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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Ahmed Badruzzaman, James Biffer, Tahmina Badruzzaman, Martin Becker
Nuclear Science and Engineering | Volume 79 | Number 1 | September 1981 | Pages 124-140
Technical Note | doi.org/10.13182/NSE81-A19050
Articles are hosted by Taylor and Francis Online.
The continuous slowing down integral transport theory has been extended to perform criticality iteration with fuel-depletion analysis for evaluating exposure-dependent spectral transitions in fast reactor core-blanket systems. The theory was applied to conventional and heterogeneous configurations, obtaining excellent predictions of the eigenvalue and the spectra. The results indicate the importance of space-dependent analysis involving considerable energy detail. The initial value energy considerations of the theory are the principal advantage in data processing and group collapse procedures requiring such detail. Several simplifying features were observed, further enhancing the advantages of the present method. The transport theory sophistication was attained without significant penalty as the spatial probabilities varied weakly with exposure. Similar insensitivity of the slowing down parameters and resonance self-shielding factors provide substantial savings in computer running time. Nonvariation of these parameters had small effects on fuel cycle characteristics. An analytical solution of the depletion equations was obtained based on the observed weak exposure variation of important microscopic reaction rates. The space-dependent slowing down theory as generalized here is thus shown to be an attractive tool for incorporating the required space-energy detail in a comprehensive fast reactor fuel cycle analysis.