Fuel assemblies with wire spacer are widely used in Generation IV liquid nuclear reactors. With the rapid development of computational power, the Computational Fluid Dynamic (CFD) method is becoming an effective tool to investigate the detailed three-dimensional thermal hydraulic characteristics in wire-wrapped fuel assemblies. Due to the complexity of geometry, most of the published researches are performed with large number tetrahedron or polyhedral cells. The simulation is quite time-consuming and is generally limited to assemblies with small number of fuel pins. In this paper, a hexahedron meshing strategy is developed based on the Radial Basis Function (RBF) theory in present paper. This strategy would be beneficial for the modeling for the wire-wrapped fuel assemblies in real nuclear reactor core with large number of fuel pins. To validate this strategy, two experiments are simulated and detailed flow parameter distributions within the bundle, including the pressure distribution and the temperature distribution, have been compared. Good agreements have been achieved between the simulation results and the experimental results.

带有金属丝垫片的燃料组件被广泛用于第四代液体核反应堆。随着计算能力的飞速发展，计算流体动力学（CFD）方法正成为研究线绕式燃料组件中详细的三维热工水力特性的有效工具。由于几何形状的复杂性，大多数已发表的研究都是使用大量的四面体或多面体单元进行的。模拟非常耗时，并且通常仅限于带有少量燃料销的组件。本文基于径向基函数（RBF）理论，提出了一种六面体网格化策略。该策略对于具有大量燃料销的真实核反应堆堆芯中的线绕燃料组件的建模将是有益的。为了验证该策略，对两个实验进行了仿真，并比较了束中的详细流量参数分布，包括压力分布和温度分布。仿真结果与实验结果之间取得了良好的一致性。