热工水力程序输入模型兼容性与转换方法研究

Study on Input Model Compatibility and Conversion Methods for Thermal-Hydraulic System Codes

摘要: 热工水力系统分析程序的验证与确认已形成较为完善的国际合作项目和试验数据支撑。然而，对于新开发的程序，仍需依据其输入规范重新开展大量的建模与校核工作。为提高复杂系统输入模型的建模与复用效率，本文针对程序间输入模型兼容性问题，构建了程序间输入模型转换框架与一致化建模技术路径。选取我国大型非能动压水堆为研究对象，以代表性的RELAP5至TRACE程序转换为实例，系统阐述了程序间输入模型的转换、迭代修正与交叉验证流程。典型工况的预测对比结果表明，转换后的模型能够再现事故主要瞬态过程及关键热工水力现象，两程序关键输出参数的变化趋势总体一致，模型转换框架具备可行性。研究表明，在程序研发与验证阶段引入输入模型兼容、转换与复用机制，能够减少重复建模与校核工作量，为程序间交叉验证和偏差溯源提供技术基础。本文工作可为后续同类堆型的输入模型转换、程序间交叉验证和自主化热工水力系统分析程序的开发与验证提供参考。

Abstract: Verification and validation of thermal-hydraulic system codes have been supported by relatively mature international collaborative projects and experimental databases. However, for newly developed codes, extensive modeling and consistency-checking efforts still need to be repeated according to their specific input specifications. To improve the efficiency of constructing and reusing complex system input models, this study addresses the compatibility problem of input models among different codes and establishes an inter-code input model conversion framework and a consistent modeling workflow. A large passive pressurized water reactor in China is selected as the research object, and a representative RELAP5-to-TRACE conversion is employed as an example to systematically describe the conversion, iterative correction, and cross-verification process of inter-code input models. Comparative predictions under typical conditions show that the converted model can reproduce the major accident transient processes and key thermal-hydraulic phenomena, while the key output parameters predicted by the two codes exhibit generally consistent trends, demonstrating the feasibility of the proposed model conversion framework. The results indicate that introducing input model compatibility, conversion, and reuse mechanisms into code development and validation can reduce repetitive modeling and consistency-checking efforts, and provide a technical basis for cross-code verification and deviation source identification. This work can provide a reference for subsequent input model conversion of similar reactor types, cross-code verification, and the development and validation of indigenous thermal-hydraulic system codes.