Numerical simulation study on the fluid excitation force on a nuclear fuel rod with a spacer grid. (January 2023)

• Record Type: Journal Article
• Authors: Wang, Yihu; Zheng, Meiyin; Zhang, Jing; Jiao, Yongjun; Wu, Yingwei; Tian, Wenxi; Su, G.H.; Qiu, Suizheng
• Is Part Of: Annals of nuclear energy. Volume 180(2023)
• Publication Date: 2023-01
• Subjects: Computational fluid dynamics -- Nuclear reactor thermal hydraulics -- Flow induced vibration; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2022.109472
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: The flow field of a 2 × 2 subchannel is simulated using ANSYS FLUENT. Fluid force on a fuel rod is analyzed on the time and frequency domain. Mechanism of the generation of fluid force on a rod is discussed. Abstract: Fluid excitation force is the driving source of grid-to-rod fretting (GTRF) wear, which is an important mechanism of nuclear fuel failure and breakage. In the present work, the fluid excitation force on a nuclear fuel rod was calculated and analyzed by the computational fluid dynamics (CFD) method, including time domain and frequency domain analysis. The cases of different turbulence models, inlet velocity, mixing vanes, and clamping structures were simulated and compared to study the mechanism of the generation of fluid force. The result shows that the SST k-ω model with a resolved near wall region mesh can capture the fluctuation of fluid excitation force, that the necessary condition for the generation of fluid force is enough inlet velocity and mixing vanes or clamping structures equipped, and that the necessary condition for the fluctuation of fluid force is enough inlet velocity and clamping structures.