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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.
Meimei Li, James F. Stubbins
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 186-190
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST03-A331
Articles are hosted by Taylor and Francis Online.
The influence of radiation damage on the fatigue performance of two selected copper alloys, a dispersion-strengthened CuAl-25 alloy and a precipitation-hardened CuCrZr alloy, was analyzed. The fatigue lives of the two alloys were predicted using their tensile properties before and after irradiation by the Universal Slopes method. The predicted lives are compared with experimental results, and the feasibility of using tensile properties to predict fatigue lives following irradiation is examined. The fatigue performance of these two copper alloys was degraded due to radiation exposure, but the radiation effect on the fatigue performance was not as severe as on the tensile properties. The life prediction agrees reasonably well with the measured fatigue response.
