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
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