. It standardizes the feedback process from structural engineers to the design team based on the results of mechanical analysis and evaluation, making the final analysis conclusions more reliable.

[0017] The entire analysis and design process is traceable and viewable, which improves the efficiency of the verification work of the verification personnel.

[0018] The above description is only an overview of the technical solution of this application. In order to better understand the technical means of this application and to implement it in accordance with the contents of the specification, and to make the above and other objects, features and advantages of this application more obvious and understandable, specific embodiments of this application are given below. Attached Figure Description

[0019] The accompanying drawings, which are included to provide a further understanding of this application and form part of this application, illustrate exemplary embodiments and are used to explain this application, but do not constitute an undue limitation of this application. In the drawings: Figure 1 A schematic flowchart of a nuclear equipment evaluation method provided in an embodiment of this application is shown; Figure 2 This paper shows a structural block diagram of a nuclear equipment evaluation apparatus provided in an embodiment of this application; Figure 3 A schematic diagram of the geometric model of the scheme for obtaining a preset core device provided in an embodiment of this application is shown; Figure 4 A schematic diagram illustrating the acquisition of the finite element analysis model provided in an embodiment of this application is shown; Figure 5 This illustration shows a schematic diagram of analyzing and evaluating the component information provided in an embodiment of this application. Detailed Implementation

[0020] The present application will be described in detail below with reference to the accompanying drawings and embodiments. It should be noted that, unless otherwise specified, the embodiments and features described in the embodiments of the present application can be combined with each other.

[0021] See Figure 1 The diagram illustrates a flowchart of a nuclear equipment evaluation method provided in an embodiment of this application. The method includes: Step S1: Obtain the geometric model of the preset nuclear equipment scheme; In the above embodiments, the user inputs key structural parameters of the nuclear equipment scheme through the interface of this application. After receiving these parameters, this application automatically searches and matches them in a preset geometric model database, and calls the corresponding standardized and parametric geometric model. This process replaces the tedious work of manually redrawing drawings in the past.

[0022] This application enables rapid reuse and automatic recall of geometric models, greatly reducing the time and effort required by engineers in the model preparation stage, avoiding repetitive work, improving design efficiency from the source, and laying the foundation for the standardization of subsequent analysis.

[0023] Step S2: Establish a finite element analysis model based on the geometric model; In the above embodiments, after the selected geometric model is invoked, this application can automatically or assisted the user in performing necessary geometric drawing, feature modification, and mesh generation to form the finite element mesh required for calculation. Subsequently, this application will further automatically link to the material property database and assign appropriate material properties, such as strength and elastic modulus, to each part of the mesh model based on the material information in the design parameters.

[0024] This application systematizes and automates the modeling and material assignment process, significantly reducing the risk of model setting errors due to human error, ensuring the consistency and accuracy of the finite element model, and providing an important guarantee for obtaining reliable calculation results.

[0025] Step S3: Solve the finite element analysis model to obtain component information; In the above embodiments, this application submits the constructed finite element analysis model to the solver for mechanical calculations, completing numerical simulations such as stress analysis. After the solution is completed, this application performs post-processing on the large amount of raw calculation results data, and extracts the mechanical information of specific parts or components of interest to the user through batch operations, such as maximum stress value and deformation.

[0026] The batch post-processing function of this application can quickly and accurately locate and extract key information from massive calculation results, avoiding omissions and errors that may be caused by manual querying and recording one by one, and greatly improving the efficiency of data processing and the reliability of results.

[0027] Step S4: Generate evaluation results based on the component information.

[0028] In the above embodiments, after obtaining the component information, this application simultaneously calls a preset database of operating condition information and evaluation criteria, such as international or industry standards like the American Society of Mechanical Engineers (ASME) and the French Code for Design and Construction of Mechanical Equipment in Pressurized Water Reactor Nuclear Island (RCC-M), to automatically compare and analyze the component information with the evaluation criteria, thereby generating an evaluation conclusion on whether the structure is safe and qualified. If the requirements are met, an evaluation report is automatically generated.

[0029] This application automates and standardizes the analysis and evaluation process, reduces over-reliance on the personal experience of evaluators, avoids subjective biases that may arise from manual interpretation, makes the evaluation results more objective and consistent, and significantly improves the report generation speed.

[0030] See Figure 3 The diagram illustrates a geometric model of a preset core device scheme provided in an embodiment of this application. Further, the step of obtaining the geometric model of the preset core device scheme includes: Obtain the structural parameters of the preset nuclear equipment scheme, and call the matching geometric model in the geometric model database according to the structural parameters.

