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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
Gregory D. Spriggs
Nuclear Science and Engineering | Volume 114 | Number 4 | August 1993 | Pages 342-351
Technical Paper | doi.org/10.13182/NSE92-78
Articles are hosted by Taylor and Francis Online.
An-in-pile experimental technique to measure the decay constants and the relative abundances of the delayed neutron groups applicable for a given reactor system is presented. The method is based on a least-squares-fitting technique that simultaneously fits a series of transients produced by small reactivity perturbations to a reactor operating initially at delayed critical. The function that is least-squares fit is the analytic solution (written in terms of an arbitrary number of delayed neutron groups) as obtained by the point reactor model for the reactor response following a step change in reactivity. The application of the method does not require any knowledge of the size of the reactivity perturbations, and the method is independent of the detector efficiency. The results are based solely on the measurable quantities of relative power, time, and one measurable root of the Inhour equation.