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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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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.
C. J. Jackson, D. G. Cacuci, H. B. Finnemann
Nuclear Science and Engineering | Volume 131 | Number 2 | February 1999 | Pages 164-186
Technical Paper | doi.org/10.13182/NSE99-A2026
Articles are hosted by Taylor and Francis Online.
A dimensionally adaptive, automatic switching algorithm is presented that has been developed for the RELAP5/PANBOX coupled thermal-hydraulics and neutron kinetics code system to switch between three-dimensional (3-D), one-dimensional (1-D), and point neutron kinetics models during a transient calculation. The switching criteria from higher- to lower-dimensional models are based on the time evolution of the flux shape, while the switching criteria from lower-dimensional models to the 3-D model are based on error estimates and reactivity criteria. Calculations of main-steam-line-break, control-rod-ejection, and boron-dilution transients have been used to validate the dimensionally adaptive automatic switching algorithm. These validation calculations show that the results produced by the automatic switching algorithm retain the accuracy of the 3-D reference calculations. Notably, they are considerably faster, typically requiring only 30 to 70% of the CPU time needed by the 3-D reference calculations. Furthermore, our calculations confirm that a 3-D neutron kinetics model is indeed required for these reactor safety transients by showing that the point-kinetics and 1-D models are by themselves very inaccurate.