[0031] In the above embodiments, this application provides a structured parameter input interface to guide users in inputting key information such as device type and size specifications. After input, this application uses these parameters as indexing conditions to automatically search and retrieve the most matching 3D geometric model from a vast geometric model library.

[0032] This application enables the reuse of design knowledge through a parametric-driven approach, allowing users to quickly obtain accurate professional models without requiring extensive 3D modeling skills. This lowers the technical barrier and ensures the quality and standardization of the models.

[0033] Furthermore, the structural parameters include: Structural type, structural dimensions, material information, analysis conditions, operating temperature and pressure.

[0034] In the above embodiments, the structural parameters required by this application encompass comprehensive information ranging from geometry and material properties to load boundary conditions. These parameters are systematically organized to collectively define a specific analysis task, providing complete and structured data input for the automation of all subsequent steps.

[0035] Comprehensive and structured parameter definitions ensure the integrity and accuracy of the analysis task, providing a reliable data foundation for the entire automated process and avoiding process interruptions or errors caused by missing or non-standard input information.

[0036] See Figure 4 The diagram illustrates how the finite element analysis model is obtained according to an embodiment of this application. Further, the step of establishing the finite element analysis model based on the geometric model includes: The geometric model is modified by geometric features, segmented features and meshed to obtain the finite element analysis model. Material property data from the material property database is then used to assign material properties to the finite element analysis model.

[0037] In the above embodiments, this application can perform preprocessing on the basic geometric model to adapt to finite element calculations, such as simplifying fine features and segmenting complex regions to facilitate mesh generation. Subsequently, a high-quality computational mesh is automatically or assisted in its generation. After mesh generation, this application can automatically retrieve the corresponding performance parameters from the material database based on the material identifiers of each part of the model and assign values ​​accordingly.

[0038] This application integrates and automates the tedious model preparation and setup process, ensuring the quality of the finite element model and completely eliminating errors that may occur when manually assigning materials, thus greatly improving the efficiency and accuracy of model preparation.

[0039] Furthermore, the step of solving the finite element analysis model to obtain component information includes: The finite element analysis model is solved using finite element methods to obtain the solution results; The solution results are post-processed to obtain the component information.

[0040] In the above embodiments, this application automatically configures the solution parameters and submits the mesh model to the solver for calculation. After the calculation is completed, this application imports the result file and provides post-processing tools, allowing users to easily view the result file and supporting batch extraction of data such as membrane stress, membrane plus bending stress, and the sum of triaxial principal stresses at key locations to form a component information list.

[0041] This application seamlessly integrates the solution and post-processing. Its batch extraction function addresses the actual needs in engineering evaluation, enabling rapid focus on key points and saving significant time spent on result screening and data processing, allowing engineers to enter the analysis and judgment phase more quickly.

[0042] Furthermore, the post-processing step of the solution result includes: Identify the areas of interest, and obtain the component information of the areas of interest in batches based on the solution results.

[0043] In the above embodiments, users can predefine or select components or areas that require focused evaluation in this application. During post-processing, this application automatically identifies these areas of interest, traverses these locations in batches, extracts all relevant mechanical response data, and organizes them into tables or reports.

[0044] This application enables batch and automated extraction of key data, completely changing the inefficient traditional manual selection and recording mode. It is not only extremely fast, but also ensures the comprehensiveness and completeness of data extraction, providing a solid foundation for accurate evaluation.

[0045] See Figure 5 This illustration shows a schematic diagram of analyzing and evaluating the component information provided in an embodiment of this application. Further, the step of generating an evaluation result based on the component information includes: Obtain the operating condition information of the preset nuclear equipment scheme, call the matching evaluation criteria in the evaluation criterion database, analyze and evaluate the component information according to the operating condition information and the evaluation criteria, and generate evaluation results; Check whether the evaluation results meet the requirements. If they do, generate an evaluation report based on the evaluation results.

[0046] In the above embodiments, this application reads the project attributes, equipment type, analysis conditions, and material information of the analysis task, defines a linearized evaluation path, evaluates components in numerical order, and automatically selects the applicable evaluation standard. Then, this application automatically compares the previously extracted component information with the allowable limits specified in the standard to determine whether it is qualified, and automatically generates an evaluation report containing the judgment conclusion, data comparison table, and visualization results.

[0047] This application realizes the intelligentization and automation of the evaluation process, freeing engineers from the heavy mental labor of reviewing a large number of standard clauses, manually calculating limits, and comparing data. The evaluation results are fast and reliable, the reports are automatically generated, and the consistency is good, which greatly improves the overall work efficiency and report quality.

