Experimental investigation of impact-sliding interaction and fretting wear between tubes and anti-vibration bars in steam generators

被引:16
|
作者
Guo, Kai [1 ]
Jiang, Naibin [2 ]
Qi, Huanhuan [2 ]
Feng, Zhipeng [2 ]
Wang, Yang [1 ]
Tan, Wei [1 ]
机构
[1] Tianjin Univ, Sch Chem Engn & Technol, Tianjin 300350, Peoples R China
[2] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610213, Sichuan, Peoples R China
基金
中国国家自然科学基金;
关键词
Tube/ support interaction; Fretting wear; Impact-sliding; Steam generator; HEAT-EXCHANGER TUBES; TURBULENCE RESPONSE; DAMAGE;
D O I
10.1016/j.net.2019.11.014
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 tubes in a heat exchanger, such as a steam generator (SG), are subjected to crossflow, and interaction between tubes and supports can happen, which can cause fretting wear of tubes. Although many experiments and models have been established, some detailed mechanisms are still not sufficiently clear. In this work, more attention is paid to obtain the regulation of impact and sliding in the complex process and many factors, such as excitation forces and clearances. The responses and contact forces were analyzed to obtain clear understanding of the influences of these factors. Room temperature tests in the air were established. The results show that the effect of clearance on the normal work rate is not monotonous and instead has two peaks. The force ratio can influence the normal work rate by changing the distribution of contact angles, which can result in higher sliding in the contact process. Fretting wear tests are conducted, and the wear surfaces are analyzed by a scanning electron microscope (SEM) and energy dispersive X-ray spectrometer ( EDX). The results of this work can serve as a reference for impact-sliding contact analysis between AVBs and tubes in steam generators. (C) 2019 Korean Nuclear Society, Published by Elsevier Korea LLC.
引用
收藏
页码:1304 / 1317
页数:14
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