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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.
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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.
Nobuyuki Nonaka, Ikken Sato
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 54-69
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34650
Articles are hosted by Taylor and Francis Online.
An improved method to evaluate key phenomena in the initiating-phase energetics of unprotected lossof-flow (ULOF) whole-core accidents in liquid-metal fast breeder reactors is presented. Three phenomena, namely, axial fuel expansion, fuel failure, and postfailure fuel motion, have been examined through the CABRI-1 in-pile experiments and analyses with special emphasis on the self-limiting mechanisms of the energetics potential. For the experiment analyses, the SAS3D, PAPAS-2S, and SAS4A computer codes are employed selectively to obtain a detailed investigation of the phenomena and to validate physical models. The improved knowledge obtained through the research efforts in CABRI-1 and relevant safety experiments has been implemented in the revised SAS3D code. This evaluation method, which accounts for the self-limiting mechanisms, has been applied to a reactor analysis of an energetic ULOF sequence. The results of the application study confirm the importance and effectiveness of the method.