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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
W. L. Filippone, M. S. Smith,S. Woolf, J. C. Garth
Nuclear Science and Engineering | Volume 95 | Number 1 | January 1987 | Pages 22-46
Technical Paper | doi.org/10.13182/NSE87-A20430
Articles are hosted by Taylor and Francis Online.
An electron transport solver has been developed based on a streaming ray (SR) solution to the Spencer-Lewis equation. Several special numerical techniques were used to make the algorithm fast and accurate. These include,an efficient routine for simulating energy loss straggling,use of extended-transport-corrected and Fokker-Planck equivalent cross sections, which speed convergence and reduce both angular and spatial differencing errors,a discrete transport correction, which further speeds convergence and further reduces spatial differencing errors,the method of numerical shoves and countershoves, which attempts to estimate and correct the remaining spatial differencing errors.The extended transport correction and the Fokker-Planck equivalent cross sections were originally developed for SN computations. The remaining techniques are new. The use of all these techniques together with the SR method has led to a complicated but highly efficient electron transport algorithm. Its efficiency is especially evident in energy spectrum calculations for which other fast algorithms such as the SN method often yield poor results. Several sample calculations involving electron transport in aluminum slabs are presented.