Published June 2019 | Version v1
Journal article

Experimental Study on Flow-Induced Vibration of Heat Transfer Tube Bundles of ZH-65 Steam Generator

  • 1. Nuclear Power Institute of China, Chengdu (China)

Description

An experimental model of heat transfer tube bundles of ZH-65 steam generator was designed. Then the flow-induced vibration of heat transfer tube bundles of ZH-65 steam generator was studied in air-water two-phase flow loop. The strain and acceleration responses of U-tube were measured under void fraction of 0% ∼ 90% and pitch velocity of 0.5 ∼ 3.43 m/s. The evaluation of tube bundles was conducted from the size of bending radius, in-plane and out-of-plane, bending section and straight section, etc. The results show that the acceleration of bending section increases with the increase of the bending radius. The strain at the root of the bending section is inversely proportional to the bending radius. The frequency of U-tube is inversely proportional to the bending radius. The in-plane acceleration of the bending section is smaller than that of the out-of-plane acceleration. The acceleration of the bending section is greater than that of the straight section. (authors)

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
40
Journal Issue
S1
Journal Page Range
p. 63-66
ISSN
0258-0926

Optional Information

Notes
7 figs., 2 tabs., 6 refs.; http://dx.doi.org/10.13832/j.jnpe.2019.S1.0063