Flow Induced Vibration Analysis of Thermo-well at Main Pipe of Reactor Coolant Loop

ZANG Fenggang; LIU Wenjin

Volume 26 Issue 4

Aug. 2005

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2005 > 26(4): 360-363

ZANG Fenggang, LIU Wenjin. Flow Induced Vibration Analysis of Thermo-well at Main Pipe of Reactor Coolant Loop[J]. Nuclear Power Engineering, 2005, 26(4): 360-363.

Citation:

ZANG Fenggang, LIU Wenjin. Flow Induced Vibration Analysis of Thermo-well at Main Pipe of Reactor Coolant Loop[J]. Nuclear Power Engineering, 2005, 26(4): 360-363.

ZANG Fenggang, LIU Wenjin. Flow Induced Vibration Analysis of Thermo-well at Main Pipe of Reactor Coolant Loop[J]. Nuclear Power Engineering, 2005, 26(4): 360-363.

Citation:

ZANG Fenggang, LIU Wenjin. Flow Induced Vibration Analysis of Thermo-well at Main Pipe of Reactor Coolant Loop[J]. Nuclear Power Engineering, 2005, 26(4): 360-363.

PDF( 220 KB)

Flow Induced Vibration Analysis of Thermo-well at Main Pipe of Reactor Coolant Loop

National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2004-07-05
Rev Recd Date: 2004-12-28

Available Online: 2025-07-29

Publish Date: 2005-08-15

Abstract

Abstract

There are mainly two excitation mechanisms in the vibration of the thermo-well at the main pipe of reactor coolant loop under cross flow: turbulence and vortex shedding. The natural frequencies of the G1″and G1″ 1/4 thermo-well and the vortex shedding frequencies are calculated, respectively, in this paper. The vortex shedding lock-in is analyzed for two different thermo-wells, and then the flow induced vibration fatigue of the thermo-well is studied using a simplified engineering approach.
- Flow-induced vibration,
- Turbulence excitation,
- Vortex shedding,
- Fatigue