ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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May 2025
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.
John Greenstadt
Nuclear Science and Engineering | Volume 82 | Number 1 | September 1982 | Pages 78-95
Technical Paper | doi.org/10.13182/NSE82-A19030
Articles are hosted by Taylor and Francis Online.
The application of the cell discretization (CD) method to a class of nuclear reactor problems is described. The CD method is based on partitioning the domain in which the diffusion equations are to be solved into a set of subdomains, or “cells.” This approach, which resembles that used in the finite element method, nevertheless differs from it in certain important respects, some of which are mentioned in the course of describing CD. A FORTRAN program has been written that implements many of the features of the CD method, but is restricted to rectangular geometry. Several representative problems from the literature are solved numerically with CD, and the results are compared with the published ones. The central processor unit times are given for solution of these problems on the IBM 370/158 under VM, a time-sharing system. All results, including keff, peak-to-average-power ratios, integrated fluxes, etc. are listed in tables in such a way as to make comparison convenient. Flux plots are also shown for those cases where they were given in the literature.
