ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Craig E. Peterson, John G. Shatford, Ardesar Irani, Nicholas G. Trikouros, Antonio F. Dias, Lance J. Agee
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 233-244
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3028
Articles are hosted by Taylor and Francis Online.
A main-steam-line-break accident analysis for Three Mile Island Unit 1 is performed with point kinetics and three-dimensional kinetics with RETRAN-3D MOD002. These analyses were performed to demonstrate differences in results that can be expected due to different reactor kinetics models. To illustrate the difference in kinetics models, the RETRAN-3D models used for both analyses were the same with the exception of the reactor core modeling. The key assumptions and methods used to model loop mixing are described.The point-kinetics analysis demonstrates a significant return-to-power following the reactor trip while the three-dimensional kinetics case does not. This study shows that three-dimensional core transient modeling provides margin to recriticality over a point-kinetics approach. Such margin is desirable to allow for power uprate and extended refueling cycles.