Study on bidirectional fluid-solid coupling characteristics of reactor coolant pump under steady-state condition

被引:23
|
作者
Wang, Xiuli [1 ]
Lu, Yonggang [1 ]
Zhu, Rongsheng [1 ]
Fu, Qiang [1 ]
Yu, Haoqian [1 ]
Chen, Yiming [1 ]
机构
[1] Jiangsu Univ, Natl Res Ctr Pumps, Zhenjiang 212013, Jiangsu, Peoples R China
关键词
Reactor coolant pump; Bidirectional fluid-solid coupling; Safety demonstration; Steady state condition; Nomenclature;
D O I
10.1016/j.net.2019.05.009
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The AP1000 reactor coolant pump is a vertical shielded-mixed flow pump, is the most important coolant power supply and energy exchange equipment in nuclear reactor primary circuit system, whose steady-state and transient performance affect the safety of the whole nuclear island. Moreover, safety demonstration of reactor coolant pump is the most important step to judge whether it can be practiced, among which software simulation is the first step of theoretical verification. This paper mainly introduces the fluid-solid coupling simulation method applied to reactor coolant pump, studying the feasibility of simulation results based on workbench fluid-solid coupling technology. The study found that: for the unsteady calculations of the pure liquid media, the average head of the reactor coolant pump with bidirectional fluid-solid coupling decreases to a certain extent. And the coupling result is closer to the real experimental value. The large stress and deformation of rotor under different flow conditions are mainly distributed on impeller and idler, and the stress concentration mainly occurs at the junction of front cover plate and blade outlet. Among the factors that affect the dynamic stress change of rotor, the pressure load takes a dominant position. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码:1842 / 1852
页数:11
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