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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.
S. Langenbuch, W. Maurer, W. Werner
Nuclear Science and Engineering | Volume 64 | Number 2 | October 1977 | Pages 508-516
Technical Paper | doi.org/10.13182/NSE77-A27386
Articles are hosted by Taylor and Francis Online.
A systematic study of the accuracy and efficiency of a class of asymmetric weighted residual methods, as applied to neutron diffusion equations, is presented. Polynomials up to the sixth order are considered, with and without mixed spatial derivative terms. It turns out that the sixth-order polynomial with mixed derivative terms is most efficient: yet, for normal reactor conditions, sufficiently accurate results can already be obtained with a third-order polynomial without mixed-derivative terms.