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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.
B. Mukherjee, M. H. El Haddad, M. L. Vanderglas, D. V. Leemans
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 505-512
Technical Paper | Materials | doi.org/10.13182/NT55-505
Articles are hosted by Taylor and Francis Online.
A large number of Monel 400 steam generator tubes may be subjected to low cycle fatigue because of the particular location of the thermal plate. A low cycle fatigue analysis method, simulating the deformation response of structural component elements due to irregular load history, was applied to predict stress-strain behavior and then fatigue life of the Monel 400 steam generator tubing. The experiments revealed that under worst loading conditions (maximum displacement, with a tube locked in the thermal plate), the specimens failed due to mechanical fatigue in a period corresponding to three to five times the expected service life of a steam generator. Standard internal coil eddy current inspection techniques were not successful in detecting the cracks that had initiated in the Monel tubes in the region of the modeled tubesheet. This made the experimental and analytical fatigue life prediction work even more valuable.