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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.
Dimitris Valougeorgis
Nuclear Science and Engineering | Volume 100 | Number 2 | October 1988 | Pages 142-148
Technical Paper | doi.org/10.13182/NSE88-A29022
Articles are hosted by Taylor and Francis Online.
A study on the development of acceleration equations for boundary cells and the associated boundary conditions for the diffusion synthetic acceleration method of neutron transport problems in x-y geometry is described. Alcouffe’s algebraic manipulation of the P, equations resulting in a single diffusion equation is modified to obtain explicit acceleration equations for the boundary cells. To accomplish this, the discretization in space is performed according to the ordinary box-centered method. The resulting synthetic computation scheme is linear in its differenced form. The boundary cell difference equations are derived in a manner that exactly parallels the discretization of the diffusion equation for interior mesh cells and that of the transport equation. The importance of these equations in improving overall efficiency without sacrificing stability is discussed, as is the optimum choice of the boundary conditions associated with these equations.