Skip to Main Content
Skip Nav Destination
Flow-Induced Vibration Handbook for Nuclear and Process Equipment
By
Michel J. Pettigrew
Michel J. Pettigrew
Search for other works by this author on:
Colette E. Taylor
Colette E. Taylor
Search for other works by this author on:
Nigel J. Fischer
Nigel J. Fischer
Search for other works by this author on:
ISBN:
9781119810964
No. of Pages:
494
Publisher:
ASME-Wiley
Publication date:
2022

Excessive flow-induced vibration must be avoided in process and nuclear system components. That is the purpose of this handbook. The term “process components” is used generally here to describe nuclear reactor internals, nuclear fuels, piping systems, and all shell-and-tube heat exchangers, including nuclear steam generators, power plant condensers, boilers, coolers, etc. Higher heat-transfer performance often requires higher flow velocities and more structural supports. On the other hand, additional supports may increase pressure drop and costs. The combination of high flow velocities and inadequate structural support may lead to excessive tube vibration. This vibration can cause failures by fatigue or fretting wear. Failures are very undesirable in terms of repair costs and lost production, particularly for high-capital-cost plants such as nuclear power stations, petroleum refineries and oil exploitation platforms. To prevent these problems at the design stage, a thorough flow-induced vibration analysis is recommended. Such analysis requires good understanding of the dynamic parameters and vibration excitation mechanisms that govern flow-induced vibration.

This content is only available via PDF.
You do not currently have access to this chapter.
Close Modal

or Create an Account

Close Modal
Close Modal