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Flow-Induced Vibration Handbook for Nuclear and Process Equipment
ISBN:
9781119810964
No. of Pages:
494
Publisher:
ASME-Wiley
Publication date:
2022
eBook Chapter
12. Assessment of Fretting-Wear Damage in Nuclear and Process Equipment
Page Count:
23
-
Published:2022
Citation
Pettigrew, MJ, Yetisir, M, Fisher, NJ, Smith, BAW, & Janzen, VP. "Assessment of Fretting-Wear Damage in Nuclear and Process Equipment." Flow-Induced Vibration Handbook for Nuclear and Process Equipment. Ed. Pettigrew, MJ, Taylor, CE, & Fischer, NJ. ASME-Wiley, 2022.
Download citation file:
Generally, the problems caused by excessive vibration are fatigue cracks and fretting-wear damage. This chapter treats the problem of fretting-wear damage between a vibrating structure and its supports. Typical components of concern are piping systems and pipe supports, multi-span heat exchanger tubes and tube supports, and nuclear fuel bundles and fuel channels. Fatigue problems, on the other hand, can be analysed using classical methods that are readily available in the literature.
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