摘要
Under the development of numerical reactor technologies, multi-scale coupled simulation based on a unified platform has become a major research focus. Given the high extensibility and 3D solving capabilities of the finite volume platform OpenFOAM, a quasi-one-dimensional solver named STACO has been developed in this study to explore the feasibility of system-level analysis on this platform. STACO constructs physically representative geometries using structured meshes, retaining three-dimensional solution characteristics. Meanwhile, through the simplification of governing equations and the development of tailored constitutive models and thermal component libraries, the solver enables efficient simulation of single-phase flow and heat transfer. Validation against single-tube and system loop cases shows that STACO’s results agree well with those from RELAP5, demonstrating its ability to predict thermal-hydraulic parameter distributions accurately and confirming the feasibility of conducting system-level analysis within OpenFOAM. Ongoing work focuses on extending the solver to incorporate more complex capabilities, including two-phase flow and multi-domain coupling, so as to build a unified, multi-scale solution framework based on OpenFOAM.
| 投稿的翻译标题 | Development of a Nuclear Reactor System Analysis Solver Based on a Finite Volume Platform |
|---|---|
| 源语言 | 繁体中文 |
| 页(从-至) | 76-86 |
| 页数 | 11 |
| 期刊 | Hedongli Gongcheng/Nuclear Power Engineering |
| 卷 | 47 |
| 期 | 1 |
| DOI | |
| 出版状态 | 已出版 - 2026 |
关键词
- OpenFOAM
- Solver development
- System analysis
学术指纹
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