Analysis on Fluid-Structure Interaction Dynamic Characteristics of Steam Generator Heat Exchanger Tubes

2011 ◽  
Vol 382 ◽  
pp. 52-55
Author(s):  
Li Na Zhang ◽  
Su Zhen Wang
Keyword(s):  
Steam Generator ◽  
Dynamic Characteristics ◽  
Nuclear Power ◽  
Power Plants ◽  
Fluid Structure Interaction ◽  
Finite Element Program ◽  
Fluid Structure ◽  
Structure Interaction ◽  
Interaction Dynamic ◽  
Steam Generator Tubes

The fluid-structure interaction (FSI) dynamic characteristics of steam generator tubes counting for much with safety of an operating nuclear power plants are investigated by analytical methods based on dynamics mechanics and FSI theories. By using the parametric design language APDL of finite element program ANSYS, intelligently dividing model, setting up material and geometric parameters, the models of tubes with internal and external fluid, the different factors influencing on fluid-structure interaction dynamic characteristics of steam generator tubes are investigated by numerical method.

Research on Fluid-Structure Interaction Dynamic Characteristics of Steam Generator Heat Exchanger Tubes

2012 ◽  
Vol 482-484 ◽  
pp. 183-187
Author(s):  
Li Na Zhang ◽  
Hui Zhao ◽  
Min Shan Liu
Keyword(s):  
Heat Transfer ◽  
Heat Exchanger ◽  
Steam Generator ◽  
Dynamic Characteristics ◽  
Fluid Structure Interaction ◽  
Heat Exchanger Tube ◽  
Fluid Structure ◽  
Structure Interaction ◽  
Steam Generator Tubes ◽  
Exchanger Tube

For heat exchanger tube of steam generator, the relation between heat exchanger tube and fluid is typical fluid-structure interaction problem. Flow induced vibration has been found so far to be responsible for fatigue damage and failure of steam generator tubes, which will result in large economic loss and radioactive pollution. So the steam generator tubes are the weakest link in the primary coolant loop. Based on the synthesis of all sorts of factors influencing the dynamic characteristics of steam generator heat transfer tubes, establishing the heat transfer tube model, research on the weakening effect of fluid hole on fluid, the natural frequencies of the heat transfer tubes are analyzed under different fluid holes and fluid hole distance by numerical simulation.

Tackling FSI Simulation for FIV Problems in Tube Bundle Systems With POD Approach

2011 ◽  
Author(s):  
Marie Pomarede ◽  
Aziz Hamdouni ◽  
Erwan Liberge ◽  
Elisabeth Longatte ◽  
Jean-Franc¸ois Sigrist
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Tube Bundle ◽  
Fluid Structure Interaction ◽  
Flowing Fluid ◽  
Fluid Structure ◽  
Reduced Order ◽  
Structure Interaction ◽  
Flow Past ◽  
Steam Boilers

Tube bundles in steam boilers of nuclear power plants and nuclear on-board stokehold are known to be exposed to high levels of vibrations under flowing fluid. This coupled fluid-structure problem is still a challenge for engineers, first because of the difficulty to fully understand it, second because of the complexity for setting it up numerically. Although numerical techniques could help the understanding of such a mechanism, a complete simulation of a fluid past a whole elastically mounted tube bundle is currently out of reach for engineering purposes. To get round this problem, the use of a reduced-order model has been proposed with the introduction of the widely used Proper Orthogonal Decomposition (POD) method for a flow past a fixed structure [M. Pomare`de, E. Liberge, A. Hamdouni, E.Longatte, & J.F. Sigrist - Simulation of a fluid flow using a reduced-order modelling by POD approach applied to academic cases; PVP2010, July 18–22, Seattle]. Interesting results have been obtained for the reconstruction of the flow. Here a first step is to propose to consider the case of a flow past a fixed tube bundle configuration in order to check the good reconstruction of the flow. Then, an original approach proposed by Liberge (E. Liberge; POD-Galerking Reduction Models for Fluid-Structure Interaction Problems, PhD Thesis, Universite´ de La Rochelle, 2008) is applied to take into account the fluid-structure interaction characteristic; the so-called “multiphase” approach. This technique allows applying the POD method to a configuration of a flow past an elastically mounted structure. First results on a single circular cylinder and on a tube bundle configuration are encouraging and let us hope that parametric studies or prediction calculations could be set up with such an approach in a future work.

