Session: FSI-02-03 Flow-induced Vibration III

Paper Number: 62128

Start Time: Wednesday, July 14, 2021, 08:00 PM

62128 - Research on Characteristics of Fluid Exciting Force of Reactor Internals 

Flow-induced vibration is an important issue related to the safety and reliability of nuclear reactor,which need to be analyzed and evaluated in the design stage. In order to obtain the input load and key parameters used in the calculation of flow-induced vibration of reactor internals that need to be satisfied the engineering requirements. The typical reactor internals are selected as the research object, and the fluid exciting force characteristics are studied based on the computational fluid dynamics methods. The results show that the fluid exciting force acting on the reactor internalsis a wide-band stochastic process. This characteristic is consistent with the nature of broadband randomness. For upper internal, the largest pressure fluctuation occurs at the guide tubes and support columns located near the outlet. Therefore, it is necessary to be paidmore attention to these guide tubesand support columns in response analysis.As for core barrel, the root mean square value of the pressure fluctuation changes drastically at the inlet and outlet location, meanwhile,the pressure fluctuation value is also considerably large.For lower internal, the lower flow field of reactor internals is relatively disordered,and its pressure fluctuation possesses irregular characteristics. Thus,each component of lower internal need to be considered in analysis and evaluation.

Presenting Author: Zhipeng Feng NPIC

Authors:

Zhipeng Feng NPIC
Liwen Deng Nuclear Power Institute of China
Xuan Huang Nuclear Power Institute of China
Pingchuan Shen Nuclear Power Institute of China
Shuai Liu NPIC
Fengchun Cai Nuclear Power Institute of China