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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Molten salt research is focus of ANS local section presentation
The American Nuclear Society’s Chicago–Great Lakes Local Section hosted a presentation on February 27 on developments at the molten salt research reactor at Abilene Christian University’s Nuclear Energy Experimental Testing (NEXT) Lab.
A recording of the presentation is available on the ANS website.
R. H. Chapman, I. Spiewak, M. L. Tobias, D. R. Vondy
Nuclear Science and Engineering | Volume 15 | Number 4 | April 1963 | Pages 347-353
Technical Paper | doi.org/10.13182/NSE63-A26450
Articles are hosted by Taylor and Francis Online.
The design of a small experimental breeder reactor which it is believed will not be subject to the chemical difficulties characteristic of the HRE-2 is presented. The reactor simulates in a small size the nuclear, chemical, mechanical, and hydrodynamic characteristics believed typical of large reactors of this type. The simulation is made possible largely by the use of a beryllium reflector between the uranyl sulfate solution core and the thoria pellet fertile blanket. The nuclear calculations indicate an initial gross breeding ratio of 1.07 for a completely blanketed reactor fueled with U233.