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
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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June 2025
Nuclear Technology
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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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.