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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.
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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.
J. D. Teachman, R. J. Onega
Nuclear Science and Engineering | Volume 83 | Number 1 | January 1983 | Pages 149-161
Technical Paper | doi.org/10.13182/NSE83-A17996
Articles are hosted by Taylor and Francis Online.
A nonlinear model is developed for the xenon-induced flux oscillation problem that occurs in nuclear power plants. The model is based on Galerkin's method of weighted residuals applied to multigroup diffusion theory. A similar linear model is developed by the same methods in order to consider the effects of the nonlinearities of the system. The effects of multi- and single-energy group considerations are also examined. The one- and three-energy group models give substantial differences in results for a 0.25% perturbation in the absorption cross section in various regions of the core. The effect of the number of profiles describing the flux distribution has an effect on the accuracy of the simulation. The minimum number of profiles is one higher than the number of regions into which the reactor is divided for a one-dimensional calculation. The use of additional profiles causes a small increase in the accuracy of the results at the expense of a dramatic increase in computational time.