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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.
M. Makai, E. Temesvári
Nuclear Science and Engineering | Volume 112 | Number 1 | September 1992 | Pages 66-77
Technical Paper | doi.org/10.13182/NSE92-A23952
Articles are hosted by Taylor and Francis Online.
Surveillance of a nuclear reactor core involves determination of the power or temperature distribution of the assemblies. Derived from other assemblies’ measured temperatures, the temperature of a nonmeasured assembly is calculated for every assembly with the help of the principal components method (PCM). The basis of this method is presented, and the measured values are interpolated for various geometrical coverings of the WWER-440 core. A number of procedures have been elaborated and investigated, the most successful of which are introduced. Each method offers self-consistent means for determining the numerical errors of the interpolated values. The procedure based on the PCM can be utilized for any reactor type and is fairly accurate.