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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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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.
Wm. A. Thomas, E. E. Lewis
Nuclear Science and Engineering | Volume 84 | Number 1 | May 1983 | Pages 67-71
Technical Note | doi.org/10.13182/NSE83-A17459
Articles are hosted by Taylor and Francis Online.
Two iterative algorithms are formulated for the solution of the within-group neutron diffusion equation in three dimensions. The algorithms are highly vectorizable, operating, respectively, on vectors with lengths of order N3/2 and of N2/2, where N is the number of mesh points in each of the three directions. The methods are well suited for present day pipeline computers. On a Cyber-205, they yield floating point operation rates that are higher by a factor of 20 to 30 than those achieved with scalar operations of the same algorithms. Convergence rates, as well as acceleration by two-cyclic overrelaxation, are investigated. For fixed source test problems with 30 X 30 X 30 grids, solutions are obtained in ∼1 s.
