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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.
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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
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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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.
D. E. Wood, K. R. Birney, E. Z. Block
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 116-125
Technical Paper | doi.org/10.13182/NSE64-A18148
Articles are hosted by Taylor and Francis Online.
Lattice parameters have been measured for natural uranium concentric tubes and solid fuel elements of 2.5 inches outside diameter in the Physical Constants Testing Reactor (PCTR). The primary quantities measured are the mass of copper required to reduce k∞ to one, copper activations throughout the lattice, and cadmium ratios for U238 capture, U235 and U238 fission, copper, gold, and lutetium. The results derived from these measurements are k∞, ε, and the effective neutron temperature for the concentric tube in a 10.5-inch graphite lattice with both water and air in the coolant channels; k∞ and for the concentric tube in an 8.375-inch lattice, water cooled only; and k∞, , and for the solid fuel in a 10.5-inch graphite lattice, water and air cooled. The effective fraction of the internal surfaces for resonance capture was determined to be 0.50. The average value of η for natural uranium in these lattices was found to be 1.30.