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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
H. J. Connors
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 311-331
Technical Paper | Materials | doi.org/10.13182/NT55-311
Articles are hosted by Taylor and Francis Online.
Potential tube fretting wear and fretting fatigue caused by flow-induced vibration are addressed in the design of nuclear steam generators. Flow-induced interactions of the tubes with the tube supports can cause localized tube wear and fretting fatigue effects if the system is not properly designed. The major flow-induced vibration mechanisms that can cause vibration of steam generator tubes are fluidelastic excitation, turbulence, and vortex shedding. Fluid-elastic excitation, rather than vortex shedding, is believed to have been the cause of large-amplitude vibration and rapid wear of heat exchanger tubes in the past. Fluidelastic vibration initiates when the flow velocity exceeds a critical value. For subcritical flow velocities, turbulence is the main excitation mechanism to consider in predicting the long-term wear of steam generator tubes. The various types of wear-producing forces and motions that can be generated between tubes and supports by flow-induced vibration have been identified, and some general procedures have been developed for predicting tube wear.