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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.
Bernard W. Shaffer
Nuclear Science and Engineering | Volume 19 | Number 3 | July 1964 | Pages 300-309
Technical Paper | doi.org/10.13182/NSE64-A20963
Articles are hosted by Taylor and Francis Online.
Thermal stress and displacement equations are derived for an internally clad tube for which the ratio of cladding thickness to internal tube radius is small with respect to unity and in which the cladding and the basic tube have different material properties. When the difference between the cladding temperature and the average temperature of the basic tube is large enough, plastic flow is found to occur in the cladding. The corresponding solution is found by making use of the Tresca yield condition and its associated flow law. The solution is examined to guide the designer in the selection of those cladding material properties that would delay the initiation of plastic flow.