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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
D. Shalitin, J. J. Wagschal, Y. Yeivin
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 364-370
Technical Paper | doi.org/10.13182/NSE77-A26978
Articles are hosted by Taylor and Francis Online.
We study the dependence of the number, N, of iterations necessary for the convergence of the one-group inhomogeneous transport equation, on the normalization, α, of an initial flux proportional to the external source distribution. It is proven that if the initial flux has the correct ψ0 component, where ψ0 is the fundamental eigenfunction of the corresponding homogeneous equation, the number of iterations is significantly reduced. This minimum is already indicated by a heuristic neutron-balance argument, whereas the complete function N(α) is derived by means of a rigorous analysis. Results of this analysis are illustrated by some numerical examples.
