Published 2006 | Version v1
Miscellaneous

Fluid-Elastic Instability of U-Tube Bundle in Two-Phase Cross-Flow

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

The U-bend region of nuclear steam generator tubes which undergoes high flow two-phase flow condition is highly susceptible to flow-induced vibration. In various flow-induced vibration mechanisms, it is generally known that fluid-elastic instability is the main cause of fretting wear of U-tubes. Since 1980s many experiments have been performed to investigate the fluid-elastic instability in two-phase cross-flow. Most of the previous experiments were performed with cantilever tube bundles. However, the vibration mode shapes of U-bend tube are quite different from those of cantilever tube, and moreover vibration of U-bend is excited by non-uniform velocity field. The purpose of the present study is to experimentally investigate the fluid-elastic instability characteristics using U-bend tube bundles under air-water two-phase cross-flow

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2006 autumn meeting of the KNS
Dates
2-3 Nov 2006
Place
Kyongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38049340
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
INSTABILITY; STEAM GENERATORS; TUBES; TWO-PHASE FLOW; VELOCITY; WEAR
Descriptors DEC
BOILERS; FLUID FLOW; VAPOR GENERATORS

Optional Information

Notes
7 refs, 4 figs