[0048] Furthermore, the step of checking whether the evaluation result meets the requirements also includes: If the requirements are not met, the finite element solution and subsequent steps are repeated. Once the requirements are met, the evaluation report is generated. If the requirements are still not met, a feedback report will be generated based on the evaluation results.

[0049] In the above embodiments, when the evaluation finds that the requirements are not met, this application needs to re-trigger the solution, post-processing and evaluation process. If the requirements are still not met after recalculation, a detailed feedback report will be automatically generated, clearly pointing out the problems in the structural design and the specific items that are not met, providing designers with a clear direction for improvement.

[0050] This application constructs a complete closed loop from analysis to evaluation to feedback, which can identify structural design problems. Simultaneously, the automated feedback reporting function ensures the accurate transmission and traceability of design issues, improves collaboration efficiency between cross-disciplinary teams, and accelerates the design finalization process.

[0051] Furthermore, the method also includes: A preliminary analysis report is generated based on the evaluation report or the feedback report, project information of the preset nuclear equipment scheme is obtained, and a complete report is generated based on the preliminary analysis report and the project information.

[0052] In the above embodiments, this application uses the automatically generated evaluation report or feedback report as the core content, and then automatically integrates the basic information of the project, such as project name, equipment number, designer, analyst, date, etc., to assemble a final analysis report document with a standardized format and complete content.

[0053] This application automates the entire report generation process, ensuring the standardization and professionalism of the output documents, saving a significant amount of time required for manual compilation, summarization, and formatting of reports, and guaranteeing the quality and efficiency of nuclear facility delivery.

[0054] See Figure 2 The diagram illustrates a structural block diagram of a nuclear equipment evaluation apparatus provided in an embodiment of this application. The apparatus includes: The structural parameter input module 10 is used to obtain the structural parameters of the preset nuclear equipment scheme. The structural parameter input module 10 includes a structural type input module 101, a structural dimension input module 102, and other parameter input modules 103. The model library calling module 20 is used to call the matching geometric model in the geometric model database according to the structural parameters; Finite element modeling module 30 is used to establish a finite element analysis model based on the geometric model; Finite element solution module 40 is used to perform finite element solution on the finite element analysis model to obtain the solution results; The post-processing module 50 is used to determine the parts of interest and obtain the component information of the parts of interest in batches based on the solution results; The calculation result evaluation module 60 is used to obtain the operating condition information of the preset nuclear equipment scheme, call the matching evaluation criteria in the evaluation criteria database, analyze and evaluate the component information according to the operating condition information and the evaluation criteria, generate evaluation results, and check whether the evaluation results meet the requirements. Report generation module 70 is used to generate an evaluation report based on the evaluation results; The geometric model database 80 is used to store the geometric models of the nuclear equipment with preset finite element analysis models. The geometric model database 80 includes a cylinder model database 801, a head model database 802, a nozzle model database 803, a support model database 804, a plate and shell model database 805, and other model databases 806. The material property database 90 is used to store preset material property data and assign material properties to the finite element analysis model. The material property database 90 includes a physical property database 901 and a mechanical property database 902. The load database 100 is used to store preset finite element solution results. The load database 100 includes a temperature and pressure database 1001, a mechanical load database 1002, a preload 1003, and other load databases 1004. The evaluation criteria database 110 is used to store preset evaluation criteria. The evaluation criteria database 110 includes the ASME code evaluation criteria database 1101, the RCC-M code evaluation criteria database 1102, the recommended national standard (GBT) evaluation criteria database 1103, and other code or standard evaluation criteria databases 1104.

[0055] It should be noted that other corresponding descriptions of the functional units involved in the nuclear equipment evaluation device provided in this embodiment can be found in [reference]. Figure 1 The corresponding description in [the document] will not be repeated here.

[0056] This application provides a method and apparatus for evaluating nuclear equipment. The method includes: obtaining a geometric model of a preset nuclear equipment scheme; establishing a finite element analysis model based on the geometric model; solving the finite element analysis model to obtain component information; and generating an evaluation result based on the component information.

[0057] This application avoids repetitive modeling operations by designers and engineers in traditional processes by automatically calling geometric model databases and material property databases, shortening the finite element model establishment time and eliminating errors that are prone to occur when manually matching material data, thus ensuring the accuracy and efficiency of the preprocessing stage. Through the synergy of the evaluation criterion database and the automatic report generation module, it not only shortens the report writing time but also reduces human error through a standardized feedback mechanism, significantly improving the efficiency of verifying analysis conclusions, and ultimately achieving full-process optimization from parameter input to report generation.

[0058] Those skilled in the art will understand that the accompanying drawings are merely schematic diagrams of a preferred embodiment, and the modules or processes shown in the drawings are not necessarily essential for implementing this application. Those skilled in the art will understand that the modules in the apparatus of the embodiment can be distributed within the apparatus of the embodiment as described, or can be modified to be located in one or more apparatuses different from this embodiment. The modules of the above-described embodiment can be combined into one module, or further divided into multiple sub-modules.

[0059] The serial numbers in this application are for descriptive purposes only and do not represent the superiority or inferiority of any particular implementation scenario. The above disclosures are merely a few specific implementation scenarios of this application; however, this application is not limited thereto, and any variations conceived by those skilled in the art should fall within the protection scope of this application.

Claims

1. A method for evaluating nuclear facilities, characterized in that, The method includes: Obtain the geometric model of the preset nuclear equipment scheme; A finite element analysis model is established based on the described geometric model; Solve the finite element analysis model to obtain component information; An evaluation result is generated based on the component information.

2. The method according to claim 1, characterized in that, The step of obtaining the geometric model of the preset nuclear equipment scheme includes: Obtain the structural parameters of the preset nuclear equipment scheme, and call the matching geometric model in the geometric model database according to the structural parameters.

3. The method according to claim 2, characterized in that, The structural parameters include: Structural type, structural dimensions, material information, analysis conditions, operating temperature and pressure.

4. The method according to claim 1, characterized in that, The steps for establishing a finite element analysis model based on the geometric model include: The geometric model is modified by geometric features, segmented features and meshed to obtain the finite element analysis model. Material property data from the material property database is then used to assign material properties to the finite element analysis model.

5. The method according to claim 1, characterized in that, The steps for solving the finite element analysis model to obtain component information include: The finite element analysis model is solved using finite element methods to obtain the solution results; The solution results are post-processed to obtain the component information.

6. The method according to claim 5, characterized in that, The post-processing steps for the solution results include: Identify the areas of interest, and obtain the component information of the areas of interest in batches based on the solution results.

7. The method according to claim 1, characterized in that, The step of generating evaluation results based on the component information includes: Obtain the operating condition information of the preset nuclear equipment scheme, call the matching evaluation criteria in the evaluation criterion database, analyze and evaluate the component information according to the operating condition information and the evaluation criteria, and generate evaluation results; Check whether the evaluation results meet the requirements. If they do, generate an evaluation report based on the evaluation results.

8. The method according to claim 7, characterized in that, The step of checking whether the evaluation result meets the requirements also includes: If the requirements are not met, the finite element solution and subsequent steps are repeated. Once the requirements are met, the evaluation report is generated. If the requirements are still not met, a feedback report will be generated based on the evaluation results.

9. The method according to claim 8, characterized in that, The method further includes: A preliminary analysis report is generated based on the evaluation report or the feedback report, project information of the preset nuclear equipment scheme is obtained, and a complete report is generated based on the preliminary analysis report and the project information.

10. A nuclear equipment evaluation device, characterized in that, The device includes: The structural parameter input module 10 is used to obtain the structural parameters of the preset nuclear equipment scheme. The structural parameter input module 10 includes a structural type input module 101, a structural dimension input module 102, and other parameter input modules 103. The model library calling module 20 is used to call the matching geometric model in the geometric model database according to the structural parameters; Finite element modeling module 30 is used to establish a finite element analysis model based on the geometric model; Finite element solution module 40 is used to perform finite element solution on the finite element analysis model to obtain the solution results; The post-processing module 50 is used to determine the parts of interest and obtain the component information of the parts of interest in batches based on the solution results; The calculation result evaluation module 60 is used to obtain the operating condition information of the preset nuclear equipment scheme, call the matching evaluation criteria in the evaluation criteria database, analyze and evaluate the component information according to the operating condition information and the evaluation criteria, generate evaluation results, and check whether the evaluation results meet the requirements. Report generation module 70 is used to generate an evaluation report based on the evaluation results; The geometric model database 80 is used to store the geometric models of the nuclear equipment with preset finite element analysis models. The geometric model database 80 includes a cylinder model database 801, a head model database 802, a nozzle model database 803, a support model database 804, a plate and shell model database 805, and other model databases 806. The material property database 90 is used to store preset material property data and assign material properties to the finite element analysis model. The material property database 90 includes a physical property database 901 and a mechanical property database 902. The load database 100 is used to store preset finite element solution results. The load database 100 includes a temperature and pressure database 1001, a mechanical load database 1002, a preload 1003, and other load databases 1004. The evaluation criteria database 110 is used to store preset evaluation criteria. The evaluation criteria database 110 includes the ASME code evaluation criteria database 1101, the RCC-M code evaluation criteria database 1102, the GBT standard evaluation criteria database 1103, and other code or standard evaluation criteria databases 1104.

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