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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
D. J. Kowalski, V. J. Esposito
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 536-539
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32363
Articles are hosted by Taylor and Francis Online.
The classical manner of analyzing the loss-of-coolant accident hydraulic loads imposed on a Westinghouse-type steam generator was to assume a primary side outlet break and to assume that the confining structure was rigid. By considering the vertical divider plate to be flexible, it can be shown that the applied hydraulic forces on the divider plate, tubesheet, and tubes are significantly reduced. The assumption of a flexible divider plate requires the interaction of the fluid and structure simultaneously. The MULTIFLEX computer program and system model have the capability of considering this mutual interaction. Results have been obtained showing the reasons why and how the hydraulic loads on the steam generator internals are attenuated.