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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
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.