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
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 54087844
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCELERATION; AIR; BENDING; DESIGN; EVALUATION; HEAT TRANSFER; PITCHES; STEAM GENERATORS; STRAINS; TUBES; TWO-PHASE FLOW; VELOCITY; VOID FRACTION; WATER
- Descriptors DEC
- BOILERS; DEFORMATION; ENERGY TRANSFER; FLUID FLOW; FLUIDS; GASES; HYDROGEN COMPOUNDS; ORGANIC COMPOUNDS; OTHER ORGANIC COMPOUNDS; OXYGEN COMPOUNDS; VAPOR GENERATORS
Optional Information
- Notes
- 7 figs., 2 tabs., 6 refs.; http://dx.doi.org/10.13832/j.jnpe.2019.S1.0063