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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.