An Overview of Numerical Method for Fluid-Structure Interaction

2014 ◽  
Author(s):  
J.-H. Jeong ◽  
M. Kim ◽  
P. Hughes
Keyword(s):  
Numerical Simulation ◽  
Numerical Methods ◽  
Nuclear Power ◽  
Power Plants ◽  
Fluid Structure Interaction ◽  
Phase Flow ◽  
Two Phase ◽  
Fluid Structure ◽  
Structure Interaction ◽  
Deformable Structure

Fluid-structure interaction (FSI) is the interaction of some movable or deformable structure with an internal or surrounding fluid flow. Therefore, fluid-structure interaction problems are too complex to solve analytically and so they have to be analysed by means of experiments or numerical simulation. This paper provides an overview of numerical methods for fluid-structure interaction evaluation in an draft IAEA technical guideline: large eddy simulation (LES), direct numerical simulation (DNS), Lattice-Boltzmann method (LBM), finite element method (FEM) and computational fluid dynamics (CFD) method. In addition to providing general applications of numerical methods for fluid-structure interaction evaluation, the paper also describes some cases applied for problems associated with single-phase flow and two-phase flow in nuclear power plants.

Pipe Rupture Analysis Considering Fluid-Structure Interaction

2011 ◽  
Author(s):  
Yukari Hamamoto ◽  
Makoto Toyoda
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Thrust Force ◽  
Fluid Structure Interaction ◽  
Low Carbon ◽  
Analysis Model ◽  
Fluid Structure ◽  
Structure Interaction ◽  
Fluid Analysis ◽  
Autogenous Control

Global warming is caused by the emission of greenhouse gases, like CO2. Nuclear energy is one of the main sources of low-carbon energy. In the events of serious accidents, a nuclear power plant may emit radioactivity that is harmful to human health. Nuclear power should be used after enough evidence of its safety is provided. Measures for safety of nuclear power plants, such as autogenous control and LBB, have been developed. Moreover, there is requirement with respect to the design, safety, equipments components and systems of nuclear plant. For example, it is necessary to place components that restrain pipe whip behavior, and to design peripheral equipments that may be affected by high-pressured fluid in pipe rupture accidents [1], [2]. In the case of pipe rupture that occurs to structures such as nuclear plants and steam generators, a pipe deforms releasing its inner high-pressured fluid. In previous studies, the pipe whip behavior analyses have been performed by using blowdown thrust force that is estimated by fluid analysis. In this study, we simulate pipe whip behavior and reduction of blowdown thrust force by releasing inner fluid to the atmosphere. The analysis model is an elbow pipe and high-pressure fluid running inside. We considered fluid-structure interaction effect in the analysis because ovalization of the cross-section of the elbow part as well as a change of the elbow torus radius affects fluid flow blowing out from the ruptured part of the pipe.

Simulation of the fluid–structure-interaction of steam generator tubes and bluff bodies

2008 ◽  
Vol 238 (8) ◽  
pp. 2048-2054 ◽  
Author(s):  
Karl Kuehlert ◽  
Stephen Webb ◽  
David Schowalter ◽  
William Holmes ◽  
Amarvir Chilka ◽  
...  
Keyword(s):  
Steam Generator ◽  
Fluid Structure Interaction ◽  
Bluff Bodies ◽  
Fluid Structure ◽  
Structure Interaction ◽  
Steam Generator Tubes

The Geometry of Steam Generator Tube and Its Relevance to the Occurrence of Stress Corrosion Cracking in Operating Nuclear Power Plants

2010 ◽  
Author(s):  
Deok Hyun Lee ◽  
Do Haeng Hur ◽  
Myung Sik Choi ◽  
Kyung Mo Kim ◽  
Jung Ho Han ◽  
...  
Keyword(s):  
Stress Corrosion ◽  
Steam Generator ◽  
Stress Corrosion Cracking ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Corrosion Cracking ◽  
Location Type ◽  
Steam Generator Tubes ◽  
Non Destructive

Occurrences of a stress corrosion cracking in the steam generator tubes of operating nuclear power plants are closely related to the residual stress existing in the local region of a geometric change, that is, expansion transition, u-bend, ding, dent, bulge, etc. Therefore, information on the location, type and quantitative size of a geometric anomaly existing in a tube is a prerequisite to the activity of a non destructive inspection for an alert detection of an earlier crack and the prediction of a further crack evolution [1].

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