Published February 1996 | Version v1
Journal article Metadata-only

Analysis of the fluid-elastic vibration of a U-bend tube bundle induced by cross-flow in PWR steam generators

Creators

  • 1. California Univ., Berkeley (United States). Dept. of Mechanical Engineering

Description

Cross-flow-induced vibration in a U-bend tube bundle causes wear and fretting fatigue in PWR steam generators and has received considerable attention in the past decade. However, all the previous studies were based on the equation of motion for straight tubes. In this paper the equations of motion for U-bend tubes subjected to cross-flow are derived. Analytical solutions for responses to fluid dynamic forces are then obtained. (orig.)

Additional details

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
160
Journal Issue
1-2
Journal Page Range
p. 111-128.
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
27041761
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Descriptors DEI
ANALYTICAL SOLUTION; CROSSFLOW SYSTEMS; DAMPING; EQUATIONS OF MOTION; FATIGUE; FLUID FLOW; FLUID MECHANICS; MECHANICAL VIBRATIONS; PWR TYPE REACTORS; STEAM GENERATORS; TUBES; VELOCITY; WEAR
Descriptors DEC
BOILERS; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; MECHANICAL PROPERTIES; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS