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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.
Richard Simms, George S. Stanford, Charles L. Fink, James P. Regis
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 594-600
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A32804
Articles are hosted by Taylor and Francis Online.
The reactivity feedback from fuel relocation is a central issue in the analysis of a loss-of-flow (LOF) accident in a liquid-metal fast breeder reactor (LMFBR). Fuel relocation has been the subject of a number of LOF simulations in the Transient Reactor Test Facility (TREAT). In this study, the results of these tests are analyzed using, as the principal figure of merit, the changes in equivalent fuel worth associated with the fuel motion. The equivalent fuel worth was obtained from the measured axial fuel distributions by weighting the data with a typical LMFBR fuel worth function. At nominal power, the initial fuel relocation resulted in increases in equivalent fuel worth. Above nominal power, the fuel motion was mildly dispersive, but the dispersive driving forces could not unequivocally be identified.