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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Christmas Light
’Twas the night before Christmas when all through the house
No electrons were flowing through even my mouse.
All devices were plugged by the chimney with care
With the hope that St. Nikola Tesla would share.
W. A. Coffman, F. T. Dunckhorst, L. L. Lynn, J. E. Meyer
Nuclear Technology | Volume 4 | Number 6 | June 1968 | Pages 372-381
Technical Paper and Note | doi.org/10.13182/NT68-A26361
Articles are hosted by Taylor and Francis Online.
A method was developed for predicting excessive clad sheath distortion in a cylindrical waterlogged reactor fuel element subjected to a transient increase in power. The analytical model includes heat transfer, linear elastic stress and deformation, and defect flow equations to yield transient values of internal pressure, clad stress, and clad strain. Details of the model and several comparisons with observed waterlogging incidents are given.