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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
A. Bousbia Salah, S. C. Ceuca, R. Puragliesi, R. Mukin, A. Grahn, S. Kliem, J. Vlassenbroeck, H. Austregesilo
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 293-314
Technical Paper | doi.org/10.1080/00295450.2018.1461517
Articles are hosted by Taylor and Francis Online.
Advanced three-dimensional (3-D) computational tools are increasingly being used to simulate complex phenomena occurring during scenarios involving operational transients and accidents in nuclear power plants. Among these scenarios, one can mention the asymmetric coolant mixing under natural-circulation flow regimes. This issue motivated some detailed experimental investigations carried out within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency PKL projects. The aim was not only to assess the mixing phenomenon in the reactor pressure vessel but also to provide experimental data for computer code validations and more specifically thermal-hydraulic system codes with 3-D capabilities. In the current study, the ROCOM/PKL-3 T2.3 experimental test is assessed using, on one hand, thermal-hydraulic system codes with 3-D capabilities and, on the other hand, computational fluid dynamics computational tools. The results emphasize the capabilities and the differences among the considered computational tools as well as their suitability for such purposes.