ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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.
Paul Naefe, Erich Zimmer
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 163-171
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Chemical Processing | doi.org/10.13182/NT79-A32147
Articles are hosted by Taylor and Francis Online.
A process has been developed for the production of dense fissile fuel kernels for the high-temperature reactor. A method is used whereby a concentrated uranyl nitrate solution with urea and ammonium nitrate as additives is dispersed horizontally into droplets that are hardened by external gelation. The process is very simple and consists of only a few steps, since no organic thickener is necessary and only aqueous solutions are used. The equipment, which has been developed for the special needs of the refabrication of 233U, has a throughput of ∼0.7 kgU/h.