Conference
Probabilistic Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations
Abstract
Flow-Induced Vibrations (FIV) continue to affect the operations of nuclear power plant components such as heat exchanger tube bundles. The negative effect of FIV is in the form of tube fatigue, cracking and fretting wear at the supports. Fretting wear at the supports is the result of tube/support impact and friction. Fluidelastic and turbulence forces are the two main excitation mechanisms that feed energy into the system causing these violent …
Authors
Hassan M; Riznic J
Pagination
pp. v004t04a052-v004t04a052
Publisher
ASME International
Publication Date
July 14, 2013
DOI
10.1115/pvp2013-97751
Name of conference
Volume 4: Fluid-Structure Interaction