Abstract The thermal hydraulic performances of Steam Generator (SG) under both steady and transient operation conditions are of great importance for the safety and economy in nuclear power plants. In this paper, based on our self-developed SG thermal hydraulic analysis code STAF (Steam-generator Thermal-hydraulic Analysis code based on Fluent), an improved new version STAF-CT (fully Coupling and Transient) is developed and introduced. Compared with original STAF, the new version code STAF-CT has two main functional improvements including “Transient” and “Fully Three Dimensional Coupling” features. In STAF-CT, a three dimensional energy transferring module is established which can achieve energy exchange computing function at the corresponding position between two sides of SG. The STAF-CT is validated against the international benchmark experiment data and the results show great agreement. Then the U-shaped SG in AP1000 nuclear power plant is modeled and simulated using STAF-CT. The results show that three dimensional flow fields in the primary side make significant effect on the energy source distribution between two sides. The development of code STAF-CT in this paper can provide an effective method for further SG high fidelity research in the nuclear reactor system.

中文翻译：

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高保真蒸汽发生器三维热力液压联轴器的研制代码：STAF-CT

摘要 蒸汽发生器（SG）在稳态和瞬态工况下的热工水力性能对核电站的安全性和经济性具有重要意义。本文在我们自主开发的SG热工水力分析代码STAF（Steam-generator Thermal-Hydraulic Analysis code based on Fluent）的基础上，开发并介绍了改进的新版本STAF-CT（全耦合瞬态）。与原STAF相比，新版本代号STAF-CT有两个主要功能改进，包括“瞬态”和“全三维耦合”特性。在STAF-CT中，建立了一个三维能量传递模块，可以实现SG两侧相应位置的能量交换计算功能。STAF-CT 根据国际基准实验数据进行了验证，结果显示出很大的一致性。然后使用STAF-CT对AP1000核电站中的U形SG进行建模和模拟。结果表明，一次侧三维流场对两侧能量源分布有显着影响。本文开发的代码STAF-CT可以为进一步研究核反应堆系统的SG高保真度提供一种有效的方法。