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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.
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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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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.
W. L. Barr, R. H. Bulmer, L. J. Perkins, S. A. Cohen, K. A. Werley
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1416-1420
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST92-A29920
Articles are hosted by Taylor and Francis Online.
We have just completed a comparison of predictions for the scrape-off layer (SOL) plasma, from a physics model [1] with the more accurate ones from a two-dimensional fluid code, the B2 code [2]. The results presented here show rather good agreement on values of plasma temperature in the SOL and of divertor heat load, for a rather wide range of Tokamak sizes and parameters. We are therefore confident that this model will provide a suitable divertor module for both the new ITER systems code, SUPERCODE [3], and other applications requiring fast but accurate modelling of edge plasma parameters, at least within the range of the present benchmarks.