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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.