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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.
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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. F. Carew
Nuclear Science and Engineering | Volume 104 | Number 4 | April 1990 | Pages 396-401
Technical Paper | doi.org/10.13182/NSE90-A23737
Articles are hosted by Taylor and Francis Online.
An analytic method for analyzing prompt-critical reactivity transients for a nonlinear energy feedback model is derived. The nonlinear point kinetics equation is replaced by a least-squares equivalent linear equation, and an approximate time-dependent reactivity is determined analytically. Assuming the power burst is infinitely sharp and symmetric about the peak, the transient peak energy, power, and pressure are expressed in terms of the inserted reactivity. The resulting expressions allow the definition of an equivalent step reactivity transient that preserves both the peak energy and power. The method is applied to the case where the feedback nonlinearity is small, and simplified expressions for the transient peak energy and power are determined and shown to approximate the known exact results in the case of a ramp reactivity insertion and a linear energy feedback model.