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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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
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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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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.
W. G. Wolfer, J. P. Foster, F. A. Garner
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 55-63
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31175
Articles are hosted by Taylor and Francis Online.
The dimensional changes occurring in metals under fast-neutron irradiation and external loads have been analyzed in terms of dislocation climb and glide, dislocation loop formation, and diffusional growth of voids. The strains produced by these mechanisms were derived. Although these strains can be divided into swelling strains and creep strains, the irradiation creep strains may be related to the swelling strains. Strains produced by the climb of dislocations contribute mainly to swelling, but not to irradiation creep. However, if the glide of dislocations is controlled by the climb motion, the resulting irradiation creep rate is directly proportional to the swelling rate. Preferential loop nucleation induced by external stresses gives rise to an irradiation creep correlation which is in agreement with the experimental data.