基于CFD方法的核动力系统热工安全特性研究进展

Review on Safety Characteristic Research Progress of Nuclear Power Plant Thermal-hydraulics Using CFD Method

西安交通大学核反应堆热工水力团队(XJTU-NuTheL)长期致力于计算流体动力学(CFD)方法的核动力系统高精度热工水力模型开发及应用方面的研究。近些年,团队在单相CFD工程应用、两相CFD模型开发、大涡模拟(LES)及直接数值模拟(DNS)高性能并行计算、跨尺度多物理场耦合等方面取得了系列研究成果。主要包括:构建了核反应堆压力容器、蒸汽发生器、非能动余热排出系统换热器等核动力系统关键设备的三维多孔介质热工水力计算模型,建立了复杂物理现象及运动瞬变工况下的两相CFD数学物理模型,开发了CFD程序与核反应堆系统程序、堆芯子通道程序之间的跨尺度耦合以及与中子物理、力学程序之间的多物理场耦合分析平台。本文将重点阐述XJTU-NuTheL基于CFD方法在核反应堆热工水力研究方面的最新成果及进展,并提出CFD方法在核反应堆工程领域应用的主要挑战及发展方向,旨在促进CFD方法更好地服务于核动力系统设计与运行安全分析。

Xi’an Jiaotong University Nuclear Thermal-hydraulic Laboratory (XJTU-NuTheL) has been committed to the development and application of high-precision thermal-hydraulic models of nuclear power plant based on CFD method.In recent years,series of research achievements in various nuclear engineering fields including single-phase CFD application,two-phase CFD model development,large eddy simulation (LES) and direct numerical simulation (DNS),were accomplished in XJTU-NuTheL.The three-dimensional porous media thermal-hydraulic models for key equipments thermal -hydraulic study in the nuclear power plant such as reactor pressurized vessel,steam generator and passive residual heat exchanger were developed.The mathematical models of complicate two-phase phenomena and ocean moving conditions were established.Also,with the high fidelity simulation requirement of the whole reactor system,the nuclear reactor system multi-dimensional and multi-physics coupling platforms were developed based on CFD codes.In this paper,the latest achievements on the nuclear reactor thermal-hydraulic research using CFD method at XJTU-NuTheL were introduced and described.In addition,the major challenges and promising directions of CFD applications on the nuclear reactor engineering field were proposed,which would be beneficial for the promotion of its further application.