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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
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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.
M. Caro, J. Ligou
Nuclear Science and Engineering | Volume 83 | Number 2 | February 1983 | Pages 242-252
Technical Paper | doi.org/10.13182/NSE83-A18217
Articles are hosted by Taylor and Francis Online.
Handling the highly anisotropic scattering of fast neutrons with conventional methods usually means that high-order Legendre expansions can be necessary to obtain correct angular fluxes. This drawback in standard transport calculations is avoided by applying the Boltzmann-Fokker-Planck (BFP) method, already used in transport of charged particles, to neutrons. Two methods are described to obtain the relevant input data for the one-dimensional BFP-1 code, one using basic differential scattering cross sections and the other using existing standard multigroup libraries. Numerical results for both methods are produced, revealing BFP as a powerful method when solving transport problems dealing with very fast neutrons. It is found that high accuracy, even for extreme cases of anisotropy, is achieved without increase of the computational effort.