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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Steven A. Wright, Erhard A. Fischer, Peter K. Mast, Gustav Schumacher
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 326-340
Technical Paper | Analyse | doi.org/10.13182/NT85-A33730
Articles are hosted by Taylor and Francis Online.
During an unprotected loss-of-flow accident in a liquid-metal fast breeder reactor, the mode of fuel disruption in sodium-voided channels and the subsequent fuel and clad motion are important issues that determine the further accident sequence. To study these phenomena, a series of in-pile fuel disruption experiments, FD2/4, were performed, and the fuel behavior was recorded by high-speed cinematography. Power transients typical of a heterogeneous (e.g., Clinch River Breeder Reactor) and a homogeneous (e.g., SNR-300, Federal Republic of Germany) core design were employed. In the first case, large-scale liquid swelling was observed, whereas in the second case, disruption by solid-state breakup occurred. Both observations provided direct experimental confirmation of the assumption usually made in the accident analysis, and thus removed still existing modeling uncertainties concerning the disruption behavior.