Dynamic Characteristics Analysis of Cylinders Bundle Coupling System Under Axial Flow

被引：1

作者：

Shu, Ya-feng ^{[1
,2
]}

Wu, Jian-jun ^{[1
]}

Yang, Yong-wei ^{[2
]}

Liu, Wei-ming ^{[2
]}

Tao, Kei-wei ^{[2
]}

机构：

[1] Lanzhou Univ, Coll Civil Engn & Mech, Key Lab Mech Disaster & Environm Western China, Minist Educ, Lanzhou 730000, Peoples R China

[2] Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China

来源：

MECHANIKA | 2021年 / 27卷 / 03期

关键词：

CB coupling dynamic model; stability analysis; pulsating flow; amplitude frequency response; movement trajectory; INDUCED VIBRATION; FUEL-RODS; STABILITY; CLUSTER;

D O I：

10.5755/j02.mech.25101

中图分类号：

O3 [力学];

学科分类号：

08 ; 0801 ;

摘要：

Nuclear reactor fuel assemblies are mainly composed of cylinders bundle (CB), calculating the dynamics characteristics of CB under axial flow can lay a foundation for predicting fretting wear and vibration fatigue. In the paper, the CB coupling dynamic model of forced vibration under pulsating flow is established. And the stability analysis and natural frequency calculation of the CB system under steady flow are compared with the existing results to verify the model. Finally, the Runge-Kutta method is applied to solve the forced vibration equation of the CB under pulsating flow. The influence of the pulsating parameters mu, omega(0) on the amplitude-frequency characteristics and the motion trajectory of the midspan cross section of the CB under forced vibration are analyzed and discussed. The results show that the pulsating parameters have an important influence on the vibration of the CB system.

引用

页码：209 / 219

页数：11

共 26 条

[1]

CHEN SS, 1972, NUCL ENG DES, V18, P253, DOI 10.1016/0029-5493(72)90144-6

[2] VIBRATION OF NUCLEAR FUEL BUNDLES [J].

CHEN, SS .

NUCLEAR ENGINEERING AND DESIGN, 1975, 35 (03) :399-422

[3]

Currie I.G., 2012, FUNDAMENTAL MECH FLU, V4th ed.

[4] Operational modal analysis of flow-induced vibration of nuclear fuel rods in a turbulent axial flow [J].

De Pauw, B. ;

Weijtjens, W. ;

Vanlanduit, S. ;

Van Tichelen, K. ;

Berghmans, F. .

NUCLEAR ENGINEERING AND DESIGN, 2015, 284 :19-26

[5]

De Pauw B., 2015, Ph. D. thesis

[6] Predicting modal characteristics of a cluster of cylinders in axial flow: From potential flow solutions to coupled CFD-CSM calculations [J].

De Ridder, Jeroen ;

Degroote, Joris ;

Van Tichelen, Katrien ;

Vierendeels, Jan .

JOURNAL OF FLUIDS AND STRUCTURES, 2017, 74 :90-110

[7] Analysis of flow induced vibrations and static deformations of fuel rods considering the effects of wire spacers and working fluids [J].

De Santis, Dante ;

Shams, Afaque .

JOURNAL OF FLUIDS AND STRUCTURES, 2019, 84 :440-465

[8] Numerical modeling of flow induced vibration of nuclear fuel rods [J].

De Santis, Dante ;

Shams, Afaque .

NUCLEAR ENGINEERING AND DESIGN, 2017, 320 :44-56

[9] Parametric resonances of supported pipes conveying pulsating fluid [J].

Jin, JD ;

Song, ZY .

JOURNAL OF FLUIDS AND STRUCTURES, 2005, 20 (06) :763-783

[10] Vibration analysis of PWR fuel rod [J].

Kim, HK ;

Kim, MS .

JOURNAL OF SOUND AND VIBRATION, 2005, 282 (1-2) :553-572

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