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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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WIPP’s SSCVS: A breath of fresh air
This spring, the Department of Energy’s Office of Environmental Management announced that it had achieved a major milestone by completing commissioning of the Safety Significant Confinement Ventilation System (SSCVS) facility—a new, state-of-the-art, large-scale ventilation system at the Waste Isolation Pilot Plant, the DOE’s geologic repository for defense-related transuranic (TRU) waste in New Mexico.
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.