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Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
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.