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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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.
J. L. Kaae, D. W. Stevens, C. S. Luby
Nuclear Technology | Volume 10 | Number 1 | January 1971 | Pages 44-53
Technical Paper and Note | Fuel | doi.org/10.13182/NT71-A30946
Articles are hosted by Taylor and Francis Online.
Three mathematical models for use in calculating the stresses and displacements in two-, three- , and four-layer pyrolytic carbon and silicon carbide coatings on microspheres of (Th,U)C2 or (Th,U)O2 during reactor service have been previously described. In these models it is assumed that pyrolytic carbon changes dimensions anisotropically and will creep under fast-neutron irradiation, silicon carbide is dimensionally stable and undergoes no creep, and an internal pressure is generated due to gaseous fission products. Comparison of the results predicted by these mathematical models with irradiation tests shows agreement with diametral changes of two-layer fuel particles. Coating failure, presumably due to stress, occurred only in those samples with high calculated stresses.