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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Anil K. Prinja, Erin D. Fichtl
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 441-448
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE07-A2675
Articles are hosted by Taylor and Francis Online.
An iterative solution of coupled standard model equations arising in electron transport in binary statistical mixtures is considered. Convergence degradation is observed in certain energy groups and is attributed to chunk sizes appearing optically thin in the higher energy groups. Fourier analysis shows that the spectral radius approaches unity for the zero wave-number error mode as the chunk sizes become vanishingly small. It is shown that the atomic mix model accurately approximates transport under these circumstances and moreover provides a suitable low-order approximation to the iteration error. Fourier analysis and numerical implementation confirm that atomic mix acceleration is unconditionally effective for the application considered here. Our computations also demonstrate the inaccuracy of the atomic mix model for electron dose, especially for materials with strongly contrasting physical properties.