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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
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
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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
W. J. FADER, R. C. HARRISON
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 405-414
Technical Paper | doi.org/10.13182/NSE61-A26042
Articles are hosted by Taylor and Francis Online.
Reactor period-reactivity relations and open-loop transfer functions may be determined directly by numerical integration of “rod-drop” neutron decay data without analysis into delayed neutron period and abundance values. Period-reactivity relations obtained by this method for two critical assemblies with and without beryllium in the core and reflector are compared with corresponding results calculated from the “in-hour” equation. Results of the application of the rod-drop experiment to the determination of the open-loop reactor transfer function are given for the beryllium-moderated assembly.