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Division Spotlight
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
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.
Lewi Tonks
Nuclear Science and Engineering | Volume 6 | Number 3 | September 1959 | Pages 202-213
Technical Paper | doi.org/10.13182/NSE59-A25660
Articles are hosted by Taylor and Francis Online.
A quantitative but simple theory of the control effect of a uniformly distributed set of thermal poison elements in a hydrogen-moderated bare reactor core has been developed. Starting with plane parallel poison sheets, a zero-flux boundary condition, in a slab core and applying Fourier analysis, it has been possible to generalize to any boundary condition, to orthogonally intersecting sets of poison sheets in an infinite rectangular core, to control crosses, and cylindrical rods in regular array, to finite rectangular cores, and to finite cylindrical cores. Each element of the control array is associated with a cross-sectional area Ac within the core and within this area is an easily determined effective “absorption area” C. To a rather good accuracy the critical k of the controlled core is greater than the k of the uncontrolled core by the ratio Ac/(Ac − C). In this the theoretically based conclusion substantiates the intuitionally based and empirically confirmed methods worked out by Greebler (1), and by Pearlstein, Ruane, and Storm (2), and furnishes correction terms.