Abstract: 　　
　　The reactor core is a critical component of nuclear power systems with a complex geometric structure, and it experiences strong coupling effects between various physical fields. High-precision thermal-hydraulic and multi-physics coupling analysis of the core is essential for ensuring the safety design and safety analysis of advanced nuclear power systems. The Nuclear Reactor Thermal-Hydraulic Laboratory (NuTHeL) at Xi'an Jiaotong University has developed a full-core neutronic-thermal-fluid-deposition multi-physics coupling analysis model, and has independently developed the CorTAF code for three-dimensional analysis at the full-core channel level based on the open-source CFD platform. Based on CorTAF code, a cross-scale coupling strategy between the core model of CorTAF and the detailed three-dimensional thermal-hydraulic model of the pressure vessel was proposed, which allows CFD-based multi-physics calculations and predictions for the entire pressure vessel. Validation and verification work has also been conducted based on international benchmark problems. In recent years, the research team has continually developed and refined the mathematical and physical models of the code. Currently, the CorTAF code supports cross-scale coupling calculations for multiple reactor types (PWR, LFR, SFR), physical fields (Neutronics, Thermal hydraulic, Deposition), and system structures (Core, Lower plenum, Upper plenum). This paper reviews the development process of the CorTAF series codes, presents their main functions and applications in PWR calculation, summarizes the current computational results, and discusses the future direction of the program's development.
　　The reactor core is a critical component of nuclear power systems with a complex geometric structure, and it experiences strong coupling effects between various physical fields. High-precision thermal-hydraulic and multi-physics coupling analysis of the core is essential for ensuring the safety design and safety analysis of advanced nuclear power systems. The Nuclear Reactor Thermal-Hydraulic Laboratory (NuTHeL) at Xi'an Jiaotong University has developed a full-core neutronic-thermal-fluid-deposition multi-physics coupling analysis model, and has independently developed the CorTAF code for three-dimensional analysis at the full-core channel level based on the open-source CFD platform. Based on CorTAF code, a cross-scale coupling strategy between the core model of CorTAF and the detailed three-dimensional thermal-hydraulic model of the pressure vessel was proposed, which allows CFD-based multi-physics calculations and predictions for the entire pressure vessel. Validation and verification work has also been conducted based on international benchmark problems. In recent years, the research team has continually developed and refined the mathematical and physical models of the code. Currently, the CorTAF code supports cross-scale coupling calculations for multiple reactor types (PWR, LFR, SFR), physical fields (Neutronics, Thermal hydraulic, Deposition), and system structures (Core, Lower plenum, Upper plenum). This paper reviews the development process of the CorTAF series codes, presents their main functions and applications in PWR calculation, summarizes the current computational results, and discusses the future direction of the program's development.